Radiological characterization survey of the former Diamond Magnesium Company Company site, 720 Fairport-Nursery Road, Painesville, Ohio (DMP001, DMP002)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Foley, R.D.; Carrier, R.F.

At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory performed an investigative radiological survey at the former Diamond Magnesium Company (DMC) site at 720 Fairport-Nursery Road, Painesville, Ohio, in September 1990. The purpose of the survey was to determine if the site is contaminated with radioactive residues as a result of federal government operation in the development of nuclear energy for defense-related projects. The survey of the site, separate parcels of which are currently owned by the Uniroyal Chemical Company (DMP001) and the Lonza Chemical Company (DMP002), included a gamma scan overmore » the ground surface, determination of gamma exposure rates at the surface and at 1 m above the surface at grid points, collection and radionuclide analysis of soil samples, and directly measured radiation levels inside three buildings used during original DMC processing. Results of the survey revealed widespread radiological contamination outdoors on the Uniroyal property and several isolated spots of elevated radiation levels on the Lonza property. The contaminants consisted of radium, uranium, and thorium in surface and subsurface soil in concentrations exceeding DOE guidelines for the release of property for unrestricted use.« less

Toxicology profiles of chemical and radiological contaminants at Hanford

DOE Office of Scientific and Technical Information (OSTI.GOV)

Harper, B.L.; Strenge, D.L.; Stenner, R.D.

1995-07-01

This document summarizes toxicology information required under Section 3.3 (Toxicity Assessment) of HSRAM, and can also be used to develop the short toxicology profiles required in site assessments (described in HSRAM, Section 3.3.5). Toxicology information is used in the dose-response step of the risk assessment process. The dose-response assessment describes the quantitative relationship between the amount of exposure to a substance and the extent of toxic injury or disease. Data are derived from animal studies or, less frequently, from studies in exposed human populations. The risks of a substance cannot be ascertained with any degree of confidence unless dose-response relationsmore » are quantified. This document summarizes dose-response information available from the US Environmental Protection Agency (EPA). The contaminants selected for inclusion in this document represent most of the contaminants found at Hanford (both radiological and chemical), based on sampling and analysis performed during site investigations, and historical information on waste disposal practices at the Hanford Site.« less

Understanding Contamination; Twenty Years of Simulating Radiological Contamination

DOE Office of Scientific and Technical Information (OSTI.GOV)

Emily Snyder; John Drake; Ryan James

A wide variety of simulated contamination methods have been developed by researchers to reproducibly test radiological decontamination methods. Some twenty years ago a method of non-radioactive contamination simulation was proposed at the Idaho National Laboratory (INL) that mimicked the character of radioactive cesium and zirconium contamination on stainless steel. It involved baking the contamination into the surface of the stainless steel in order to 'fix' it into a tenacious, tightly bound oxide layer. This type of contamination was particularly applicable to nuclear processing facilities (and nuclear reactors) where oxide growth and exchange of radioactive materials within the oxide layer becamemore » the predominant model for material/contaminant interaction. Additional simulation methods and their empirically derived basis (from a nuclear fuel reprocessing facility) are discussed. In the last ten years the INL, working with the Defense Advanced Research Projects Agency (DARPA) and the National Homeland Security Research Center (NHSRC), has continued to develop contamination simulation methodologies. The most notable of these newer methodologies was developed to compare the efficacy of different decontamination technologies against radiological dispersal device (RDD, 'dirty bomb') type of contamination. There are many different scenarios for how RDD contamination may be spread, but the most commonly used one at the INL involves the dispersal of an aqueous solution containing radioactive Cs-137. This method was chosen during the DARPA projects and has continued through the NHSRC series of decontamination trials and also gives a tenacious 'fixed' contamination. Much has been learned about the interaction of cesium contamination with building materials, particularly concrete, throughout these tests. The effects of porosity, cation-exchange capacity of the material and the amount of dirt and debris on the surface are very important factors. The interaction of the contaminant/substrate with the particular decontamination technology is also very important. Results of decontamination testing from hundreds of contaminated coupons have lead to certain conclusions about the contamination and the type of decontamination methods being deployed. A recent addition to the DARPA initiated methodology simulates the deposition of nuclear fallout. This contamination differs from previous tests in that it has been developed and validated purely to simulate a 'loose' type of contamination. This may represent the first time that a radiologically contaminated 'fallout' stimulant has been developed to reproducibly test decontamination methods. While no contaminant/methodology may serve as a complete example of all aspects that could be seen in the field, the study of this family of simulation methods provides insight into the nature of radiological contamination.« less

Corrective Action Investigation Plan for Corrective Action Unit 106: Areas 5, 11 Frenchman Flat Atmospheric Sites, Nevada National Security Site, Nevada

DOE Office of Scientific and Technical Information (OSTI.GOV)

Patrick Matthews

2011-07-01

Corrective Action Unit 106 comprises the four corrective action sites (CASs) listed below: • 05-20-02, Evaporation Pond • 05-23-05, Atmospheric Test Site - Able • 05-45-04, 306 GZ Rad Contaminated Area • 05-45-05, 307 GZ Rad Contaminated Area These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viablemore » CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 19, 2010, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 106. The presence and nature of contamination at CAU 106 will be evaluated based on information collected from a field investigation. The CAU includes land areas impacted by the release of radionuclides from groundwater pumping during the Radionuclide Migration study program (CAS 05-20-02), a weapons-related airdrop test (CAS 05-23-05), and unknown support activities at two sites (CAS 05-45-04 and CAS 05-45-05). The presence and nature of contamination from surface-deposited radiological contamination from CAS 05-23-05, Atmospheric Test Site - Able, and other types of releases (such as migration and excavation as well as any potential releases discovered during the investigation) from the remaining three CASs will be evaluated using soil samples collected from the locations most likely containing contamination, if present. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the corrective action investigation for CAU 106 includes the following activities: • Conduct radiological surveys. • Collect and submit environmental samples for laboratory analysis to determine internal dose rates and the presence of contaminants of concern. • If contaminants of concern are present, collect additional samples to define the extent of the contamination and determine the area where the total effective dose at the site exceeds final action levels (i.e., corrective action boundary). • Collect samples of investigation-derived waste, as needed, for waste management purposes.« less

Corrective Action Investigation Plan for Corrective Action Unit 541: Small Boy Nevada National Security Site and Nevada Test and Training Range, Nevada with ROTC 1

DOE Office of Scientific and Technical Information (OSTI.GOV)

Matthews, Patrick

Corrective Action Unit (CAU) 541 is co-located on the boundary of Area 5 of the Nevada National Security Site and Range 65C of the Nevada Test and Training Range, approximately 65 miles northwest of Las Vegas, Nevada. CAU 541 is a grouping of sites where there has been a suspected release of contamination associated with nuclear testing. This document describes the planned investigation of CAU 541, which comprises the following corrective action sites (CASs): 05-23-04, Atmospheric Tests (6) - BFa Site; 05-45-03, Atmospheric Test Site - Small Boy. These sites are being investigated because existing information on the nature andmore » extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the investigation report. The sites will be investigated based on the data quality objectives (DQOs) developed on April 1, 2014, by representatives of the Nevada Division of Environmental Protection; U.S. Air Force; and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 541. The site investigation process also will be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The potential contamination sources associated with CASs 05-23-04 and 05-45-03 are from nuclear testing activities conducted at the Atmospheric Tests (6) - BFa Site and Atmospheric Test Site - Small Boy sites. The presence and nature of contamination at CAU 541 will be evaluated based on information collected from field investigations. Radiological contamination will be evaluated based on a comparison of the total effective dose at sample locations to the dose-based final action level. The total effective dose will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample location will be used to measure external radiological dose. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS.« less

Health care facility-based decontamination of victims exposed to chemical, biological, and radiological materials.

PubMed

Koenig, Kristi L; Boatright, Connie J; Hancock, John A; Denny, Frank J; Teeter, David S; Kahn, Christopher A; Schultz, Carl H

2008-01-01

Since the US terrorist attacks of September 11, 2001, concern regarding use of chemical, biological, or radiological weapons is heightened. Many victims of such an attack would present directly to health care facilities without first undergoing field decontamination. This article reviews basic tenets and recommendations for health care facility-based decontamination, including regulatory concerns, types of contaminants, comprehensive decontamination procedures (including crowd control, triage, removal of contaminated garments, cleaning of body contaminants, and management of contaminated materials and equipment), and a discussion of methods to achieve preparedness.

Turbo FRMAC 2011

DOE Office of Scientific and Technical Information (OSTI.GOV)

Fulton, John; Gallagher, Linda K.; Whitener, Dustin

The Turbo FRMAC (TF) software automates the calculations described in volumes 1-3 of "The Federal Manual for Assessing Environmental Data During a Radiological Emergency" (2010 version). This software automates the process of assessing radiological data during a Federal Radiological Emergency. The manual upon which the software is based is unclassified and freely available on the Internet. TF takes values generated by field samples or computer dispersion models and assesses the data in a way which is meaningful to a decision maker at a radiological emergency; such as, do radiation values exceed city, state, or federal limits; should the crops bemore » destroyed or can they be utilized; do residents need to be evacuated, sheltered in place, or should another action taken. The software also uses formulas generated by the EPA, FDA, and other federal agencies to generate field observable values specific to the radiological event that can be used to determine where regulatory limit values are exceeded. In addition to these calculations, TF calculates values which indicate how long an emergency worker can work in the contaminated area during a radiological emergency, the dose received from drinking contaminated water or milk, the dose from eating contaminated food, the does expected down or upwind of a given field sample, along with a significant number of other similar radiological health values.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Rick Demmer; John Drake; Ryan James, PhD

Over the last 50 years, the study of radiological contamination and decontamination has expanded significantly. This paper addresses the mechanisms of radiological contamination that have been reported and then discusses which methods have recently been used during performance testing of several different decontamination technologies. About twenty years ago the Idaho Nuclear Technology Engineering Center (INTEC) at the INL began a search for decontamination processes which could minimize secondary waste. In order to test the effectiveness of these decontamination technologies, a new simulated contamination, termed SIMCON, was developed. SIMCON was designed to replicate the types of contamination found on stainless steel,more » spent fuel processing equipment. Ten years later, the INL began research into methods for simulating urban contamination resulting from a radiological dispersal device (RDD). This work was sponsored by the Defense Advanced Research Projects Agency (DARPA) and included the initial development an aqueous application of contaminant to substrate. Since 2007, research sponsored by the US Environmental Protection Agency (EPA) has advanced that effort and led to the development of a contamination method that simulates particulate fallout from an Improvised Nuclear Device (IND). The IND method diverges from previous efforts to create tenacious contamination by simulating a reproducible “loose” contamination. Examining these different types of contamination (and subsequent decontamination processes), which have included several different radionuclides and substrates, sheds light on contamination processes that occur throughout the nuclear industry and in the urban environment.« less

A comprehensive inventory of radiological and nonradiological contaminants in waste buried or projected to be buried in the subsurface disposal area of the INEL RWMC during the years 1984-2003, Volume 3

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1995-05-01

This is the third volume of this comprehensive report of the inventory of radiological and nonradiological contaminants in waste buried or projected to be buried in the subsurface disposal area of the Idaho National Engineering Laboratory. Appendix B contains a complete printout of contaminant inventory and other information from the CIDRA Database and is presented in volumes 2 and 3 of the report.

Estimates of radiological risk from depleted uranium weapons in war scenarios.

PubMed

Durante, Marco; Pugliese, Mariagabriella

2002-01-01

Several weapons used during the recent conflict in Yugoslavia contain depleted uranium, including missiles and armor-piercing incendiary rounds. Health concern is related to the use of these weapons, because of the heavy-metal toxicity and radioactivity of uranium. Although chemical toxicity is considered the more important source of health risk related to uranium, radiation exposure has been allegedly related to cancers among veterans of the Balkan conflict, and uranium munitions are a possible source of contamination in the environment. Actual measurements of radioactive contamination are needed to assess the risk. In this paper, a computer simulation is proposed to estimate radiological risk related to different exposure scenarios. Dose caused by inhalation of radioactive aerosols and ground contamination induced by Tomahawk missile impact are simulated using a Gaussian plume model (HOTSPOT code). Environmental contamination and committed dose to the population resident in contaminated areas are predicted by a food-web model (RESRAD code). Small values of committed effective dose equivalent appear to be associated with missile impacts (50-y CEDE < 5 mSv), or population exposure by water-independent pathways (50-y CEDE < 80 mSv). The greatest hazard is related to the water contamination in conditions of effective leaching of uranium in the groundwater (50-y CEDE < 400 mSv). Even in this worst case scenario, the chemical toxicity largely predominates over radiological risk. These computer simulations suggest that little radiological risk is associated to the use of depleted uranium weapons.

Radiological survey results at Building 22, Washington Navy Yard, Washington, D.C. (WNS001)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Rodriguez, R.E.; Foley, R.D.; Uziel, M.S.

A radiological survey was conducted in a portion of Building 22 at the Washington Navy Yard, Washington, D.C., on December 13, 1995. The survey was performed because former employees thought the area surveyed had some previous association with radioactive material. Employees remembered seeing radiation signs in the area and indicated that personnel occupying this area wore dosimeters. Two rooms in the survey area were surrounded by 1-ft-thick poured concrete walls and similar 6-in.-thick ceilings, and situated on top of a 1-ft-thick concrete slab, a configuration commonly used for radiation shielding in industrial radiography facilities. The radiological survey showed no gamma,more » beta-gamma, or alpha measurements above typical background levels. Low background radiation levels within the building indicated that even if low-level contamination were present beneath the tile, or larger amounts of contamination beneath the concrete slab, it poses no radiological hazard to building inhabitants under the present conditions. Further investigation may be required before drilling or demolition of the concrete slab. No photon radiation fields from sealed gamma sources or x-ray sources were detectable at the time of the survey. Gamma spectrometry analysis revealed no gamma emitters above typical background concentrations in one sediment and one water sample collected from a pit in the open bay area.« less

Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 415: Project 57 No. 1 Plutonium Dispersion (NTTR), Nevada, Revision 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Matthews, Patrick; Burmeister, Mark

2014-04-01

This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the actions needed to achieve closure for Corrective Action Unit (CAU) 415, Project 57 No. 1 Plutonium Dispersion (NTTR). CAU 415 is located on Range 4808A of the Nevada Test and Training Range (NTTR) and consists of one corrective action site: NAFR-23-02, Pu Contaminated Soil. The CAU 415 site consists of the atmospheric release of radiological contaminants to surface soil from the Project 57 safety experiment conducted in 1957. The safety experiment released plutonium (Pu), uranium (U), and americium (Am) to the surface soil over an area of approximately 1.9 squaremore » miles. This area is currently fenced and posted as a radiological contamination area. Vehicles and debris contaminated by the experiment were subsequently buried in a disposal trench within the surface-contaminated, fenced area and are assumed to have released radiological contamination to subsurface soils. Potential source materials in the form of pole-mounted electrical transformers were also identified at the site and will be removed as part of closure activities.« less

The long-term problems of contaminated land: Sources, impacts and countermeasures

DOE Office of Scientific and Technical Information (OSTI.GOV)

Baes, C.F. III

1986-11-01

This report examines the various sources of radiological land contamination; its extent; its impacts on man, agriculture, and the environment; countermeasures for mitigating exposures; radiological standards; alternatives for achieving land decontamination and cleanup; and possible alternatives for utilizing the land. The major potential sources of extensive long-term land contamination with radionuclides, in order of decreasing extent, are nuclear war, detonation of a single nuclear weapon (e.g., a terrorist act), serious reactor accidents, and nonfission nuclear weapons accidents that disperse the nuclear fuels (termed ''broken arrows'').

Fixation of Radiological Contamination; International Collaborative Development

DOE Office of Scientific and Technical Information (OSTI.GOV)

Rick Demmer

2013-03-01

A cooperative international project was conducted by the Idaho National Laboratory (INL) and the United Kingdom’s National Nuclear Laboratory (NNL) to integrate a capture coating with a high performance atomizing process. The initial results were promising, and lead to further trials. The somewhat longer testing and optimization process has resulted in a product that could be demonstrated in the field to reduce airborne radiological dust and contamination.

Results of the radiological survey at 31 Lily Street, Albany, New York (AL171)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Espergren, M.L.; Marley, J.L.

1987-12-01

A number of properties in the Albany/Colonie area have been identified as being potentially contaminated with uranium originating from the former National Lead Company's uranium forming plant in Colonie, New York. The property at 31 Lily Street in Albany, New York was the subject of a radiological investigation initiated July 19, 1986. The residential property consists of a one-story frame house located on a rectangular lot. An asphalt driveway connects the house to the street. A diagram of the property showing the approximate boundaries and the 4-m grid network established for measurements outside the house is shown. The lot includedmore » in the radiological survey was /approximately/18 m wide by 25 m deep. Front and rear views of the property are shown. 13 refs., 5 figs., 5 tabs.« less

Results of the radiological survey at 23 Lily Street, Albany, New York

DOE Office of Scientific and Technical Information (OSTI.GOV)

Espegren, M.L.; Marley, J.L.; Carrier, R.F.

1987-12-01

A number of properties in the Albany/Colonie area have been identified as being potentially contaminated with uranium originating from the former National Lead Company's uranium forming plant in Colonie, New York. The property at 23 Lily Street in Albany, New York (AL174), was the subject of a radiological investigation initiated July 21, 1986. The residential property consists of a two-story frame house located on a rectangular lot. An asphalt driveway connects the house to the street. A diagram of the property showing the approximate boundaries and the 5-m grid network established for measurements outside the house is shown. The lotmore » included in the radiological survey was /approximately/20 m wide by 30 m deep. Front and side views of the property are shown. 13 refs., 5 figs., 5 tabs.« less

Results of the radiological survey at 20 Lily Street, Albany, New York (AL168)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Espegren, M.L.; Marley, J.L.

1987-12-01

A number of properties in the Albany/Colonie area have been identified as being potentially contaminated with uranium originating from the former National Lead Company's uranium forming plant in Colonie, New York. The property at 20 Lily Street in Albany, New York, was the subject of a radiological investigation initiated July 18, 1986. The residential property consists of a two-story frame house located on a rectangular lot. An asphalt driveway connects the house to the street. A diagram of the property showing the approximate boundaries and the 5-m grid network established for measurements outside the house is shown. the lot includedmore » in the radiological survey was /approximately/14 m wide by 37 m deep. Front and rear views of the property are shown. 13 refs., 5 figs., 5 tabs.« less

Results of the radiological survey at 22 Lily Street, Albany, New York (AL169)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Espegren, M.L.; Marley, J.L.

1987-12-01

A number of properties in the Albany/Colonie area have been identified as being potentially contaminated with uranium originating from the former National Lead Company's uranium forming plant in Colonie, New York. The property at 22 Lily Street in Albany, New York, was the subject of a radiological investigation initiated July 18, 1986. The residential property consists of a two-story frame house located on a rectangular lot. An asphalt driveway connects the house to the street. A diagram of the property showing the approximate boundaries and the 4-m grid network established for measurements outside the house is shown. The lot includedmore » in the radiological survey was /approximately/11 m wide by 30 m deep. Front and rear views of the property are shown. 13 refs., 5 figs., 5 tabs.« less

Results of the radiological survey at 21 Lily Street, Albany, New York

DOE Office of Scientific and Technical Information (OSTI.GOV)

Espegren, M.L.; Marley, J.L.

1987-12-01

A number of properties in the Albany/Colonie area have been identified as being potentially contaminated with uranium originating from the former National Lead Company's uranium forming plant in Colonie, New York. The property at 21 Lily Street in Albany, New York (AL164) was the subject of a radiological investigation initiated July 16, 1986. The residential property consists of a two-story frame house located on a rectangular lot. A gravel drive is located on the lot. A diagram of the property showing the approximate boundaries and the 5-m grid network established for measurements outside the house is shown. The lot includedmore » in the radiological survey was /approximately/21 m wide by 26 m deep. Front and rear views of the property are shown. 13 refs., 5 figs., 5 tabs.« less

Results of the radiological survey at 18 Lily Street, Albany, New York (AL167)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Espegren, M.L.; Marley, J.L.

1987-12-01

A number of properties in the Albany/Colonie area have been identified as being potentially contaminated with uranium originating from the former National Lead Company's uranium forming plant in Colonie, New York. The property at 18 Lily Street in Albany, New York was the subject of a radiological investigation initiated July 18, 1986. The residential property consists of a two-story frame house located on a rectangular lot. An asphalt driveway connects the house to the street. A diagram of the property showing the approximate boundaries and the 5-m grid network established for measurements outside the house is shown. The lot includedmore » in the radiological survey was /approximately/15 m wide by 37 m deep. Front and rear views of the property are shown. 13 refs., 5 figs., 5 tabs.« less

Results of the radiological survey at 15 Lily Street, Albany, New York (AL165)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Espegren, M.L.; Marley, J.L.

1987-12-01

A number of properties in the Albany/Colonie area have been identified as being potentially contaminated with uranium originating from the former National Lead Company's uranium forming plant in Colonie, New York. The property at 15 Lily Street in Albany, New York was the subject of a radiological investigation initiated July 17, 1986. The residential property consists of a one-story frame house located on a rectangular lot. An asphalt driveway connects the house to the street. A diagram of the property showing the approximate boundaries and the 4-m grid network established for measurements outside the house is shown. The lot includedmore » in the radiological survey was /approximately/20 m wide by 26 m deep. Front and rear views of the property are shown. 13 refs., 5 figs., 5 tabs.« less

Results of the radiological survey at 27 Lily Street, Albany, New York (AL172)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Espegren, M.L.; Marley, J.L.; Carrier, R.F.

1987-12-01

A number of properties in the Albany/Colonie area have been identified as being potentially contaminated with uranium originating from the former National Lead Company's uranium forming plant in Colonie, New York. The property at 27 Lily Street in Albany, New York, was the subject of a radiological investigation initiated July 19, 1986. The residential property consists of a two-story frame house located on a rectangular lot. An asphalt driveway connects the house to the street. A diagram of the property showing the approximate boundaries and the 5-m grid network established for measurements outside the house is shown. The lot includedmore » in the radiological survey was /approximately/20 m wide by 34 m deep. Front and rear views of the property are shown. 13 refs., 5 figs., 5 tabs.« less

Results of the radiological survey at 26 Lily Street, Albany, New York (AL170)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Espegren, M.L.; Marley, J.L.

1987-12-01

A number of properties in the Albany/Colonie area have been identified as being potentially contaminated with uranium originating from the former National Lead Company's uranium forming plant in Colonie, New York. The property at 26 Lily Street in Albany, New York, was the subject of a radiological investigation initiated July 18, 1986. The residential property consists of a two-story frame house located on a rectangular lot. An asphalt driveway connects the house to the street. A diagram of the property showing the approximate boundaries and the 10-m grid network established for measurements outside the house is shown. The lot includedmore » in the radiological survey was /approximately/29 m wide by 74 m deep. Front and rear views of the property are shown. 13 refs., 5 figs., 5 tabs.« less

Results of the radiological survey at 15 Keller Street, Albany, New York (AL176)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Espegren, M.L.; Marley, J.L.; Carrier, R.F.

1987-12-01

A number of properties in the Albany/Colonie area have been identified as being potentially contaminated with uranium originating from the former National Lead Company's uranium forming plant in Colonie, New York. The property at 15 Keller Street in Albany, New York was the subject of a radiological investigation initiated July 22, 1986. The residential property consists of a one-story frame house with an asphalt drive connects the house to the street. A diagram of the property showing the approximate boundaries and the grid network established for measurements outside the house is shown. The lot included in the radiological survey wasmore » /approximately/20 m wide by 27 m deep. Front and rear views of the property are shown. 13 refs., 5 figs., 5 tabs.« less

Investigation of the radiological impact on the coastal environment surrounding a fertilizer plant.

PubMed

El Samad, O; Aoun, M; Nsouli, B; Khalaf, G; Hamze, M

2014-07-01

This investigation was carried out in order to assess the marine environmental radioactive pollution and the radiological impact caused by a large production plant of phosphate fertilizer, located in the Lebanese coastal zone. Natural radionuclides ((238)U, (235)U, (232)Th, (226)Ra, (210)Po, (210)Pb, (40)K) and anthropogenic (137)Cs were measured by alpha and gamma spectrometry in seawater, sediment, biota and coastal soil samples collected from the area impacted by this industry. The limited environmental monitoring program within 2 km of the plant indicates localized contamination with radionuclides of the uranium decay chain mainly due to the transport, the storage of raw materials and the free release of phosphogypsum waste. Copyright © 2013 Elsevier Ltd. All rights reserved.

US screening of international travelers for radioactive contamination after the Japanese nuclear plant disaster in March 2011.

PubMed

Wilson, Todd; Chang, Arthur; Berro, Andre; Still, Aaron; Brown, Clive; Demma, Andrew; Nemhauser, Jeffrey; Martin, Colleen; Salame-Alfie, Adela; Fisher-Tyler, Frieda; Smith, Lee; Grady-Erickson, Onalee; Alvarado-Ramy, Francisco; Brunette, Gary; Ansari, Armin; McAdam, David; Marano, Nina

2012-10-01

On March 11, 2011, a magnitude 9.0 earthquake and subsequent tsunami damaged nuclear reactors at the Fukushima Daiichi complex in Japan, resulting in radionuclide release. In response, US officials augmented existing radiological screening at its ports of entry (POEs) to detect and decontaminate travelers contaminated with radioactive materials. During March 12 to 16, radiation screening protocols detected 3 travelers from Japan with external radioactive material contamination at 2 air POEs. Beginning March 23, federal officials collaborated with state and local public health and radiation control authorities to enhance screening and decontamination protocols at POEs. Approximately 543 000 (99%) travelers arriving directly from Japan at 25 US airports were screened for radiation contamination from March 17 to April 30, and no traveler was detected with contamination sufficient to require a large-scale public health response. The response highlighted synergistic collaboration across government levels and leveraged screening methods already in place at POEs, leading to rapid protocol implementation. Policy development, planning, training, and exercising response protocols and the establishment of federal authority to compel decontamination of travelers are needed for future radiological responses. Comparison of resource-intensive screening costs with the public health yield should guide policy decisions, given the historically low frequency of contaminated travelers arriving during radiological disasters.

Results of the survey activities and mobile gamma scanning in Monticello, Utah

DOE Office of Scientific and Technical Information (OSTI.GOV)

Little, C.A.; Berven, B.A.

The town of Monticello, Utah, was once the site of an active mill which processed vanadium ore (1942 to 1948), and uranium ore (1948 to 1960). Properties in the vicinity of that mill have become contaminated with radioactive material from ore processing. The Radiological Survey Activities (RASA) group at Oak Ridge National Laboratory (ORNL) was requested by the Division of Remedial Action Projects (DRAP) in the Department of Energy (DOE) to: (1) identify potentially contaminated properties; (2) assess natural background radiation levels; and (3) rapidly assess the magnitude, extent, and type (i.e. ore, tailings, etc.) of contamination present on thesemore » properties (if any). This survey was conducted by RASA during April 1983. In addition to the 114 properties previously identified from historical information, the ORNL mobile gamma scanning van located 36 new properties exhibiting anomalous gamma radiation levels. Onsite surveys were conducted on 145 of the 150 total properties identified either historically or with the gamma scanning van. Of these 145 properties, 122 of them appeared to have some type of contaminated material present on them; however, only 48 appeared to be contaminated to the extent where they were in excess of Environmental Protection Agency (EPA) criteria (40 CFR 192). Twenty-one other properties were recommended for additional investigation (indoor gamma scanning and radon daughter measurements); of these, only ten required further analysis. This report provides the detailed data and analyses related to the radiological survey efforts performed by ORNL in Monticello, Utah.« less

Closure Report for Corrective Action Unit 412: Clean Slate I Plutonium Dispersion (TTR) Tonopah Test Range, Nevada, Revision 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Matthews, Patrick

This Closure Report (CR) presents information supporting the clean closure of Corrective Action Unit (CAU) 412: Clean Slate I Plutonium Dispersion (TTR), located on the Tonopah Test Range, Nevada. CAU 412 consists of a release of radionuclides to the surrounding soil from a storage–transportation test conducted on May 25, 1963. Corrective action investigation (CAI) activities were performed in April and May 2015, as set forth in the Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 412: Clean Slate I Plutonium Dispersion (TTR), Tonopah Test Range, Nevada; and in accordance with the Soils Activity Quality Assurance Plan. Themore » purpose of the CAI was to fulfill data needs as defined during the data quality objectives process. The CAU 412 dataset of investigation results was evaluated based on a data quality assessment. This assessment demonstrated the dataset is complete and acceptable for use in fulfilling the data needs identified by the data quality objectives process. This CR provides documentation and justification for the clean closure of CAU 412 under the FFACO without further corrective action. This justification is based on historical knowledge of the site, previous site investigations, implementation of the 1997 interim corrective action, and the results of the CAI. The corrective action of clean closure was confirmed as appropriate for closure of CAU 412 based on achievement of the following closure objectives: Radiological contamination at the site is less than the final action level using the ground troops exposure scenario (i.e., the radiological dose is less than the final action level): Removable alpha contamination is less than the high contamination area criterion: No potential source material is present at the site, and any impacted soil associated with potential source material has been removed so that remaining soil contains contaminants at concentrations less than the final action levels: and There is sufficient information to characterize investigation and remediation waste for disposal.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Loar, J.M.; Adams, S.M.; Bailey, R.D.

As a condition of the National Pollutant Discharge Elimination System (NPDES) permit issued to Oak Ridge National Laboratory (ORNL) on April 1, 1985, a Biological Monitoring and Abatement Program (BMAP) was developed for White Oak Creek (WOC); selected tributaries of WOC, including Fifth Creek, First Creek, Melton Branch, and Northwest Tributary; and the Clinch River. The BMAP currently consists of six major tasks that address both radiological and nonradiological contaminants in the aquatic and terrestrial environs at ORNL. These are (1) toxicity monitoring, (2) bioaccumulation monitoring of nonradiological contaminants in aquatic biota, (3) biological indicator studies, (4) instream ecological monitoring,more » (5) assessment of contaminants in the terrestrial environment, and (6) radioecology of WOC and White Oak Lake (WOL). The investigation of contaminant transport, distribution, and fate in the WOC embayment-Clinch River-Watts Bar Reservoir system was originally a task of the BMAP but, in 1988, was incorporated into the Resource Conservation and Recovery Act Facility Investigation for the Clinch River, a separate study to assess offsite contamination from all three Department of Energy facilities in Oak Ridge.« less

The use of unmanned aerial systems for the mapping of legacy uranium mines.

PubMed

Martin, P G; Payton, O D; Fardoulis, J S; Richards, D A; Scott, T B

2015-05-01

Historical mining of uranium mineral veins within Cornwall, England, has resulted in a significant amount of legacy radiological contamination spread across numerous long disused mining sites. Factors including the poorly documented and aged condition of these sites as well as the highly localised nature of radioactivity limit the success of traditional survey methods. A newly developed terrain-independent unmanned aerial system [UAS] carrying an integrated gamma radiation mapping unit was used for the radiological characterisation of a single legacy mining site. Using this instrument to produce high-spatial-resolution maps, it was possible to determine the radiologically contaminated land areas and to rapidly identify and quantify the degree of contamination and its isotopic nature. The instrument was demonstrated to be a viable tool for the characterisation of similar sites worldwide. Copyright © 2015 The Authors. Published by Elsevier Ltd.. All rights reserved.

Corrective Action Decision Document/Closure Report for Corrective Action Unit 375: Area 30 Buggy Unit Craters, Nevada National Security Site, Nevada, Revision 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Patrick Matthews

2011-08-01

Corrective Action Unit 375 comprises three corrective action sites (CASs): (1) 25-23-22, Contaminated Soils Site; (2) 25-34-06, Test Cell A Bunker; and (3) 30-45-01, U-30a, b, c, d, e Craters. The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 375 based on the implementation of corrective action of closure in place with administrative controls at CAS 25-23-22, no further action at CAS 25-34-06, and closure in place with administrative controls and removal of potential source material (PSM) at CAS 30-45-01. Corrective action investigation (CAI) activities weremore » performed from July 28, 2010, through April 4, 2011, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 375: Area 30 Buggy Unit Craters. The approach for the CAI was divided into two facets: investigation of the primary release of radionuclides, and investigation of other releases (migration in washes and chemical releases). The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 375 dataset of investigation results was evaluated based on the data quality assessment. This assessment demonstrated the dataset is acceptable for use in fulfilling the DQO data needs. Investigation results were evaluated against final action levels (FALs) established in this document. A radiological dose FAL of 25 millirem per year was established based on the Remote Work Area exposure scenario (336 hours of annual exposure). Radiological doses exceeding the FAL were assumed to be present within the default contamination boundaries at CASs 25-23-22 and 30-45-01. No contaminants were identified at CAS 25-34-06, and no corrective action is necessary. Potential source material in the form of lead plate, lead-acid batteries, and oil within an abandoned transformer were identified at CAS 30-45-01, and corrective actions were undertaken that consisted of removing the PSM. Use restrictions and warning signs were implemented for the remaining radiological contamination at CASs 25-23-22 and 30-45-01. These use restrictions were recorded in the FFACO database; the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Facility Information Management System; and the NNSA/NSO CAU/CAS files. Therefore, NNSA/NSO provides the following recommendations: (1) No further corrective actions are necessary for CAU 375; (2) A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 375; and (3) Move CAU 375 from Appendix III to Appendix IV of the FFACO.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Demmer, Rick; Fox, Don; Reese, Stephen

The Idaho National Laboratory (INL) and the United Kingdom (UK) National Nuclear Laboratory (NNL) have been collaborating for several years on materials and methods for the fogged/misted introduction of fixatives into radiologically contaminated facilities. The objective of the project is to deliver a process for reducing airborne radiological and/or mercury contamination and affixing loose contamination in place, thereby reducing contamination risk to employees and decreasing D&D cost and schedule. The developed process provides a reliable, unmanned method of introducing a coating that captures and fixes contamination in place within facilities. The INL coating, termed FX2, has undergone extensive non-radiological testing,more » including determination that it is non-flammable, affixes contamination and flows well through unusual geometries (testing at Florida International University). A series of non-active fogging trials for activity knock/tie-down application have been completed at NNL Workington on behalf of Idaho National Laboratory (INL). These trials performed by the NNL employed commercially available agricultural fogging equipment and the INL’s knock/tie-down latex formulation (FX-2). This testing successfully demonstrated the ability of the fogging devices to successfully spray the FX-2 formulation within various scenarios, and prepared the project for a radioactive trial. The INL has also developed a mercury vapor reducing form of the coating termed FX-Hg, which has shown great promise in laboratory studies.« less

Characterizing Contamination and Assessing Exposure, Risk and Resilience

EPA Pesticide Factsheets

EPA supports its responders' ability to characterize site contamination by developing sampling protocols, sample preparation methods, and analytical methods for chemicals, biotoxins, microbial pathogens, and radiological agents.

10 CFR 835.1102 - Control of areas.

Code of Federal Regulations, 2010 CFR

2010-01-01

... DEPARTMENT OF ENERGY OCCUPATIONAL RADIATION PROTECTION Radioactive Contamination Control § 835.1102 Control... transfer of removable contamination to locations outside of radiological areas under normal operating conditions. (b) Any area in which contamination levels exceed the values specified in appendix D of this part...

Contamination of X-ray Cassettes with Methicillin-resistant Staphylococcus aureus and Methicillin-resistant Staphylococcus haemolyticus in a Radiology Department

PubMed Central

Kim, Han-Sung; Park, Ji-Young; Koo, Hyun-Sook; Choi, Chul-Sun; Song, Wonkeun; Cho, Hyoun Chan; Lee, Kyu Man

2012-01-01

Background We performed surveillance cultures of the surfaces of X-ray cassettes to assess contamination with methicillin-resistant Staphylococcus aureus (MRSA). Methods The surfaces of 37 X-ray cassettes stored in a radiology department were cultured using mannitol salt agar containing 6 µg/mL oxacillin. Suspected methicillin-resistant staphylococcal colonies were isolated and identified by biochemical testing. Pulsed-field gel electrophoresis (PFGE) analysis was performed to determine the clonal relationships of the contaminants. Results Six X-ray cassettes (16.2%) were contaminated with MRSA. During the isolation procedure, we also detected 19 X-ray cassettes (51.4%) contaminated with methicillin-resistant Staphylococcus haemolyticus (MRSH), identified as yellow colonies resembling MRSA on mannitol salt agar. PFGE analysis of the MRSA and MRSH isolates revealed that most isolates of each organism were identical or closely related to each other, suggesting a common source of contamination. Conclusions X-ray cassettes, which are commonly in direct contact with patients, were contaminated with MRSA and MRSH. In hospital environments, contaminated X-ray cassettes may serve as fomites for methicillin-resistant staphylococci. PMID:22563556

Contamination of X-ray cassettes with methicillin-resistant Staphylococcus aureus and methicillin-resistant Staphylococcus haemolyticus in a radiology department.

PubMed

Kim, Jae-Seok; Kim, Han-Sung; Park, Ji-Young; Koo, Hyun-Sook; Choi, Chul-Sun; Song, Wonkeun; Cho, Hyoun Chan; Lee, Kyu Man

2012-05-01

We performed surveillance cultures of the surfaces of X-ray cassettes to assess contamination with methicillin-resistant Staphylococcus aureus (MRSA). The surfaces of 37 X-ray cassettes stored in a radiology department were cultured using mannitol salt agar containing 6 µg/mL oxacillin. Suspected methicillin-resistant staphylococcal colonies were isolated and identified by biochemical testing. Pulsed-field gel electrophoresis (PFGE) analysis was performed to determine the clonal relationships of the contaminants. Six X-ray cassettes (16.2%) were contaminated with MRSA. During the isolation procedure, we also detected 19 X-ray cassettes (51.4%) contaminated with methicillin-resistant Staphylococcus haemolyticus (MRSH), identified as yellow colonies resembling MRSA on mannitol salt agar. PFGE analysis of the MRSA and MRSH isolates revealed that most isolates of each organism were identical or closely related to each other, suggesting a common source of contamination. X-ray cassettes, which are commonly in direct contact with patients, were contaminated with MRSA and MRSH. In hospital environments, contaminated X-ray cassettes may serve as fomites for methicillin-resistant staphylococci.

Multiservice Tactics, Techniques, and Procedures for Chemical, Biological, Radiological and Nuclear Contamination Avoidance

DTIC Science & Technology

2006-02-01

Radiological and Nuclear Contamination Avoidance 5a. CONTRACT NUMBER 5b. GRANT NUMBER 5c. PROGRAM ELEMENT NUMBER 6. AUTHOR( S ) 5d. PROJECT NUMBER 5e. TASK...NUMBER 5f. WORK UNIT NUMBER 7. PERFORMING ORGANIZATION NAME( S ) AND ADDRESS(ES) Federation of American Scientists 1717 K St., NW Suite 209 Washington...DC 20036 8. PERFORMING ORGANIZATION REPORT NUMBER 9. SPONSORING/MONITORING AGENCY NAME( S ) AND ADDRESS(ES) 10. SPONSOR/MONITOR’S ACRONYM( S ) 11

SUDOQU, a new dose-assessment methodology for radiological surface contamination.

PubMed

van Dillen, Teun; van Dijk, Arjan

2018-06-12

A new methodology has been developed for the assessment of the annual effective dose resulting from removable and fixed radiological surface contamination. It is entitled SUDOQU (SUrface DOse QUantification) and it can for instance be used to derive criteria for surface contamination related to the import of non-food consumer goods, containers and conveyances, e.g., limiting values and operational screening levels. SUDOQU imposes mass (activity)-balance equations based on radioactive decay, removal and deposition processes in indoor and outdoor environments. This leads to time-dependent contamination levels that may be of particular importance in exposure scenarios dealing with one or a few contaminated items only (usually public exposure scenarios, therefore referred to as the 'consumer' model). Exposure scenarios with a continuous flow of freshly contaminated goods also fall within the scope of the methodology (typically occupational exposure scenarios, thus referred to as the 'worker model'). In this paper we describe SUDOQU, its applications, and its current limitations. First, we delineate the contamination issue, present the assumptions and explain the concepts. We describe the relevant removal, transfer, and deposition processes, and derive equations for the time evolution of the radiological surface-, air- and skin-contamination levels. These are then input for the subsequent evaluation of the annual effective dose with possible contributions from external gamma radiation, inhalation, secondary ingestion (indirect, from hand to mouth), skin contamination, direct ingestion and skin-contact exposure. The limiting effective surface dose is introduced for issues involving the conservatism of dose calculations. SUDOQU can be used by radiation-protection scientists/experts and policy makers in the field of e.g. emergency preparedness, trade and transport, exemption and clearance, waste management, and nuclear facilities. Several practical examples are worked out demonstrating the potential applications of the methodology. . Creative Commons Attribution license.

Corrective Action Investigation Plan for Corrective Action Unit 410: Waste Disposal Trenches, Tonopah Test Range, Nevada, Revision 0 (includes ROTCs 1, 2, and 3)

DOE Office of Scientific and Technical Information (OSTI.GOV)

NNSA /NV

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 410 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 410 is located on the Tonopah Test Range (TTR), which is included in the Nevada Test and Training Range (formerly the Nellis Air Force Range) approximately 140 miles northwest of Las Vegas, Nevada. This CAU is comprised of five Corrective Action Sites (CASs): TA-19-002-TAB2, Debris Mound; TA-21-003-TANL, Disposal Trench; TA-21-002-TAAL,more » Disposal Trench; 09-21-001-TA09, Disposal Trenches; 03-19-001, Waste Disposal Site. This CAU is being investigated because contaminants may be present in concentrations that could potentially pose a threat to human health and/or the environment, and waste may have been disposed of with out appropriate controls. Four out of five of these CASs are the result of weapons testing and disposal activities at the TTR, and they are grouped together for site closure based on the similarity of the sites (waste disposal sites and trenches). The fifth CAS, CAS 03-19-001, is a hydrocarbon spill related to activities in the area. This site is grouped with this CAU because of the location (TTR). Based on historical documentation and process know-ledge, vertical and lateral migration routes are possible for all CASs. Migration of contaminants may have occurred through transport by infiltration of precipitation through surface soil which serves as a driving force for downward migration of contaminants. Land-use scenarios limit future use of these CASs to industrial activities. The suspected contaminants of potential concern which have been identified are volatile organic compounds; semivolatile organic compounds; high explosives; radiological constituents including depleted uranium, beryllium, total petroleum hydrocarbons; and total Resource Conservation and Recovery Act metals. Field activities will consist of geophysical and radiological surveys, and collecting soil samples at biased locations by appropriate methods. A two-step data quality objective strategy will be followed: (1) define the nature of contamination at each CAS location by identifying any contamination above preliminary action levels (PALs); and, (2) determine the extent of contamination identified above PALs. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.« less

10 CFR 20.1406 - Minimization of contamination.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Minimization of contamination. 20.1406 Section 20.1406 Energy NUCLEAR REGULATORY COMMISSION STANDARDS FOR PROTECTION AGAINST RADIATION Radiological Criteria for License Termination § 20.1406 Minimization of contamination. (a) Applicants for licenses, other than early...

10 CFR 20.1406 - Minimization of contamination.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 1 2011-01-01 2011-01-01 false Minimization of contamination. 20.1406 Section 20.1406 Energy NUCLEAR REGULATORY COMMISSION STANDARDS FOR PROTECTION AGAINST RADIATION Radiological Criteria for License Termination § 20.1406 Minimization of contamination. (a) Applicants for licenses, other than early...

Federal Radiological Monitoring and Assessment Center Monitoring Manual Volume 1, Operations

DOE Office of Scientific and Technical Information (OSTI.GOV)

NSTec Aerial Measurement Systems

2012-07-31

The Monitoring division is primarily responsible for the coordination and direction of: Aerial measurements to delineate the footprint of radioactive contaminants that have been released into the environment. Monitoring of radiation levels in the environment; Sampling to determine the extent of contaminant deposition in soil, water, air and on vegetation; Preliminary field analyses to quantify soil concentrations or depositions; and Environmental and personal dosimetry for FRMAC field personnel, during a Consequence Management Response Team (CMRT) and Federal Radiological Monitoring and Assessment Center (FRMAC) response. Monitoring and sampling techniques used during CM/FRMAC operations are specifically selected for use during radiological emergenciesmore » where large numbers of measurements and samples must be acquired, analyzed, and interpreted in the shortest amount of time possible. In addition, techniques and procedures are flexible so that they can be used during a variety of different scenarios; e.g., accidents involving releases from nuclear reactors, contamination by nuclear waste, nuclear weapon accidents, space vehicle reentries, or contamination from a radiological dispersal device. The Monitoring division also provides technicians to support specific Health and Safety Division activities including: The operation of the Hotline; FRMAC facility surveys; Assistance with Health and Safety at Check Points; and Assistance at population assembly areas which require support from the FRMAC. This volume covers deployment activities, initial FRMAC activities, development and implementation of the monitoring and assessment plan, the briefing of field teams, and the transfer of FRMAC to the EPA.« less

EFFECTS OF RADIATION ON ESTABLISHED FORENSIC EVIDENCE CONTAINMENT METHODS

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ferguson, C.; Duff, M.; Clark, E.

2010-11-29

The Federal Bureau of Investigation (FBI) Laboratory is currently exploring needs and protocols for the storage of evidentiary items contaminated with radioactive material. While a large body of knowledge on the behavior of storage polymers in radiation fields exists, this knowledge has not been applied to the field of forensics and maintaining evidentiary integrity. The focus of this research was to evaluate the behavior of several traditional evidentiary containment polymers when exposed to significant alpha, beta, gamma, neutron and mixed radiation sources. Doses were designed to simulate exposures possible during storage of materials. Several products were found to be poorlymore » suited for use in this specific application based on standardized mechanical testing results. Remaining products were determined to warrant further investigation for the storage of radiologically contaminated evidence.« less

RCT: Module 2.11, Radiological Work Coverage, Course 8777

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hillmer, Kurt T.

2017-07-20

Radiological work is usually approved and controlled by radiation protection personnel by using administrative and procedural controls, such as radiological work permits (RWPs). In addition, some jobs will require working in, or will have the potential for creating, very high radiation, contamination, or airborne radioactivity areas. Radiological control technicians (RCTs) providing job coverage have an integral role in controlling radiological hazards. This course will prepare the student with the skills necessary for RCT qualification by passing quizzes, tests, and the RCT Comprehensive Phase 1, Unit 2 Examination (TEST 27566) and will provide in-the-field skills.

ASSESSING INTERNAL CONTAMINATION AFTER THE DETONATION OF A RADIOLOGICAL DISPERSION DEVICE USING A 2×2-INCH SODIUM IODIDE DETECTOR

PubMed Central

Dewji, S.; Hertel, N.; Ansari, A.

2017-01-01

The detonation of a radiological dispersion device may result in a situation where individuals inhale radioactive materials and require rapid assessment of internal contamination. The feasibility of using a 2×2-inch sodium-iodide detector to determine the committed effective dose to an individual following acute inhalation of gamma-emitting radionuclides was investigated. Experimental configurations of point sources with a polymethyl methacrylate slab phantom were used to validate Monte Carlo simulations. The validated detector model was used to simulate the responses for four detector positions on six different anthropomorphic phantoms. The nuclides examined included 241Am, 60Co, 137Cs, 131I and 192Ir. Biokinetic modelling was employed to determine the distributed activity in the body as a function of post-inhalation time. The simulation and biokinetic data were used to determine time-dependent count-rate values at optimal detector locations on the body for each radionuclide corresponding to a target committed effective dose (E50) value of 250 mSv. PMID:23436621

DEMOLISHING A COLD WARE ERA FULE STORAGE BASIN SUPERSTRUCTURE LADEN WITH ASBESTOS

DOE Office of Scientific and Technical Information (OSTI.GOV)

LLOYD ER; STEVENS JM; DAGAN EB

The K East (KE) Basin facilities are located near the north end of the Hanford Site's 100 K area. The facilities were built in 1950 as part of the KE Reactor complex and constructed within 400 meters of the Columbia River, which is the largest river in the Pacific Northwest and by volume the fourth largest river in the United States. The basin, located adjacent to the reactor, was used for the underwater storage of irradiated nuclear fuel discharged from the reactor. The basin was covered by a superstructure comprising steel columns and beams, concrete, and cement asbestos board (CAB)more » siding. The project's mission was to complete demolition of the structure over the KE Basin within six months of turnover from facility deactivation activities. The demolition project team applied open-air demolition techniques to bring the facility to slab-on-grade. Several innovative techniques were used to control contamination and maintain contamination control within the confines of the demolition exclusion zone. The techniques, which focused on a defense-in-depth approach, included spraying fixatives on interior and exterior surfaces before demolition began; applying fixatives during the demolition; misting using a fine spray of water during demolition; and demolishing the facility systematically. Another innovative approach that made demolition easier was to demolish the building with the non-friable CAB remaining in place. The CAB siding covered the exterior of the building and portions of the interior walls, and was an integral part of the multiple-layered roof. The project evaluated the risks involved in removing the CAB material in a radiologically contaminated environment and determined that radiological dose rates and exposure to radiological contamination and industrial hazards would be significantly reduced by using heavy equipment to remove the CAB during demolition. The ability to perform this demolition safely and without spreading contamination (radiological or asbestos) demonstrates that contaminated structures can be torn down successfully using similar open-air demolition techniques.« less

ASSESSMENT OF RADIOACTIVE AND NON-RADIOACTIVE CONTAMINANTS FOUND IN LOW LEVEL RADIOACTIVE WASTE STREAMS

DOE Office of Scientific and Technical Information (OSTI.GOV)

R.H. Little, P.R. Maul, J.S.S. Penfoldag

2003-02-27

This paper describes and presents the findings from two studies undertaken for the European Commission to assess the long-term impact upon the environment and human health of non-radioactive contaminants found in various low level radioactive waste streams. The initial study investigated the application of safety assessment approaches developed for radioactive contaminants to the assessment of nonradioactive contaminants in low level radioactive waste. It demonstrated how disposal limits could be derived for a range of non-radioactive contaminants and generic disposal facilities. The follow-up study used the same approach but undertook more detailed, disposal system specific calculations, assessing the impacts of bothmore » the non-radioactive and radioactive contaminants. The calculations undertaken indicated that it is prudent to consider non-radioactive, as well as radioactive contaminants, when assessing the impacts of low level radioactive waste disposal. For some waste streams with relatively low concentrations of radionuclides, the potential post-closure disposal impacts from non-radioactive contaminants can be comparable with the potential radiological impacts. For such waste streams there is therefore an added incentive to explore options for recycling the materials involved wherever possible.« less

Radiological health risk evaluation of radium contaminated land: a real life implementation.

PubMed

Paridaens, J

2005-01-01

A plot of land, currently used for dairy farming, has been contaminated over the years with radium due to the operation of one of the world's largest radium production plants. Within the framework of a global remediation approach for the plant surroundings, the land owner needed advice for a future destination of the land. Therefore, the radium contamination was accurately mapped, and on the basis of its severity a practically feasible subdivision of the land into four plots was proposed. For all four plots, the radiological risk was evaluated for the current type of land use and for possible alternative types. Hence a clear and useable advice could be formulated to the authorities reconciling public health, economic and practical issues.

Skin decontamination cream for radiological contaminants: Formulation development and evaluation

PubMed Central

Khan, Abdul Wadood; Kotta, Sabna; Rana, Sudha; Ansari, Shahid Husain; Sharma, Rakesh Kumar; Ali, Javed

2013-01-01

Background: Increased use of the radioactive materials in the field of research, medical, nuclear power plant, and industry has increased the risk of accidental exposure. Intentional use of the radioisotopes by terrorist organizations could cause exposure/contamination of a number of the population. In view of the accidental contamination, there is a need to develop self-usable decontamination formulations that could be used immediately after contamination is suspected. Materials and Methods: Present work was planned to optimize and develop self-usable radiation decontamination cream formulation. Various pharmaceutical parameters were characterized. 99mTc-sodium pertechnetate was used as radiocontaminant. Static counts were recorded before and after decontamination using single photon emission computed tomography. Results: Decontamination efficacy of the cream was found to be 42% ± 3% at 0-0.5 h after the exposure. Primary skin irritancy test was satisfactory as no erythema or edema was observed visually after 2 weeks of the formulation application. Conclusion: The decontamination studies proved the potential of EDTA to remove the radiological contaminants effectively. PMID:23799206

Ensuring the safety of surgical teams when managing casualties of a radiological dirty bomb.

PubMed

Williams, Geraint; O'Malley, Michael; Nocera, Antony

2010-09-01

The capacity for surgical teams to ensure their own safety when dealing with the consequences caused by the detonation of a radiological dirty bomb is primarily determined by prior knowledge, familiarity and training for this type of event. This review article defines the associated radiological terminology with an emphasis on the personal safety of surgical team members in respect to the principles of radiological protection. The article also describes a technique for use of hand held radiation monitors and will discuss the identification and management of radiologically contaminated patients who may pose a significant danger to the surgical team. 2010 Elsevier Ltd. All rights reserved.

Assessment of self-help methods to reduce potential exposure to radiological contamination after a large-scale radiological release.

PubMed

Snyder, Emily; Drake, John; Cardarelli, John; Hall, Kathy; Szabo, Jeff; Demmer, Rick; Lindberg, Michael; Riggs, Karen; James, Ryan

2014-09-01

After the release of radioactive materials from a large radiological dispersal device (e.g., dirty bomb), improvised nuclear detonation, or nuclear power plant accident, up to hundreds of square miles may be contaminated. A portion of this area will be evacuated; however, people living in the portion that is not evacuated yet is still contaminated with low-levels of radioactive contamination will be asking for ways they can reduce their exposure. Whether cleaning activities can significantly reduce exposure is not fully understood. In this effort, the ability of cleaning activities to remove cesium (137Cs) was studied. The removal efficacy of cleaning with a commercial product, Simple Green®, was compared to cleaning with water for hard surfaces typically seen in residences. The removal efficacy of laundering fabric material surfaces was also determined for a range of conditions (e.g., fabric material type, wash temperature). During these studies, assessments of the implications of these activities (e.g., cross-contamination, resulting waste streams) were also completed. Simple Green and water were effective for removing 137Cs from plastic laminate and vinyl flooring (93.4-96.8%) but were not effective for removing 137Cs from painted wallboard and wood (7.3-68.1%). It was also determined that there was no significant difference between the two cleaners on all of the surfaces, except plastic laminate, for which Simple Green was slightly more effective. Laundering was effective for removing 137Cs contamination from polyester and cotton swatches and cotton comforters (up to 96.8% in the single swatch testing).

A Planning Tool for Estimating Waste Generated by a Radiological Incident and Subsequent Decontamination Efforts - 13569

DOE Office of Scientific and Technical Information (OSTI.GOV)

Boe, Timothy; Lemieux, Paul; Schultheisz, Daniel

2013-07-01

Management of debris and waste from a wide-area radiological incident would probably constitute a significant percentage of the total remediation cost and effort. The U.S. Environmental Protection Agency's (EPA's) Waste Estimation Support Tool (WEST) is a unique planning tool for estimating the potential volume and radioactivity levels of waste generated by a radiological incident and subsequent decontamination efforts. The WEST was developed to support planners and decision makers by generating a first-order estimate of the quantity and characteristics of waste resulting from a radiological incident. The tool then allows the user to evaluate the impact of various decontamination/demolition strategies onmore » the waste types and volumes generated. WEST consists of a suite of standalone applications and Esri{sup R} ArcGIS{sup R} scripts for rapidly estimating waste inventories and levels of radioactivity generated from a radiological contamination incident as a function of user-defined decontamination and demolition approaches. WEST accepts Geographic Information System (GIS) shape-files defining contaminated areas and extent of contamination. Building stock information, including square footage, building counts, and building composition estimates are then generated using the Federal Emergency Management Agency's (FEMA's) Hazus{sup R}-MH software. WEST then identifies outdoor surfaces based on the application of pattern recognition to overhead aerial imagery. The results from the GIS calculations are then fed into a Microsoft Excel{sup R} 2007 spreadsheet with a custom graphical user interface where the user can examine the impact of various decontamination/demolition scenarios on the quantity, characteristics, and residual radioactivity of the resulting waste streams. (authors)« less

Remote Handled WIPP Canisters at Los Alamos National Laboratory Characterized for Retrieval

DOE Office of Scientific and Technical Information (OSTI.GOV)

Griffin, J.; Gonzales, W.

2007-07-01

The Los Alamos National Laboratory (LANL) is pursuing retrieval, transportation, and disposal of 16 remote handled transuranic waste canisters stored below ground in shafts since 1994. These canisters were retrievably stored in the shafts to await Nuclear Regulatory Commission certification of the Model Number RH-TRU 72B transportation cask and authorization of the Waste Isolation Pilot Plant (WIPP) to accept the canisters for disposal. Retrieval planning included radiological characterization and visual inspection of the canisters to confirm historical records, verify container integrity, determine proper personnel protection for the retrieval operations, provide radiological dose and exposure rate data for retrieval operations, andmore » to provide exterior radiological contamination data. The radiological characterization and visual inspection of the canisters was performed in May 2006. The effort required the development of remote techniques and equipment due to the potential for personnel exposure to radiological doses approaching 300 R/hr. Innovations included the use of two nested 1.5 meter (m) (5-feet [ft]) long concrete culvert pipes (1.1-m [42 inch (in.)] and 1.5-m [60-in] diameter, respectively) as radiological shielding and collapsible electrostatic dusting wands to collect radiological swipe samples from the annular space between the canister and shaft wall. Visual inspection indicated that the canisters are in good condition with little or no rust, the welded seams are intact, and ten of the canisters include hydrogen gas sampling equipment on the pintle that will have to be removed prior to retrieval. The visual inspection also provided six canister identification numbers that matched historical storage records. The exterior radiological data indicated alpha and beta contamination below LANL release criteria and radiological dose and exposure rates lower than expected based upon historical data and modeling of the canister contents. (authors)« less

Integrating intrusive and nonintrusive characterization methods to achieve a conceptual site model for the SLDA FUSRAP site - 8265.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Durham, L. A.; Peterson, J. M.; Frothingham, D. G.

2008-01-01

The US Army Corps of Engineers (USACE) is addressing radiological contamination following Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requirements at the Shallow Land Disposal Area (SLDA) site, which is a radiologically contaminated property that is part of the Formerly utilized Sites Remedial Action Program (FUSRAP). The SLDA is an 18-hectare (44-acre) site in Parks township, Armstrong County, Pennsylvania, about 37 kilometers (23 miles) east-northeast of Pittsburgh. According to historical record, radioactive wastes were disposed of at the SLDA in a series of trenches by the Nuclear Materials and Equipment Company (NUMEC) in the 1960s. The wastes originated frommore » the nearby Apollo nuclear fuel fabrication facility, which began operations under NUMEC in the late 1950s and fabricated enriched uranium into naval reactor fuel elements. It is believed that the waste materials were buried in a series of pits constructed adjacent to one another in accordance with an Atomic Energy Commission (AEC) regulation that has since been rescinded. A CERCLA remedial investigation/feasibility study (RI/FS) process was completed for the SLDA site, and the results of the human health risk assessment indicated that the radiologically contaminated wastes could pose a risk to human health in the future. There are no historical records that provide the exact location of these pits. However, based on geophysical survey results conducted in the 1980s, these pits were defined by geophysical anomalies and were depicted on historical site drawings as trenches. At the SLDA site, a combination of investigative methods and tools was used in the RI/FS and site characterization activities. The SLDA site provides an excellent example of how historical documents and data, historical aerial photo analysis, physical sampling, and nonintrusive geophysical and gamma walkover surveys were used in combination to reduce the uncertainty in the location of the trenches. The data and information from these sources were used to refine the conceptual site model, complete the RI/FS, and support the ongoing remedial design and action, which will achieve site closure acceptable to all stakeholders.« less

Integrating Intrusive and Non-intrusive Characterization Methods To Achieve A Conceptual Site Model For The SLDA FUSRAP

DOE Office of Scientific and Technical Information (OSTI.GOV)

Durham, L.A.; Peterson, J.M.; Frothingham, D.G.

2008-07-01

The U.S. Army Corps of Engineers (USACE) is addressing radiological contamination following Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requirements at the Shallow Land Disposal Area (SLDA) site, which is a radiologically contaminated property that is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). The SLDA is an 18-hectare (44- acre) site in Parks Township, Armstrong County, Pennsylvania, about 37 kilometers (23 miles) east-northeast of Pittsburgh. According to historical record, radioactive wastes were disposed of at the SLDA in a series of trenches by the Nuclear Materials and Equipment Company (NUMEC) in the 1960's. The wastes originatedmore » from the nearby Apollo nuclear fuel fabrication facility, which began operations under NUMEC in the late 1950's and fabricated enriched uranium into naval reactor fuel elements. It is believed that the waste materials were buried in a series of pits constructed adjacent to one another in accordance with an Atomic Energy Commission (AEC) regulation that has since been rescinded. A CERCLA remedial investigation/feasibility study (RI/FS) process was completed for the SLDA site, and the results of the human health risk assessment indicated that the radiologically contaminated wastes could pose a risk to human health in the future. There are no historical records that provide the exact location of these pits. However, based on geophysical survey results conducted in the 1980's, these pits were defined by geophysical anomalies and were depicted on historical site drawings as trenches. At the SLDA site, a combination of investigative methods and tools was used in the RI/FS and site characterization activities. The SLDA site provides an excellent example of how historical documents and data, historical aerial photo analysis, physical sampling, and non-intrusive geophysical and gamma walkover surveys were used in combination to reduce the uncertainty in the location of the trenches. The data and information from these sources were used to refine the conceptual site model, complete the RI/FS, and support the ongoing remedial design and action, which will achieve site closure acceptable to all stakeholders. (authors)« less

The Semipalatinsk nuclear test site: a first assessment of the radiological situation and the test-related radiation doses in the surrounding territories.

PubMed

Gusev, B I; Abylkassimova, Z N; Apsalikov, K N

1997-09-01

As a result of atmospheric nuclear tests at the Semipalatinsk test site 'Polygon', adjacent territories were contaminated by radionuclide fallout. The population of some districts in the Semipalatinsk oblast were exposed to elevated levels of radiation. Contamination and exposure mostly resulted from early atmospheric tests. The radiological situation of the Semipalatinsk oblast is described. Effective dose estimates due to external and internal exposure attributable to the 1949 and 1953 tests in villages near the Polygon range from 70 mSv to 4470 mSv.

Microbial contamination in intraoral phosphor storage plates: the dilemma.

PubMed

de Souza, Tricia Murielly Pereira Andrade; de Castro, Ricardo Dias; de Vasconcelos, Laís César; Pontual, Andréa Dos Anjos; de Moraes Ramos Perez, Flávia Maria; Pontual, Maria Luiza Dos Anjos

2017-01-01

The aims of this study were to evaluate microbial contamination in phosphor storage plates in dental radiology services and discuss the possible origin of this contamination. The sample comprised 50 phosphor plates: 14 plates from service A, 30 from service B, and 6 in the control group, consisting of plates never used. Damp sterile swabs were rubbed on the phosphor plates, and then transferred to tests tubes containing sterile saline solution. Serial dilutions were made, and then inoculated in triplicate on Mueller Hinton agar plates and incubated at 37 °C/48 h, before counting the colony-forming units (CFU). The samples were also seeded in brain-heart infusion medium to confirm contamination by turbidity of the culture medium. All solutions, turbid and clean, were seeded in selective and non-selective media. At service A and B, 50 and 73.3 % of the phosphor plates were contaminated, respectively. This contamination was mainly due to bacteria of the genus Staphylococcus. CFU counts ranged from 26.4 to 80.0 CFU/plate. Most of the phosphor plates evaluated shown to be contaminated, mainly by Staphylococcus ssp. Quantitatively, this contamination occurred at low levels, possibly arising from handling of the plates. The use of a second plastic barrier may have diminished contamination by microorganisms from the oral cavity. There is a risk of cross-contamination by phosphor storage plates used in dental radiology services.

Phase I Flow and Transport Model Document for Corrective Action Unit 97: Yucca Flat/Climax Mine, Nevada National Security Site, Nye County, Nevada, Revision 1 with ROTCs 1 and 2

DOE Office of Scientific and Technical Information (OSTI.GOV)

Andrews, Robert

The Underground Test Area (UGTA) Corrective Action Unit (CAU) 97, Yucca Flat/Climax Mine, in the northeast part of the Nevada National Security Site (NNSS) requires environmental corrective action activities to assess contamination resulting from underground nuclear testing. These activities are necessary to comply with the UGTA corrective action strategy (referred to as the UGTA strategy). The corrective action investigation phase of the UGTA strategy requires the development of groundwater flow and contaminant transport models whose purpose is to identify the lateral and vertical extent of contaminant migration over the next 1,000 years. In particular, the goal is to calculate themore » contaminant boundary, which is defined as a probabilistic model-forecast perimeter and a lower hydrostratigraphic unit (HSU) boundary that delineate the possible extent of radionuclide-contaminated groundwater from underground nuclear testing. Because of structural uncertainty in the contaminant boundary, a range of potential contaminant boundaries was forecast, resulting in an ensemble of contaminant boundaries. The contaminant boundary extent is determined by the volume of groundwater that has at least a 5 percent chance of exceeding the radiological standards of the Safe Drinking Water Act (SDWA) (CFR, 2012).« less

Nuclear Warfare Water Contamination.

DTIC Science & Technology

1982-05-01

obscured the important relationship between radionuclide ground concentrations and fallout dose rate contours by focusing too much attention on the...19 ) Radiological water contamination by nonpoint sources has received little, if any, attention in the current literature on the environmental... attention . Nevertheless, the environmental contamination of water supplies by fallout has been noted as a source of background radiation (20 ) and a possible

Corrective Action Investigation Plan for Corrective Action Unit 576: Miscellaneous Radiological Sites and Debris Nevada National Security Site, Nevada, Revision 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Matthews, Patrick

Corrective Action Unit (CAU) 576 is located in Areas 2, 3, 5, 8, and 9 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 576 is a grouping of sites where there has been a suspected release of contamination associated with nuclear testing. This document describes the planned investigation of CAU 576, which comprises the following corrective action sites (CASs): 00-99-01, Potential Source Material; 02-99-12, U-2af (Kennebec) Surface Rad-Chem Piping; 03-99-20, Area 3 Subsurface Rad-Chem Piping; 05-19-04, Frenchman Flat Rad Waste Dump ; 09-99-08, U-9x (Allegheny) Subsurface Rad-Chem Piping; 09-99-09, U-9its u24more » (Avens-Alkermes) Surface Contaminated Flex Line These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document (CADD).« less

DEMOLISHING A COLD-WAR-ERA FUEL STORAGE BASIN SUPERSTRUCTURE LADEN WITH ASBESTOS

DOE Office of Scientific and Technical Information (OSTI.GOV)

LLOYD ER; ORGILL TK; DAGAN EB

The K East (KE) Basin facilities are located near the north end of the Hanford Site's 100 K area. The facilities were built in 1950 as part of the KE Reactor complex and constructed within 400 meters of the Columbia River, which is the largest river in the Pacific Northwest and by volume the fourth largest river in the United States. The basin, located adjacent to the reactor, was used for the underwater storage of irradiated nuclear fuel discharged from the reactor. The basin was covered by a superstructure comprising steel columns and beams, concrete, and cement asbestos board (CAB)more » siding. The project's mission was to complete demolition of the structure over the K East basin within six months of tumover from facility deactivation activities. The demolition project team implemented open-air demolition techniques to demolish the facility to slab-on-grade. Several innovative techniques were used to control contamination and maintain contamination control within the confines of the demolition exclusion zone. The techniques, which focused on a defense-in-depth approach, included spraying fixatives on interior and exterior surfaces before demolition began; applying fixatives; misting using a fine spray of water during demolition; and demolishing the facility systematically. Another innovation that aided demolition was to demolish the building with the non-friable CAB remaining in place. The CAB siding covered the exterior of the building, portions of the interior walls, and was an integral part of the multiple layered roof. The project evaluated the risks involved in removing the CAB material in a radiologically contaminated environment and determined that radiological dose rates and exposure to radiological contamination and industrial hazards would be significantly reduced by removing the CAB during demolition using heavy equipment. The ability to perform this demolition safely and without spreading contamination (radiological or asbestos) demonstrates that similar open-air demolition ofcontaminated structures can be performed successfully.« less

Analytical method for nitroaromatic explosives in radiologically contaminated soil for ISO/IEC 17025 accreditation

DOE PAGES

Boggess, Andrew; Crump, Stephen; Gregory, Clint; ...

2017-12-06

Here, unique hazards are presented in the analysis of radiologically contaminated samples. Strenuous safety and security precautions must be in place to protect the analyst, laboratory, and instrumentation used to perform analyses. A validated method has been optimized for the analysis of select nitroaromatic explosives and degradative products using gas chromatography/mass spectrometry via sonication extraction of radiologically contaminated soils, for samples requiring ISO/IEC 17025 laboratory conformance. Target analytes included 2-nitrotoluene, 4-nitrotoluene, 2,6-dinitrotoluene, and 2,4,6-trinitrotoluene, as well as the degradative product 4-amino-2,6-dinitrotoluene. Analytes were extracted from soil in methylene chloride by sonication. Administrative and engineering controls, as well as instrument automationmore » and quality control measures, were utilized to minimize potential human exposure to radiation at all times and at all stages of analysis, from receiving through disposition. Though thermal instability increased uncertainties of these selected compounds, a mean lower quantitative limit of 2.37 µg/mL and mean accuracy of 2.3% relative error and 3.1% relative standard deviation were achieved. Quadratic regression was found to be optimal for calibration of all analytes, with compounds of lower hydrophobicity displaying greater parabolic curve. Blind proficiency testing (PT) of spiked soil samples demonstrated a mean relative error of 9.8%. Matrix spiked analyses of PT samples demonstrated that 99% recovery of target analytes was achieved. To the knowledge of the authors, this represents the first safe, accurate, and reproducible quantitative method for nitroaromatic explosives in soil for specific use on radiologically contaminated samples within the constraints of a nuclear analytical lab.« less

Analytical method for nitroaromatic explosives in radiologically contaminated soil for ISO/IEC 17025 accreditation

DOE Office of Scientific and Technical Information (OSTI.GOV)

Boggess, Andrew; Crump, Stephen; Gregory, Clint

Here, unique hazards are presented in the analysis of radiologically contaminated samples. Strenuous safety and security precautions must be in place to protect the analyst, laboratory, and instrumentation used to perform analyses. A validated method has been optimized for the analysis of select nitroaromatic explosives and degradative products using gas chromatography/mass spectrometry via sonication extraction of radiologically contaminated soils, for samples requiring ISO/IEC 17025 laboratory conformance. Target analytes included 2-nitrotoluene, 4-nitrotoluene, 2,6-dinitrotoluene, and 2,4,6-trinitrotoluene, as well as the degradative product 4-amino-2,6-dinitrotoluene. Analytes were extracted from soil in methylene chloride by sonication. Administrative and engineering controls, as well as instrument automationmore » and quality control measures, were utilized to minimize potential human exposure to radiation at all times and at all stages of analysis, from receiving through disposition. Though thermal instability increased uncertainties of these selected compounds, a mean lower quantitative limit of 2.37 µg/mL and mean accuracy of 2.3% relative error and 3.1% relative standard deviation were achieved. Quadratic regression was found to be optimal for calibration of all analytes, with compounds of lower hydrophobicity displaying greater parabolic curve. Blind proficiency testing (PT) of spiked soil samples demonstrated a mean relative error of 9.8%. Matrix spiked analyses of PT samples demonstrated that 99% recovery of target analytes was achieved. To the knowledge of the authors, this represents the first safe, accurate, and reproducible quantitative method for nitroaromatic explosives in soil for specific use on radiologically contaminated samples within the constraints of a nuclear analytical lab.« less

Corrective Action Decision Document/Corrective Action Plan for Corrective Action Unit 573: Alpha Contaminated Sites Nevada National Security Site, Nevada, Revision 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Matthews, Patrick

CAU 573 comprises the following corrective action sites (CASs): • 05-23-02, GMX Alpha Contaminated Area • 05-45-01, Atmospheric Test Site - Hamilton These two CASs include the release at the Hamilton weapons-related tower test and a series of 29 atmospheric experiments conducted at GMX. The two CASs are located in two distinctly separate areas within Area 5. To facilitate site investigation and data quality objective (DQO) decisions, all identified releases (i.e., CAS components) were organized into study groups. The reporting of investigation results and the evaluation of DQO decisions are at the release level. The corrective action alternatives (CAAs) weremore » evaluated at the FFACO CAS level. The purpose of this CADD/CAP is to evaluate potential CAAs, provide the rationale for the selection of recommended CAAs, and provide the plan for implementation of the recommended CAA for CAU 573. Corrective action investigation (CAI) activities were performed from January 2015 through November 2015, as set forth in the CAU 573 Corrective Action Investigation Plan (CAIP). Analytes detected during the CAI were evaluated against appropriate final action levels (FALs) to identify the contaminants of concern. Assessment of the data generated from investigation activities conducted at CAU 573 revealed the following: • Radiological contamination within CAU 573 does not exceed the FALs (based on the Occasional Use Area exposure scenario). • Chemical contamination within CAU 573 does not exceed the FALs. • Potential source material—including lead plates, lead bricks, and lead-shielded cables—was removed during the investigation and requires no additional corrective action.« less

The inspection of a radiologically contaminated pipeline using a teleoperated pipe crawler

DOE Office of Scientific and Technical Information (OSTI.GOV)

Fogle, R.F.; Kuelske, K.; Kellner, R.A.

1995-08-01

In the 1950s, the Savannah River Site built an open, unlined retention basin to temporarily store potentially radionuclide contaminated cooling water from a chemical separations process and storm water drainage from a nearby waste management facility that stored large quantities of nuclear fission byproducts in carbon steel tanks. The retention basin was retired from service in 1972 when a new, lined basin was completed. In 1978, the old retention basin was excavated, backfilled with uncontaminated dirt, and covered with grass. At the same time, much of the underground process pipeline leading to the basin was abandoned. Since the closure ofmore » the retention basin, new environmental regulations require that the basin undergo further assessment to determine whether additional remediation is required. A visual and radiological inspection of the pipeline was necessary to aid in the remediation decision making process for the retention basin system. A teleoperated pipe crawler inspection system was developed to survey the abandoned sections of underground pipelines leading to the retired retention basin. This paper will describe the background to this project, the scope of the investigation, the equipment requirements, and the results of the pipeline inspection.« less

Effects of soil water content on the external exposure of fauna to radioactive isotopes.

PubMed

Beaugelin-Seiller, K

2016-01-01

Within a recent model intercomparison about radiological risk assessment for contaminated wetlands, the influence of soil saturation conditions on external dose rates was evidenced. This issue joined concerns of assessors regarding the choice of the soil moisture value to input in radiological assessment tools such as the ERICA Tool. Does it really influence the assessment results and how? This question was investigated under IAEA's Modelling and Data for Radiological Impacts Assessments (MODARIA) programme via 42 scenarios for which the soil water content varied from 0 (dry soil) to 100% (saturated soil), in combination with other parameters that may influence the values of the external dose conversion coefficients (DCCs) calculated for terrestrial organisms exposed in soil. A set of α, β, and γ emitters was selected in order to cover the range of possible emission energies. The values of their external DCCs varied generally within a factor 1 to 1.5 with the soil water content, excepted for β emitters that appeared more sensitive (DCCs within a factor of about 3). This may be of importance for some specific cases or for upper tiers of radiological assessments, when refinement is required. But for the general purpose of screening assessment of radiological impact on fauna and flora, current approaches regarding the soil water content are relevant. Copyright © 2015 Elsevier Ltd. All rights reserved.

10 CFR 20.1406 - Minimization of contamination.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 1 2012-01-01 2012-01-01 false Minimization of contamination. 20.1406 Section 20.1406 Energy NUCLEAR REGULATORY COMMISSION STANDARDS FOR PROTECTION AGAINST RADIATION Radiological Criteria for..., including the subsurface, in accordance with the existing radiation protection requirements in Subpart B and...

Chemical, biological, radiological, and nuclear decontamination: Recent trends and future perspective

PubMed Central

Kumar, Vinod; Goel, Rajeev; Chawla, Raman; Silambarasan, M.; Sharma, Rakesh Kumar

2010-01-01

Chemical, biological, radiological, and nuclear (CBRN) decontamination is the removal of CBRN material from equipment or humans. The objective of the decontamination is to reduce radiation burden, salvage equipment, and materials, remove loose CBRN contaminants, and fix the remaining in place in preparation for protective storage or permanent disposal work activities. Decontamination may be carried out using chemical, electrochemical, and mechanical means. Like materials, humans may also be contaminated with CBRN contamination. Changes in cellular function can occur at lower radiation doses and exposure to chemicals. At high dose, cell death may take place. Therefore, decontamination of humans at the time of emergency while generating bare minimum waste is an enormous task requiring dedication of large number of personnel and large amount of time. General principles of CBRN decontamination are discussed in this review with emphasis on radiodecontamination. PMID:21829318

Development of practical methods for removal of radiological, biological, and chemical contaminants from water supplies. Final report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Woodward, R.L.; Robeck, G.G.

1958-06-01

Laboratory and engineering studies were conducted to determine the design criteria and cost estimated of providing and operating devices to protect against radiological, biological and chemical warfare agents that may contaminate shore based Naval water supplies. Small disposable columns of mixed cation-anion exchange resins will remove the soluble radionuclides enough to suffice for immediate drinking and culinary purposes. Chemical warfare agents are so numerous and varied that it is not feasible to provide a single protective device to cope with them. Chlorination with free available chlorine residuals of 1 mg liter will handle most biological warfare agents.

An assessment of drinking-water supplies on the Hanford site: an evaluation conducted at a federal nuclear facility in southeastern Washington state.

PubMed

Hanf, R William; Kelly, Lynn M

2005-03-01

Drinking water is supplied to most U.S. Department of Energy (DOE) facilities on the Hanford Site by DOE-owned, contractor-operated pumping and distribution systems. Water is primarily obtained from the Columbia River, but some facilities use water from on-site groundwater wells. Because of the large amount of radioactive and chemical waste produced, stored, and disposed of at Hanford, some people are concerned that waste materials are contaminating on-site drinking-water supplies. This paper describes the drinking-water facilities and treatment requirements on the Hanford Site and summarizes radiological and non-radiological water quality data obtained from water samples collected from each drinking-water system in use during 2001 and 2002. Monitoring data show that Hanford-produced radionuclides are measurable in some drinking-water samples. The only non-radiological contaminants detected either were by-products of the chlorination process or came from off-site agricultural activities. Contaminant level values were, in all cases, below state and federal drinking-water limits. This information will provide assurance to current employees and future site developers that drinking water on the Hanford Site is safe for public consumption.

Foreign bodies in the aerodigestive tract.

PubMed

Lawson, V G; Middleton, W G

1986-04-01

Foreign bodies in the aerodigestive tract are common. They may cause minimal disturbance of function, severe morbidity or even sudden death. They enter the aerodigestive tract because of haste during eating, disturbances in physical function, impairments due to extreme youth or age, or contamination of food with foreign bodies. Common symptoms are pain, dysphagia, odynophagia, cough, airway distress, hemoptysis and hematemesis. Signs include point tenderness, respiratory distress and surgical emphysema. Clinical, radiological and endoscopic investigations are described, as are principles of crisis and elective management.

Technical Report for the Demonstration of Wide Area ...

EPA Pesticide Factsheets

Report The U.S. Environmental Protection Agency in collaboration with the Department of Homeland Security conducted the “Wide-Area Urban Radiological Contaminant, Mitigation, and Cleanup Technology Demonstration” in Columbus, Ohio on June 22-25, 2015. Five wide-area radiological decontamination technologies (including strippable coatings, gels, and chemical foam technologies) were demonstrated on an urban building.

Geochemical investigation of UMTRAP designated site at Durango, Colorado

DOE Office of Scientific and Technical Information (OSTI.GOV)

Markos, G.; Bush, K.J.

1983-09-01

This report is the result of a geochemical investigation of the former uranium mill and tailings site at Durango, Colorado. This is one in a series of site specific geochemical investigations performed on the inactive uranium mill tailings included in the UMTRA Project. The objectives of the investigation are to characterize the geochemistry, to determine the contaminant distribution resulting from the former milling activities and tailings, and to infer chemical pathways and transport mechanisms from the contaminant distribution. The results will be used to model contaminant migration and to develop criteria for long-term containment media such as a cover systemmore » which is impermeable to contaminant migration. This report assumes a familiarity with the hydrologic conditions of the site and the geochemical concepts underlying the investigation. The results reported are based on a one-time sampling of waters and solid material from the background, the area adjacent to the site, and the site. The solid samples are water extracted remove easily soluble salts and acids extracted to remove cabonates and hydroxides. The water extracts and solid samples were analyzed for the major and trace elements. A limited number of samples were analyzed for radiological components. The report includes the methods of sampling, sample processing, analysis, and data interpretation. Three major conclusions are: (1) carbonate salts and low TDS characterize the tailings; (2) the adjacent area and raffinate ponds contain contaminants deposited by a single event of fluid permeation of the soils; and (3) the Animas River adjacent to the site has elevated gross alpha activity attributed to /sup 226/Ra in the sediments derived from the tailings or milling activities.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Demmer, Rick; Boxall, Colin

Radiological decontamination is an essential enterprise that has become more important over the last four decades due to unfortunate accidents and the threat of terrorist actions. Decontamination can be an effective, beneficial alternative for the cleanup of radiological contamination events; however, the costs and benefits need to be balanced against those for complete removal and demolition of contaminated areas or facilities. Demolition and removal are often the first options considered in such circumstances as decontamination may be thought of as slow and costly. Decontamination has advantages, including significant waste reduction over demolition. In areas with buildings of cultural or societalmore » importance, demolition may not be an option. Three decontamination evaluation test series are the focus of this article: SIMCON 1 and 2 (i.e., simulated contamination), and Urban RDD (radiological dispersal device, i.e., a dirty bomb detonation). These test series revealed that different contaminants respond differently during decontamination. This was found to be true with both SIMCON and Urban RDD simulant tests. SIMCON 2 especially demonstrated that chemically different contaminants respond differently to different decontamination methods: cesium appears to be less tenacious (more easily removed) than zirconium using chemical methods. These differences were underscored by the Urban RDD tests where americium and cobalt tended to precipitate on high pH surfaces (such as concrete), making them easier to remove, while cesium and strontium were essentially unaffected by surface pH and were imbibed more strongly into the substrate pore structure. While authorities argue over the contributions of contaminant chemistry and substrate morphology, the clear answer is that each has a contribution to the tenacity of a contaminant. Knowing how these characteristics interact will make us better at decontamination in the field. This knowledge refutes the efforts of perhaps well-meaning marketers to define our decontamination problems by what products they are trying to sell; often a “one size fits all” type approach. Knowing even a little bit about the character of the decontamination problem will save time and money and increase the efficacy of decontamination.« less

Internal contamination of an irradiator discovered during security enhancement.

PubMed

Harvey, R P

2014-08-01

High-risk radioactive sources regulated under Increased Controls Regulations have been protected by licensed facilities, but the federal government has placed significant emphasis on these sources and has developed initiatives to assist radioactive material licensees. The Department of Energy's Global Threat Reduction Initiative (GTRI) Domestic Threat Reduction Program is a voluntary federally funded program for security enhancements of high-risk radiological material. During the hardening or security enhancement process by the United States Department of Energy (U.S. DOE) contractors, a small amount of radioactive contamination was discovered in a Cesium irradiator. Ultimately, it was decided to pursue disposal with U.S. DOE's Off-Site Recovery Program (OSRP). Radiological devices may have a leaking source or known internal contamination that may cause difficulty during security enhancement. If the licensee understands this, it may provide facilities the opportunity to plan and prepare for unusual circumstances.

MANAGING INTERNAL RADIATION CONTAMINATION FOLLOWING AN EMERGENCY: IDENTIFICATION OF GAPS AND PRIORITIES

PubMed Central

Li, Chunsheng; Ansari, Armin; Etherington, George; Jourdain, Jean-Rene; Kukhta, Boris; Kurihara, Osamu; Lopez, Maria Antonia; Ménétrier, Florence; dos Reis, Arlene Alves; Solomon, Stephen; Zhang, Jiangfeng; Carr, Zhanat

2017-01-01

Following a radiological or nuclear emergency, first responders and the public may become internally contaminated with radioactive materials, as demonstrated during the Goiânia, Chernobyl and Fukushima accidents. Timely monitoring of the affected populations for potential internal contamination, assessment of radiation dose and the provision of necessary medical treatment are required to minimize the health risks from the contamination. This paper summarizes the guidelines and tools that have been developed, and identifies the gaps and priorities for future projects. PMID:27521210

Chemical, Biological, Radiological, and Nuclear Consequence Management: Ways to Improve Fixed-Site Decontamination Capability

DTIC Science & Technology

2007-05-10

objective is achieved through consequence management and fixed-site decontamination operations. The effectiveness of CBRN consequence management...decontamination operations. The effectiveness of CBRN consequence management and fixed-site decontamination executed in the Joint Security Area can be...when faced with Chemical, Biological, Radiological, or Nuclear (CBRN) contaminated ports of debarkation. The effectiveness of CBRN consequence

Guidance on the Use of Hand-Held Survey Meters for Radiological Triage: Time-Dependent Detector Count Rates Corresponding to 50, 250, and 500 mSv Effective Dose for Adult Males and Adult Females

PubMed Central

Bolch, Wesley E.; Hurtado, Jorge L.; Lee, Choonsik; Manger, Ryan; Hertel, Nolan; Dickerson, William

2013-01-01

In June of 2006, the Radiation Studies Branch of the Centers for Disease Control and Prevention held a workshop to explore rapid methods of facilitating radiological triage of large numbers of potentially contaminated individuals following detonation of a radiological dispersal device. Two options were discussed. The first was the use of traditional gamma-cameras in nuclear medicine departments operated as make-shift whole-body counters. Guidance on this approach is currently available from the CDC. This approach is feasible if a manageable number of individuals were involved, transportation to the relevant hospitals was quickly provided, and the medical staff at each facility had been previously trained in this non-traditional use of their radiopharmaceutical imaging devices. If, however, substantially large numbers of individuals (100s to 1000s) needed radiological screening, other options must be given to first responders, first receivers, and health physicists providing medical management. In this study, the second option of the workshop was investigated – the use of commercially available portable survey meters (either NaI or GM based) for assessing potential ranges of effective dose (<50, 50–250, 250–500, and >500 mSv). Two hybrid computational phantoms were used to model an adult male and an adult female subject internally contaminated with either 241Am, 60Cs, 137Cs, 131I, and 192Ir following an acute inhalation or ingestion intake. As a function of time following the exposure, the net count rates corresponding to committed effective doses of 50, 250, and 500 mSv were estimated via Monte Carlo radiation transport simulation for each of four different detectors types, positions, and screening distances. Measured count rates can be compared to these values and an assignment of one of four possible effective dose ranges could be made. The method implicitly assumes that all external contamination has been removed prior to screening, and that the measurements be conducted in a low-background, and possibly mobile, facility positioned at the triage location. Net count rate data are provided in both tabular and graphical format within a series of eight handbooks available at the CDC website http://emergency.cdc.gov/radiation. PMID:22420020

Guidance on the Use of Hand-Held Survey Meters for radiological Triage: Time-Dependent Detector Count Rates Corresponding to 50, 250, and 500 mSv Effective Dose for Adult Males and Adult Females

DOE Office of Scientific and Technical Information (OSTI.GOV)

Bolch, W.E.; Hurtado, J.L.; Lee, C.

2012-01-01

In June 2006, the Radiation Studies Branch of the Centers for Disease Control and Prevention held a workshop to explore rapid methods of facilitating radiological triage of large numbers of potentially contaminated individuals following detonation of a radiological dispersal device. Two options were discussed. The first was the use of traditional gamma cameras in nuclear medicine departments operated as makeshift wholebody counters. Guidance on this approach is currently available from the CDC. This approach would be feasible if a manageable number of individuals were involved, transportation to the relevant hospitals was quickly provided, and the medical staff at each facilitymore » had been previously trained in this non-traditional use of their radiopharmaceutical imaging devices. If, however, substantially larger numbers of individuals (100 s to 1,000 s) needed radiological screening, other options must be given to first responders, first receivers, and health physicists providing medical management. In this study, the second option of the workshop was investigated by the use of commercially available portable survey meters (either NaI or GM based) for assessing potential ranges of effective dose (G50, 50Y250, 250Y500, and 9500 mSv). Two hybrid computational phantoms were used to model an adult male and an adult female subject internally contaminated with 241Am, 60Cs, 137Cs, 131I, or 192Ir following an acute inhalation or ingestion intake. As a function of time following the exposure, the net count rates corresponding to committed effective doses of 50, 250, and 500 mSv were estimated via Monte Carlo radiation transport simulation for each of four different detector types, positions, and screening distances. Measured net count rates can be compared to these values, and an assignment of one of four possible effective dose ranges could be made. The method implicitly assumes that all external contamination has been removed prior to screening and that the measurements be conducted in a low background, and possibly mobile, facility positioned at the triage location. Net count rate data are provided in both tabular and graphical format within a series of eight handbooks available at the CDC website (http://www.bt.cdc.gov/radiation/clinicians/evaluation).« less

Corrective Action Investigation Plan for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada (December 2002, Revision No.: 0), Including Record of Technical Change No. 1

DOE Office of Scientific and Technical Information (OSTI.GOV)

NNSA /NSO

The Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 204 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 204 is located on the Nevada Test Site approximately 65 miles northwest of Las Vegas, Nevada. This CAU is comprised of six Corrective Action Sites (CASs) which include: 01-34-01, Underground Instrument House Bunker; 02-34-01, Instrument Bunker; 03-34-01, Underground Bunker; 05-18-02, Chemical Explosives Storage; 05-33-01, Kay Blockhouse; 05-99-02, Explosive Storage Bunker.more » Based on site history, process knowledge, and previous field efforts, contaminants of potential concern for Corrective Action Unit 204 collectively include radionuclides, beryllium, high explosives, lead, polychlorinated biphenyls, total petroleum hydrocarbons, silver, warfarin, and zinc phosphide. The primary question for the investigation is: ''Are existing data sufficient to evaluate appropriate corrective actions?'' To address this question, resolution of two decision statements is required. Decision I is to ''Define the nature of contamination'' by identifying any contamination above preliminary action levels (PALs); Decision II is to ''Determine the extent of contamination identified above PALs. If PALs are not exceeded, the investigation is completed. If PALs are exceeded, then Decision II must be resolved. In addition, data will be obtained to support waste management decisions. Field activities will include radiological land area surveys, geophysical surveys to identify any subsurface metallic and nonmetallic debris, field screening for applicable contaminants of potential concern, collection and analysis of surface and subsurface soil samples from biased locations, and step-out sampling to define the extent of contamination, as necessary. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.« less

Surgical considerations in the management of combined radiation blast injury casualties caused by a radiological dirty bomb.

PubMed

Williams, Geraint; O'Malley, Michael

2010-09-01

The capacity for surgical teams to respond appropriately to the consequences caused by the detonation of a radiological dirty bomb will be determined by prior knowledge, familiarity and training for this type unique terrorist event. This paper will focus on the surgical aspects of this scenario with particular emphasis on the management of combined trauma-radiological injury. The paper also describes some of the more serious explosion-contamination incidents from nuclear industrial sources, summarises learning points and parallels taken from these scenarios in relation to subject of a radiological dirty bomb and describes the likely radioactive substances involved. 2010 Elsevier Ltd. All rights reserved.

Corrective Action Decision Document/Closure Report for Corrective Action Unit 365: Baneberry Contamination Area, Nevada National Security Site, Nevada, Revision 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Patrick Matthews

2011-09-01

Corrective Action Unit 365 comprises one corrective action site (CAS), CAS 08-23-02, U-8d Contamination Area. The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 365 based on the implementation of the corrective action of closure in place with a use restriction (UR). Corrective action investigation (CAI) activities were performed from January 18, 2011, through August 2, 2011, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 365: Baneberry Contamination Area. The purpose of the CAI was to fulfill data needs as definedmore » during the data quality objective (DQO) process. The CAU 365 dataset of investigation results was evaluated based on a data quality assessment. This assessment demonstrated the dataset is complete and acceptable for use in supporting the DQO decisions. Investigation results were evaluated against final action levels (FALs) established in this document. A radiological dose FAL of 25 millirem per year was established based on the Remote Work Area exposure scenario (336 hours of annual exposure). Radiological doses exceeding the FAL were found to be present to the southwest of the Baneberry crater. It was also assumed that radionuclide levels present within the crater and fissure exceed the FAL. Corrective actions were undertaken that consisted of establishing a UR and posting warning signs for the crater, fissure, and the area located to the southwest of the crater where soil concentrations exceeded the FAL. These URs were recorded in the FFACO database; the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Facility Information Management System; and the NNSA/NSO CAU/CAS files. Therefore, NNSA/NSO provides the following recommendations: (1) No further corrective actions beyond what are described in this document are necessary for CAU 365. (2) A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 365. (3) Corrective Action Unit 365 should be moved from Appendix III to Appendix IV of the FFACO.« less

Analysis of Environmental Contamination resulting from ...

EPA Pesticide Factsheets

Catastrophic incidents can generate a large number of samples with analytically diverse types including forensic, clinical, environmental, food, and others. Environmental samples include water, wastewater, soil, air, urban building and infrastructure materials, and surface residue. Such samples may arise not only from contamination from the incident but also from the multitude of activities surrounding the response to the incident, including decontamination. This document summarizes a range of activities to help build laboratory capability in preparation for analysis following a catastrophic incident, including selection and development of fit-for-purpose analytical methods for chemical, biological, and radiological contaminants. Fit-for-purpose methods are those which have been selected to meet project specific data quality objectives. For example, methods could be fit for screening contamination in the early phases of investigation of contamination incidents because they are rapid and easily implemented, but those same methods may not be fit for the purpose of remediating the environment to safe levels when a more sensitive method is required. While the exact data quality objectives defining fitness-for-purpose can vary with each incident, a governing principle of the method selection and development process for environmental remediation and recovery is based on achieving high throughput while maintaining high quality analytical results. This paper illu

Support to triage and public risk perception considering long-term response to a Cs-137 radiological dispersive device scenario.

PubMed

Andrade, Cristiane Ps; Souza, Cláudio J; Camerini, Eduardo Sn; Alves, Isabela S; Vital, Hélio C; Healy, Matthew Jf; Ramos De Andrade, Edson

2018-06-01

A radiological dispersive device (RDD) spreads radioactive material, complicates the treatment of physical injuries, raises cancer risk, and induces disproportionate fear. Simulating such an event enables more effective and efficient utilization of the triage and treatment resources of staff, facilities, and space. Fast simulation can give detail on events in progress or future events. The resources for triage and treatment of contaminated trauma victims can differ for pure exposure individuals, while discouraging the "worried well" from presenting in the crisis phase by media announcement would relieve pressure on hospital facilities. The proposed methodology integrates capabilities from different platforms in a convergent way composed of three phases: (a) scenario simulation, (b) data generation, and (c) risk assessment for triage focused on follow-up epidemiological assessment. Simulations typically indicate that most of the affected population does not require immediate medical assistance. Medical triage for the few severely injured and the radiological triage to diminish the contamination with radioactivity will always be the priority. For this study, however, higher priorities should be given to individuals from radiological "warm" and "hot" zones as required by risk criteria. The proposed methodology could thus help to (a) filter and reduce the number of individuals to be attended, (b) optimize the prioritization of medical care, (c) reduce or prepare for future costs, (d) effectively locate the operational triage site to avoid possible contamination on the main facility, and (e) provide the scientific data needed to develop an adequate approach to risk and its proper communication.

Non-destructive in-situ method and apparatus for determining radionuclide depth in media

DOEpatents

Xu, X. George; Naessens, Edward P.

2003-01-01

A non-destructive method and apparatus which is based on in-situ gamma spectroscopy is used to determine the depth of radiological contamination in media such as concrete. An algorithm, Gamma Penetration Depth Unfolding Algorithm (GPDUA), uses point kernel techniques to predict the depth of contamination based on the results of uncollided peak information from the in-situ gamma spectroscopy. The invention is better, faster, safer, and/cheaper than the current practice in decontamination and decommissioning of facilities that are slow, rough and unsafe. The invention uses a priori knowledge of the contaminant source distribution. The applicable radiological contaminants of interest are any isotopes that emit two or more gamma rays per disintegration or isotopes that emit a single gamma ray but have gamma-emitting progeny in secular equilibrium with its parent (e.g., .sup.60 Co, .sup.235 U, and .sup.137 Cs to name a few). The predicted depths from the GPDUA algorithm using Monte Carlo N-Particle Transport Code (MCNP) simulations and laboratory experiments using .sup.60 Co have consistently produced predicted depths within 20% of the actual or known depth.

Processing plutonium-contaminated soil on Johnston Atoll

DOE Office of Scientific and Technical Information (OSTI.GOV)

Moroney, K.; Moroney, J. III; Turney, J.

1994-07-01

This article describes a cleanup project to process plutonium- and americium-contaminated soil on Johnston Atoll for volume reduction. Thermo Analytical`s (TMA`s) segmented gate system (SGS) for this remedial operation has been in successful on-site operation since 1992. Topics covered include the basis for development, a description of the Johnston Atoll; the significance of results; the benefits of the technology; applicability to other radiologically contaminated sites. 7 figs., 1 tab.

Radiological emergency: Malaysian preparedness and response.

PubMed

Yusof, Mohd Abd Wahab; Ali, Hamrah Mohd

2011-07-01

Planning and preparation in advance for radiological emergencies can help to minimise potential public health and environmental threats if and when an actual emergency occurs. During the planning process, emergency response organisations think through how they would respond to each type of incident and the resources that will be needed. In Malaysia, planning, preparation for and response to radiological emergencies involve many parties. In the event of a radiological emergency and if it is considered a disaster, the National Security Council, the Atomic Energy Licensing Board and the Malaysian Nuclear Agency (Nuclear Malaysia) will work together with other federal agencies, state and local governments, first responders and international organisations to monitor the situation, contain the release, and clean up the contaminated site. Throughout the response, these agencies use their protective action guidelines. This paper discusses Malaysian preparedness for, and response to, any potential radiological emergency.

Natural radioactivity measurements and dosimetric evaluations in soil samples with a high content of NORM

NASA Astrophysics Data System (ADS)

Caridi, F.; Marguccio, S.; Durante, G.; Trozzo, R.; Fullone, F.; Belvedere, A.; D'Agostino, M.; Belmusto, G.

2017-01-01

In this article natural radioactivity measurements and dosimetric evaluations in soil samples contaminated by Naturally Occurring Radioactive Materials (NORM) are made, in order to assess any possible radiological hazard for the population and for workers professionally exposed to ionizing radiations. Investigated samples came from the district of Crotone, Calabria region, South of Italy. The natural radioactivity investigation was performed by high-resolution gamma-ray spectrometry. From the measured gamma spectra, activity concentrations were determined for 226Ra , 234-mPa , 224Ra , 228Ac and 40K and compared with their clearance levels for NORM. The total effective dose was calculated for each sample as due to the committed effective dose for inhalation and to the effective dose from external irradiation. The sum of the total effective doses estimated for all investigated samples was compared to the action levels provided by the Italian legislation (D.Lgs.230/95 and subsequent modifications) for the population members (0.3mSv/y) and for professionally exposed workers (1mSv/y). It was found to be less than the limit of no radiological significance (10μSv/y).

Quadrant III RFI draft report: Volume 1

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1992-12-01

The purpose of the RCRA Facility Investigation (RFI) at The Portsmouth Gaseous Diffusion Plant (PORTS) is to acquire, analyze and interpret data that will: characterize the environmental setting, including ground water, surface water and sediment, soil and air; define and characterize sources of contamination; characterize the vertical and horizontal extent and degree of contamination of the environment; assess the risk to human health and the environment resulting from possible exposure to contaminants; and support the Corrective Measures Study (CMS), which will follow the RFI, if required. A total of 18 Solid Waste Management Units (SWMU's) were investigated. All surficial soilmore » samples (0--2 ft), sediment samples and surface-water samples proposed in the approved Quadrant III RFI Work Plan were collected as specified in the approved work plan and RFI Sampling Plan. All soil, sediment and surface-water samples were analyzed for parameters specified from the Target Compound List and Target Analyte List (TCL/TAL) as listed in the US EPA Statement of Work for Inorganic (7/88a) and Organic (2/88b) analyses for Soil and Sediment, and analyses for fluoride, Freon-113 and radiological parameters (total uranium, gross alpha, gross beta and technetium).« less

Quadrant III RFI draft report: Volume 1

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1992-12-01

The purpose of the RCRA Facility Investigation (RFI) at The Portsmouth Gaseous Diffusion Plant (PORTS) is to acquire, analyze and interpret data that will: characterize the environmental setting, including ground water, surface water and sediment, soil and air; define and characterize sources of contamination; characterize the vertical and horizontal extent and degree of contamination of the environment; assess the risk to human health and the environment resulting from possible exposure to contaminants; and support the Corrective Measures Study (CMS), which will follow the RFI, if required. A total of 18 Solid Waste Management Units (SWMU`s) were investigated. All surficial soilmore » samples (0--2 ft), sediment samples and surface-water samples proposed in the approved Quadrant III RFI Work Plan were collected as specified in the approved work plan and RFI Sampling Plan. All soil, sediment and surface-water samples were analyzed for parameters specified from the Target Compound List and Target Analyte List (TCL/TAL) as listed in the US EPA Statement of Work for Inorganic (7/88a) and Organic (2/88b) analyses for Soil and Sediment, and analyses for fluoride, Freon-113 and radiological parameters (total uranium, gross alpha, gross beta and technetium).« less

Principles on Radiological Characterization of the Unit 1 at Ignalina NPP for Decommissioning Purposes

DOE Office of Scientific and Technical Information (OSTI.GOV)

Poskas, P.; Zujus, R.; Drumstas, G.

There is only one nuclear power plant in Lithuania - Ignalina NPP (INPP). The INPP operated two similar units with installed capacity of 1500 MW(each). They were commissioned in 12/1983 and 08/1987, and the original design lifetime was projected out to 2010 and 2015 respectively. But the first Unit of Ignalina NPP was shutdown December 31, 2004, and second Unit will be closed down before 2010 taking into consideration substantial long-term financial assistance from the EU, G7 and other states as well as international institutions. Implementation of dismantling activities requires detailed knowledge of the radiological situation at the Unit 1.more » General Programme of Radiological Survey for Ignalina NPP Unit 1 based on NUREG-1575 was prepared in 2005- 2006 by Consortium led by Lithuanian Energy Institute and approved by Regulatory Bodies. It includes such main steps as historical site assessment, scoping, characterization, remedial actions/decontamination support surveys and final status surveys. General Programme of Radiological Survey defines content and principles of the surveys, and preliminary survey considerations, including identification of the contaminants, establishment of the free release levels, principles on areas classification depending on contamination potential, identification of the final survey units, criteria for selection survey instrumentation, techniques and methods etc. So, in the paper information on these principles and the content of the different stages in General Programme of Radiological Survey is presented. (authors)« less

Final Status Survey Report for Corrective Action Unit 117 - Pluto Disassembly Facility, Building 2201, Nevada National Security Site, Nevada

DOE Office of Scientific and Technical Information (OSTI.GOV)

Jeremy Gwin and Douglas Frenette

This document contains the process knowledge, radiological data and subsequent statistical methodology and analysis to support approval for the radiological release of Corrective Action Unit (CAU) 117 – Pluto Disassembly Facility, Building 2201 located in Area 26 of the Nevada National Security Site (NNSS). Preparations for release of the building began in 2009 and followed the methodology described in the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM). MARSSIM is the DOE approved process for release of Real Property (buildings and landmasses) to a set of established criteria or authorized limits. The pre-approved authorized limits for surface contamination values andmore » corresponding assumptions were established by DOE O 5400.5. The release criteria coincide with the acceptance criteria of the U10C landfill permit. The U10C landfill is the proposed location to dispose of the radiologically non-impacted, or “clean,” building rubble following demolition. However, other disposition options that include the building and/or waste remaining at the NNSS may be considered providing that the same release limits apply. The Final Status Survey was designed following MARSSIM guidance by reviewing historical documentation and radiological survey data. Following this review a formal radiological characterization survey was performed in two phases. The characterization revealed multiple areas of residual radioactivity above the release criteria. These locations were remediated (decontaminated) and then the surface activity was verified to be less than the release criteria. Once remediation efforts had been successfully completed, a Final Status Survey Plan (10-015, “Final Status Survey Plan for Corrective Action Unit 117 – Pluto Disassembly Facility, Building 2201”) was developed and implemented to complete the final step in the MARSSIM process, the Final Status Survey. The Final Status Survey Plan consisted of categorizing each individual room into one of three categories: Class 1, Class 2 or Class 3 (a fourth category is a “Non-Impacted Class” which in the case of Building 2201 only pertained to exterior surfaces of the building.) The majority of the rooms were determined to fall in the less restrictive Class 3 category, however, Rooms 102, 104, 106, and 107 were identified as containing Class 1 and 2 areas. Building 2201 was divided into “survey units” and surveyed following the requirements of the Final Status Survey Plan for each particular class. As each survey unit was completed and documented, the survey results were evaluated. Each sample (static measurement) with units of counts per minute (cpm) was corrected for the appropriate background and converted to a value with units of dpm/100 cm2. With a surface contamination value in the appropriate units, it was compared to the surface contamination limits, or in this case the derived concentration guideline level (DCGLw). The appropriate statistical test (sign test) was then performed. If the survey unit was statistically determined to be below the DCGLw, then the survey unit passed and the null hypothesis (that the survey unit is above limits) was rejected. If the survey unit was equal to or below the critical value in the sign test, the null hypothesis was not rejected. This process was performed for all survey units within Building 2201. A total of thirty-three “Class 1,” four “Class 2,” and one “Class 3” survey units were developed, surveyed, and evaluated. All survey units successfully passed the statistical test. Building 2201 meets the release criteria commensurate with the Waste Acceptance Criteria (for radiological purposes) of the U10C landfill permit residing within NNSS boundaries. Based on the thorough statistical sampling and scanning of the building’s interior, Building 2201 may be considered radiologically “clean,” or free of contamination.« less

Work plan for the radiological survey for the David Witherspoon, Incorporated, Landfill-1630 site, Knoxville, Tennessee

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1996-07-01

This work plan establishes the methods and requirements for performing a radiological survey at the David Witherspoon, Incorporated, Landfill-1630 Site, Knoxville, Tennessee (DWI 1630 Site) in accordance with requirements under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). The radiological survey will identify the radiological contamination level of the equipment and debris stored at the DWI 1630 Site. The data generated from the survey activities will support the decisions for characterization of the equipment/debris and aid in subsequent disposition and waste handling. The survey activities to be performed under this work plan include an equipment radiological survey,more » a walkover survey, and an immunoassay testing for polychlorinated biphenyls (PCBs). This work plan includes a quality assurance (QA)/quality control (QC) project plan, a health and safety (H&S) plan, and a waste management plan.« less

Corrective Action Decision Document/Closure Report for Corrective Action Unit 106: Area 5, 11 Frenchman Flat Atmospheric Sites, Nevada National Security Site, Nevada, Revision 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Patrick Matthews and Dawn Peterson

2011-09-01

Corrective Action Unit 106 comprises four corrective action sites (CASs): (1) 05-20-02, Evaporation Pond; (2) 05-23-05, Atmospheric Test Site - Able; (3) 05-45-04, 306 GZ Rad Contaminated Area; (4) 05-45-05, 307 GZ Rad Contaminated Area. The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 106 based on the implementation of corrective actions. The corrective action of clean closure was implemented at CASs 05-45-04 and 05-45-05, while no corrective action was necessary at CASs 05-20-02 and 05-23-05. Corrective action investigation (CAI) activities were performed from October 20,more » 2010, through June 1, 2011, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 106: Areas 5, 11 Frenchman Flat Atmospheric Sites. The approach for the CAI was divided into two facets: investigation of the primary release of radionuclides, and investigation of other releases (mechanical displacement and chemical releases). The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 106 dataset of investigation results was evaluated based on a data quality assessment. This assessment demonstrated the dataset is complete and acceptable for use in fulfilling the DQO data needs. Investigation results were evaluated against final action levels (FALs) established in this document. A radiological dose FAL of 25 millirem per year was established based on the Industrial Area exposure scenario (2,250 hours of annual exposure). The only radiological dose exceeding the FAL was at CAS 05-45-05 and was associated with potential source material (PSM). It is also assumed that additional PSM in the form of depleted uranium (DU) and DU-contaminated debris at CASs 05-45-04 and 05-45-05 exceed the FAL. Therefore, corrective actions were undertaken at these CASs that consisted of removing PSM and collecting verification samples. Results of verification samples show that remaining soil does not contain contamination exceeding the FALs. Therefore, the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) provides the following recommendations: (1) No further corrective actions are necessary for CAU 106. (2) A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 106. (3) Corrective Action Unit 106 should be moved from Appendix III to Appendix IV of the FFACO.« less

Estimates of the radiological dose to people living on Bikini Island for two weeks while diving in and around the sunken ships in Bikini Lagoon

DOE Office of Scientific and Technical Information (OSTI.GOV)

Robison, W.L.

1990-09-01

Bikini Island and Bikini Lagoon were contaminated by fallout from nuclear weapons tests conducted at the atoll by the United States from 1946 to 1958. The second test, Baker, of the Crossroads series was an underwater detonation in 1946 that sank several ships in the lagoon, including the USS Saratoga and the Japanese battleship Nagato. The ships received high-intensity gamma-ray and neutron bombardment from the Baker test, which induced radioactivity in the metal structures. Some of the tests conducted after the Baker shot (there were 21 tests in all) injected contaminated carbonate particles into the air, some of which weremore » deposited across the lagoon surface. Most of this contaminated soil then settled onto the ships` decks and other structures and on the lagoon bottom. These sunken ships provide an interesting location for divers. Recreational diving and swimming in and around the ships raises the question of the potential radiological dose from the radionuclides present in or on the ships and in the lagoon sediments. The purpose of this paper, therefore, is to present an analysis of the potential radiological dose to persons who would dive near the sunken ships and live on Bikini Island for a short period of time.« less

Estimates of the radiological dose to people living on Bikini Island for two weeks while diving in and around the sunken ships in Bikini Lagoon

DOE Office of Scientific and Technical Information (OSTI.GOV)

Robison, W.L.

1990-09-01

Bikini Island and Bikini Lagoon were contaminated by fallout from nuclear weapons tests conducted at the atoll by the United States from 1946 to 1958. The second test, Baker, of the Crossroads series was an underwater detonation in 1946 that sank several ships in the lagoon, including the USS Saratoga and the Japanese battleship Nagato. The ships received high-intensity gamma-ray and neutron bombardment from the Baker test, which induced radioactivity in the metal structures. Some of the tests conducted after the Baker shot (there were 21 tests in all) injected contaminated carbonate particles into the air, some of which weremore » deposited across the lagoon surface. Most of this contaminated soil then settled onto the ships' decks and other structures and on the lagoon bottom. These sunken ships provide an interesting location for divers. Recreational diving and swimming in and around the ships raises the question of the potential radiological dose from the radionuclides present in or on the ships and in the lagoon sediments. The purpose of this paper, therefore, is to present an analysis of the potential radiological dose to persons who would dive near the sunken ships and live on Bikini Island for a short period of time.« less

A Study of Emergency Room Health CAre Providers and the Fixed Facility Physical Capabilities to Manage the Presenting Radiologically Injured Patient

DTIC Science & Technology

1984-08-01

large areas 6. Contaminated hair 35 a. Shampoo with mild soap for three minutes and rinse b. Monitor and repeat step a as needed c. If contamination...M counters are generally used for surveying low-level radiation and are calibrated either in counts per minute (CPM) or milloroentgens per hours (mR... surveyed for contamination? Decontaminated D. Nature of accident: Type radiation source Other Details: E. Person in charge of radiation evaluation: F

Emerging Technologies and Techniques for Wide Area Radiological Survey and Remediation

DOE Office of Scientific and Technical Information (OSTI.GOV)

Sutton, M.; Zhao, P.

2016-03-24

Technologies to survey and decontaminate wide-area contamination and process the subsequent radioactive waste have been developed and implemented following the Chernobyl nuclear power plant release and the breach of a radiological source resulting in contamination in Goiania, Brazil. These civilian examples of radioactive material releases provided some of the first examples of urban radiological remediation. Many emerging technologies have recently been developed and demonstrated in Japan following the release of radioactive cesium isotopes (Cs-134 and Cs-137) from the Fukushima Dai-ichi nuclear power plant in 2011. Information on technologies reported by several Japanese government agencies, such as the Japan Atomic Energymore » Agency (JAEA), the Ministry of the Environment (MOE) and the National Institute for Environmental Science (NIES), together with academic institutions and industry are summarized and compared to recently developed, deployed and available technologies in the United States. The technologies and techniques presented in this report may be deployed in response to a wide area contamination event in the United States. In some cases, additional research and testing is needed to adequately validate the technology effectiveness over wide areas. Survey techniques can be deployed on the ground or from the air, allowing a range of coverage rates and sensitivities. Survey technologies also include those useful in measuring decontamination progress and mapping contamination. Decontamination technologies and techniques range from non-destructive (e.g., high pressure washing) and minimally destructive (plowing), to fully destructive (surface removal or demolition). Waste minimization techniques can greatly impact the long-term environmental consequences and cost following remediation efforts. Recommendations on technical improvements to address technology gaps are presented together with observations on remediation in Japan.« less

A garage sale bargain: A leaking 2.2 GBq source, Phase III - The radiological cleanup

DOE Office of Scientific and Technical Information (OSTI.GOV)

Vitkus, T.; Beck, W.L.; Freeman, B.

1996-06-01

As described in a previous paper, a private residence in Bristol, Tennessee, was extensively contaminated when the owner unknowingly handled a leaking {sup 226}Ra source of about 60 mCi. Contamination was found on both floors of the two-story house and in the yard. The most extensively contaminated area was a back porch where the owner initially opened the source containment box. Contamination was probably spread most by {open_quotes}tracking{close_quotes} by the owner, his wife, and several pet cats. One of the most contaminated objects found was a pillow, a favorite napping place for the cats, which read 25 mR h{sup -1}more » at contact. Several decon techniques were tried including stripable paints, washing with various agents, etc. However, decontamination was primarily accomplished by physical removal techniques, such as removing carpeting, scraping and sanding wooden surfaces, and by disposal of contaminated objects (much to the owners` dismay). The house and the yard were cleaned up to meet the recommended guidelines for unrestricted release with the expenditure of about 550 hours of effort. The groups assisting the Tennessee Division of Radiological Health included the Department of Energy, Tennessee Valley Authority`s Watts Bar Nuclear Plant, Oak Ridge Institute for Science and Education, Oak Ridge National Laboratory, and Scientific Ecology Group. All of the assistance was provided at no cost to the home owner or the State of Tennessee.« less

Water System Security and Resilience in Homeland Security Research

EPA Pesticide Factsheets

EPA's water security research provides tools needed to improve infrastructure security and to recover from an attack or contamination incident involving chemical, biological, or radiological (CBR) agents or weapons.

Report on the remedial investigation of Bear Creek Valley at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 5: Appendix F -- Baseline human health risk assessment report

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1996-09-01

This Remedial Investigation (RI) Report characterizes the nature and extent of contamination, evaluates the fate and transport of contaminants, and assesses risk to human health and the environment resulting from waste disposal and other US Department of Energy (DOE) operations in Bear Creek Valley (BCV). BCV, which is located within the DOE Oak Ridge Reservation (ORR) encompasses multiple waste units containing hazardous and radioactive wastes arising from operations at the adjacent Oak Ridge Y-12 Plant. The primary waste units discussed in this RI Report are the S-3 Site, Oil Landfarm (OLF), Boneyard/Burnyard (BYBY), Sanitary Landfill 1 (SL 1), and Bearmore » Creek Burial Grounds (BCBG). These waste units, plus the contaminated media resulting from environmental transport of the wastes from these units, are the subject of this RI. This BCV RI Report represents the first major step in the decision-making process for the BCV watershed. The RI results, in concert with the follow-on FS will form the basis for the Proposed Plan and Record of Decision for all BCV sites. This comprehensive decision document process will meet the objectives of the watershed approach for BCV. Appendix F documents potential risks and provides information necessary for making remediation decisions. A quantitative analysis of the inorganic, organic, and radiological site-related contaminants found in various media is used to characterize the potential risks to human health associated with exposure to these contaminants.« less

Chemical, Biological, and Radiological (CBR) Contamination Survivability, Large Item Interiors

DTIC Science & Technology

2016-08-03

e.g., mud, grease, etc.). m. Pretest (baseline) and posttest (30 days after the first contamination and/or other defined long-term time interval...procedures used. f. Description of SUT-interior materials of construction, paint type, and surface condition (pretest and posttest ), including...difficult to decontaminate or allow liquid to penetrate. g. Pretest and posttest ME functional performance characteristics (when measured) used as

3D unmanned aerial vehicle radiation mapping for assessing contaminant distribution and mobility

NASA Astrophysics Data System (ADS)

Martin, P. G.; Kwong, S.; Smith, N. T.; Yamashiki, Y.; Payton, O. D.; Russell-Pavier, F. S.; Fardoulis, J. S.; Richards, D. A.; Scott, T. B.

2016-10-01

Following the events of March 2011 at the Fukushima Daiichi Nuclear Power Plant, significant quantities of radioactive material were released into the local and wider global environment. At five years since the incident, much expense is being currently devoted to the remediation of a large portion of eastern Japan contaminated primarily by radiocesium, yet further significant expenditure will be required over the succeeding decades to complete this clean-up. People displaced from their homes by the incident are now increasingly keen to return, making it more important than ever to provide accurate quantification and representation of any residual radiological contamination. Presented here is the use of an unmanned aerial vehicle equipped with a laser rangefinder unit to generate a three dimensional point-cloud of an area onto which a radiation contamination map, also obtained concurrently via the unmanned aerial platform, can be rendered. An exemplar site of an un-remediated farm consisting of multiple stepped rice paddy fields with a dedicated irrigation system was used for this work. The results obtained show that heightened radiological contamination exists around the site within the drainage network where material is observed to have collected, having been transported by transient water runoff events. These results obtained in May 2014 suggest that a proportion of the fallout material is highly mobile within the natural environment and is likely to be transported further through the system over the succeeding years.

Penetration and decontamination of americium-241 ex vivo using fresh and frozen pig skin.

PubMed

Tazrart, A; Bolzinger, M A; Moureau, A; Molina, T; Coudert, S; Angulo, J F; Briancon, S; Griffiths, N M

2017-04-01

Skin contamination is one of the most probable risks following major nuclear or radiological incidents. However, accidents involving skin contamination with radionuclides may occur in the nuclear industry, in research laboratories and in nuclear medicine departments. This work aims to measure the penetration of the radiological contaminant Americium ( 241 Am) in fresh and frozen skin and to evaluate the distribution of the contamination in the skin. Decontamination tests were performed using water, Fuller's earth and diethylene triamine pentaacetic acid (DTPA), which is the recommended treatment in case of skin contamination with actinides such as plutonium or americium. To assess these parameters, we used the Franz cell diffusion system with full-thickness skin obtained from pigs' ears, representative of human skin. Solutions of 241 Am were deposited on the skin samples. The radioactivity content in each compartment and skin layers was measured after 24 h by liquid scintillation counting and alpha spectrophotometry. The Am cutaneous penetration to the receiver compartment is almost negligible in fresh and frozen skin. Multiple washings with water and DTPA recovered about 90% of the initial activity. The rest remains fixed mainly in the stratum corneum. Traces of activity were detected within the epidermis and dermis which is fixed and not accessible to the decontamination. Copyright © 2016 Elsevier Ireland Ltd. All rights reserved.

Kara Sea radioactivity assessment.

PubMed

Osvath, I; Povinec, P P; Baxter, M S

1999-09-30

Investigations following five international expeditions to the Kara Sea have shown that no radiologically significant contamination has occurred outside of the dumping sites in Novaya Zemlya bays. Increased levels of radionuclides in sediment have only been observed in Abrosimov and Stepovoy Bays very close to dumped containers. Evaluations of radionuclide inventories in water and sediment of the open Kara Sea and Novaya Zemlya bays as well as soil from the shore of Abrosimov bay have shown that radionuclide contamination of the open Kara Sea is mainly due to global fallout, with smaller contributions from the Sellafield reprocessing plant, the Chernobyl accident run-off from the Ob and Yenisey rivers and local fallout. Computer modelling results have shown that maximum annual doses of approximately 1 mSv are expected for a hypothetical critical group subsisting on fish caught in the Novaya Zemlya bays whereas populations living on the mainland can be expected to receive doses at least three orders of magnitude lower.

Cleanup Verification Package for the 300-18 Waste Site

DOE Office of Scientific and Technical Information (OSTI.GOV)

J. M. Capron

This cleanup verification package documents completion of remedial action for the 300-18 waste site. This site was identified as containing radiologically contaminated soil, metal shavings, nuts, bolts, and concrete.

Environmental Response Laboratory Network (ERLN) Overview

EPA Pesticide Factsheets

The Environmental Response Laboratory Network provides Federal, State, and local decision-makers with reliable, high quality analytical data used to identify chemical, biological, and radiological contaminants collected in support of response and cleanup.

Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron-Activated Shield Wall

DOE Office of Scientific and Technical Information (OSTI.GOV)

Michael R. Kruzic

2008-06-01

Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility (Figure 1) was used in the early to mid-1960s for testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles. The TCA facility, known as Corrective Action Unit 115, was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the Federal Facility Agreement and Consentmore » Order. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously, provided technical decisions are made by an experienced decision maker within the site conceptual site model. Facility closure involved a seven-step decommissioning strategy. First, preliminary investigation activities were performed, including review of process knowledge documentation, targeted facility radiological and hazardous material surveys, concrete core drilling and analysis, shield wall radiological characterization, and discrete sampling, which proved to be very useful and cost-effective in subsequent decommissioning planning and execution and worker safety. Second, site setup and mobilization of equipment and personnel were completed. Third, early removal of hazardous materials, including asbestos, lead, cadmium, and oil, was performed ensuring worker safety during more invasive demolition activities. Process piping was to be verified void of contents. Electrical systems were de-energized and other systems were rendered free of residual energy. Fourth, areas of high radiological contamination were decontaminated using multiple methods. Contamination levels varied across the facility. Fixed beta/gamma contamination levels ranged up to 2 million disintegrations per minute (dpm)/100 centimeters squared (cm2) beta/gamma. Removable beta/gamma contamination levels seldom exceeded 1,000 dpm/100 cm2, but, in railroad trenches on the reactor pad containing soil on the concrete pad in front of the shield wall, the beta dose rates ranged up to 120 milli-roentgens per hour from radioactivity entrained in the soil. General area dose rates were less than 100 micro-roentgens per hour. Prior to demolition of the reactor shield wall, removable and fixed contaminated surfaces were decontaminated to the best extent possible, using traditional decontamination methods. Fifth, large sections of the remaining structures were demolished by mechanical and open-air controlled explosive demolition (CED). Mechanical demolition methods included the use of conventional demolition equipment for removal of three main buildings, an exhaust stack, and a mobile shed. The 5-foot (ft), 5-inch (in.) thick, neutron-activated reinforced concrete shield was demolished by CED, which had never been performed at the NTS.« less

Tonopah Test Range Air Monitoring: CY2016 Meteorological, Radiological, and Wind Transported Particulate Observations

DOE Office of Scientific and Technical Information (OSTI.GOV)

Chapman, Jenny; Nikolich, George; Shadel, Craig

In 1963, the U.S. Department of Energy (DOE) (formerly the Atomic Energy Commission [AEC]), implemented Operation Roller Coaster on the Tonopah Test Range (TTR) and an adjacent area of the Nevada Test and Training Range (NTTR) (formerly the Nellis Air Force Range). This operation resulted in radionuclide-contaminated soils at the Clean Slate I, II, and III sites. This report documents observations made during ongoing monitoring of radiological, meteorological, and dust conditions at stations installed adjacent to Clean Slate I and Clean Slate III, and at the TTR Sandia National Laboratories (SNL) Range Operations Control (ROC) center. The primary objective ofmore » the monitoring effort is to determine if wind blowing across the Clean Slate sites is transporting particles of radionuclide-contaminated soil beyond the physical and administrative boundaries of the sites.« less

Guidelines for handling radioactively contaminated decedents.

PubMed

Wood, Charles M; DePaolo, Frank; Whitaker, Doggett

2008-05-01

The Centers for Disease Control and Prevention recently issued guidelines for medical examiners, coroners, and morticians in dealing with decedents after detonation of an improvised nuclear device (IND) or radiological dispersal device (RDD) (). Partners in this effort included the New York City Office of Chief Medical Examiner and the National Funeral Directors' Association. This paper describes the handling techniques required for loose surface contamination, radioactive shrapnel, and internal contamination caused by inhaling or ingesting radioactive materials from an IND or RDD, and provides suggested guidelines for medical examiners, coroners, and morticians to deal with these situations.

Skin decontamination: principles and perspectives.

PubMed

Chan, Heidi P; Zhai, Hongbo; Hui, Xiaoying; Maibach, Howard I

2013-11-01

Skin decontamination is the primary intervention needed in chemical, biological and radiological exposures, involving immediate removal of the contaminant from the skin performed in the most efficient way. The most readily available decontamination system on a practical basis is washing with soap and water or water only. Timely use of flushing with copious amounts of water may physically remove the contaminant. However, this traditional method may not be completely effective, and contaminants left on the skin after traditional washing procedures can have toxic consequences. This article focuses on the principles and practices of skin decontamination.

Managing Internal Radiation Contamination Following an Emergency: Identification of Gaps and Priorities.

PubMed

Li, Chunsheng; Ansari, Armin; Etherington, George; Jourdain, Jean-Rene; Kukhta, Boris; Kurihara, Osamu; Lopez, Maria Antonia; Ménétrier, Florence; Alves Dos Reis, Arlene; Solomon, Stephen; Zhang, Jiangfeng; Carr, Zhanat

2016-09-01

Following a radiological or nuclear emergency, first responders and the public may become internally contaminated with radioactive materials, as demonstrated during the Goiânia, Chernobyl and Fukushima accidents. Timely monitoring of the affected populations for potential internal contamination, assessment of radiation dose and the provision of necessary medical treatment are required to minimize the health risks from the contamination. This paper summarizes the guidelines and tools that have been developed, and identifies the gaps and priorities for future projects. © World Health Organisation 2016. All rights reserved. The World Health Organization has granted Oxford University Press permission for the reproduction of this article.

Requirements for estimation of doses from contaminants dispersed by a 'dirty bomb' explosion in an urban area.

PubMed

Andersson, K G; Mikkelsen, T; Astrup, P; Thykier-Nielsen, S; Jacobsen, L H; Hoe, S C; Nielsen, S P

2009-12-01

The ARGOS decision support system is currently being extended to enable estimation of the consequences of terror attacks involving chemical, biological, nuclear and radiological substances. This paper presents elements of the framework that will be applied in ARGOS to calculate the dose contributions from contaminants dispersed in the atmosphere after a 'dirty bomb' explosion. Conceptual methodologies are presented which describe the various dose components on the basis of knowledge of time-integrated contaminant air concentrations. Also the aerosolisation and atmospheric dispersion in a city of different types of conceivable contaminants from a 'dirty bomb' are discussed.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Nichols, T.

The Nuclear Forensics Analysis Center (NFAC) is part of Savannah River National Laboratory (SRNL) and is one of only two USG National Laboratories accredited to perform nuclear forensic analyses to the requirements of ISO 17025. SRNL NFAC is capable of analyzing nuclear and radiological samples from bulk material to ultra-trace samples. NFAC provides analytical support to the FBI's Radiological Evidence Examination Facility (REEF), which is located within SRNL. REEF gives the FBI the capability to perform traditional forensics on material that is radiological and/or is contaminated. SRNL is engaged in research and development efforts to improve the USG technical nuclearmore » forensics capabilities. Research includes improving predictive signatures and developing a database containing comparative samples.« less

Environmental impacts of the release of a transuranic actinide, americium-241, from a contaminated facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Want, J.; Merry-Libby, P.

1985-10-29

Americium-241 is widely used as a radiation source, but it also has some potential risk if taken into the body because of its high dose conversion factor. Although the radiotoxicity of americium-241 is small compared to other transuranic actinides, its effects on the reproductive system and on development of the placenta are more damaging than the effects of plutonium-239. In Ohio, a gemologist's laboratory was contaminated with americium-241. Prior to decontamination of the laboratory, potential radiological impacts to the surrounding environment were assessed. A hypothetical fire accident resulting in a unit release (1 curie) was assumed. Potential radiological impacts weremore » simulated using an atmospheric dispersion and dosimetry model with local meteorological data, population census data, and detailed information regarding the neighborhood. The results indicate that there could have been a significant impact on nearby residents from americium-241 via atmospheric dispersion if a major catastrophic release had occurred prior to contamination and decommissioning of the laboratory. 14 refs., 3 figs., 2 tabs.« less

Plutonium Particle Migration in the Shallow Vadose Zone: The Nevada Test Site as an Analog Site

NASA Astrophysics Data System (ADS)

Hunt, J. R.; Smith, D. K.

2004-12-01

The upper meter of the vadose zone in desert environments is the horizon where wastes have been released and human exposure is determined through dermal, inhalation, and food uptake pathways. This region is also characterized by numerous coupled processes that determine contaminant transport, including precipitation infiltration, evapotranspiration, daily and annual temperature cycling, dust resuspension, animal burrowing, and geochemical weathering reactions. While there is considerable interest in colloidal transport of minerals, pathogenic organisms, and contaminants in the vadose zone, there are limited field sites where the actual occurrence of contaminant migration can be quantified over the appropriate spatial and temporal scales of interest. At the US Department of Energy Nevada Test Site, there have been numerous releases of radionuclides since the 1950's that have become field-scale tracer tests. One series of tests was the four safety shots conducted in an alluvial valley of Area 11 in the 1950's. These experiments tested the ability of nuclear materials to survive chemical explosions without initiating fission reactions. Four above-ground tests were conducted and they released plutonium and uranium on the desert valley floor with only one of the tests undergoing some fission. Shortly after the tests, the sites were surveyed for radionuclide distribution on the land surface using aerial surveys and with depth. Additional studies were conducted in the 1970's to better understand the fate of plutonium in the desert that included studies of depth distribution and dust resuspension. More recently, plutonium particle distribution in the soil profile was detected using autoradiography. The results to date demonstrate the vertical migration of plutonium particles to depths in excess of 30 cm in this arid vadose zone. While plutonium migration at the Nevada Test Site has been and continues to be a concern, these field experiments have become analog sites for the release of radiological materials potentially important to consequence management investigations. In particular, these 50-year old experiments with long and detailed site investigations under relative undisturbed conditions offer insights into transport pathways that must be represented in simulation models that evaluate responses to radiological dispersal devices (RDDs). A compilation of the available site characterization data suggests additional experimental and modeling programs that can ultimately quantify the fate of contaminant particles released at the soil surface.

Tonopah Test Range Air Monitoring: CY2015 Meteorological, Radiological, and Airborne Particulate Observations

DOE Office of Scientific and Technical Information (OSTI.GOV)

Nikolich, George; Shadel, Craig; Chapman, Jenny

2016-09-01

In 1963, the U.S. Department of Energy (DOE) (formerly the Atomic Energy Commission [AEC]), implemented Operation Roller Coaster on the Tonopah Test Range (TTR) and an adjacent area of the Nevada Test and Training Range (NTTR) (formerly the Nellis Air Force Range). The operation resulted in radionuclide-contaminated soils at the Clean Slate I, II, and III sites. This report documents observations made during ongoing monitoring of radiological, meteorological, and dust conditions at stations installed adjacent to Clean Slate I and Clean Slate III, and at the TTR Sandia National Laboratories (SNL) Range Operations Control (ROC) center. The primary objective ofmore » the monitoring effort is to determine if winds blowing across the Clean Slate sites are transporting particles of radionuclide-contaminated soil beyond the physical and administrative boundaries of the sites. Radionuclide assessment of airborne particulates in 2015 found the gross alpha and gross beta values of dust collected from the filters at the monitoring stations are consistent with background conditions. The meteorological and particle monitoring indicate that conditions for wind-borne contaminant movement exist at the Clean Slate sites and that, although the transport of radionuclide-contaminated soil by suspension has not been detected, movement by saltation is occurring.« less

Preliminary site survey report for the Uniroyal Chemical Company, formerly the Diamond Magnesium Company, 720 Fairport-Nursery Road, Painesville, Ohio (DMP001)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Foley, R.D.; Floyd, L.M.

1990-03-01

At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducted a preliminary radiological survey at the Uniroyal Chemical Company, formerly the Diamond Magnesium Company, 720 Fairport-Nursery Road, Painesville, Ohio (DMP001), in 1988. The purpose of the survey was to determine whether the property was contaminated with radioactive residues from the former Manhattan Engineer District (MED) project. The scope of this preliminary survey primarily covered the area west of the buildings around the railroad car spill containment basin. The survey included direct measurement of gamma radiation levels at the surface and soil samplingmore » for radionuclide analyses. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria for both {sup 238}U and {sup 226}Ra in soil. Based on the results of this radiological assessment, it is recommended that a follow-up, detailed radiological survey of both surface and subsurface environs be performed to more precisely define the extent of the contamination. 5 refs., 10 figs., 3 tabs.« less

Corrective Action Investigation Plan for Corrective Action Unit 428: Area 3 Septic Waste Systems 1 and 5, Tonopah Test Range, Nevada, REVISION 0, march 1999

DOE Office of Scientific and Technical Information (OSTI.GOV)

ITLV.

1999-03-01

The Corrective Action Investigation Plan for Corrective Action Unit 428, Area 3 Septic Waste Systems 1 and 5, has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the U. S. Department of Energy, Nevada Operations Office; the State of Nevada Division of Environmental Protection; and the U. S. Department of Defense. Corrective Action Unit 428 consists of Corrective Action Sites 03- 05- 002- SW01 and 03- 05- 002- SW05, respectively known as Area 3 Septic Waste System 1 and Septic Waste System 5. This Corrective Action Investigation Plan is used inmore » combination with the Work Plan for Leachfield Corrective Action Units: Nevada Test Site and Tonopah Test Range, Nevada , Rev. 1 (DOE/ NV, 1998c). The Leachfield Work Plan was developed to streamline investigations at leachfield Corrective Action Units by incorporating management, technical, quality assurance, health and safety, public involvement, field sampling, and waste management information common to a set of Corrective Action Units with similar site histories and characteristics into a single document that can be referenced. This Corrective Action Investigation Plan provides investigative details specific to Corrective Action Unit 428. A system of leachfields and associated collection systems was used for wastewater disposal at Area 3 of the Tonopah Test Range until a consolidated sewer system was installed in 1990 to replace the discrete septic waste systems. Operations within various buildings at Area 3 generated sanitary and industrial wastewaters potentially contaminated with contaminants of potential concern and disposed of in septic tanks and leachfields. Corrective Action Unit 428 is composed of two leachfield systems in the northern portion of Area 3. Based on site history collected to support the Data Quality Objectives process, contaminants of potential concern for the site include oil/ diesel range total petroleum hydrocarbons, and Resource Conservation and Recovery Act characteristic volatile organic compounds, semivolatile organic compounds, and metals. A limited number of samples will be analyzed for gamma- emitting radionuclides and isotopic uranium from four of the septic tanks and if radiological field screening levels are exceeded. Additional samples will be analyzed for geotechnical and hydrological properties and a bioassessment may be performed. The technical approach for investigating this Corrective Action Unit consists of the following activities: Perform video surveys of the discharge and outfall lines. Collect samples of material in the septic tanks. Conduct exploratory trenching to locate and inspect subsurface components. Collect subsurface soil samples in areas of the collection system including the septic tanks and outfall end of distribution boxes. Collect subsurface soil samples underlying the leachfield distribution pipes via trenching. Collect surface and near- surface samples near potential locations of the Acid Sewer Outfall if Septic Waste System 5 Leachfield cannot be located. Field screen samples for volatile organic compounds, total petroleum hydrocarbons, and radiological activity. Drill boreholes and collect subsurface soil samples if required. Analyze samples for total volatile organic compounds, total semivolatile organic compounds, total Resource Conservation and Recovery Act metals, and total petroleum hydrocarbons (oil/ diesel range organics). Limited number of samples will be analyzed for gamma- emitting radionuclides and isotopic uranium from particular septic tanks and if radiological field screening levels are exceeded. Collect samples from native soils beneath the distribution system and analyze for geotechnical/ hydrologic parameters. Collect and analyze bioassessment samples at the discretion of the Site Supervisor if total petroleum hydrocarbons exceed field- screening levels.« less

Factors that elevate the internal radionuclide and chemical retention, dose and health risks to infants and children in a radiological-nuclear emergency.

PubMed

Richardson, Richard B

2009-06-01

The factors that influence the dose and risk to vulnerable population groups from exposure and internal uptake of chemicals are examined and, in particular, the radionuclides released in chemical, biological, radiological, nuclear and explosive events. The paper seeks to identify the areas that would benefit from further research. The intake and body burdens of carbon and calcium were assessed as surrogates for contaminants that either act like or bind to hydrocarbons (e.g. tritium and (14)C) or bone-seeking radionuclides (e.g. (90)Sr and (239)Pu). The shortest turnover times for such materials in the whole body were evaluated for the newborn: 11 d and 0.5 y for carbon and calcium, respectively. However, their biokinetic behaviour is complicated by a particularly high percentage of the gut-absorbed dietary intake of carbon (approximately 16%) and calcium (approximately 100%) that is incorporated into the soft tissue and skeleton of the growing neonate. The International Commission on Radiological Protection dose coefficients (Sv Bq(-1)) were examined for 14 radionuclides, including 9 of concern because of their potential use in radiological dispersal devices. The dose coefficients for a 3-month-old are greater than those for adults (2-56 times more for ingestion and 2-12 times for inhalation). The age-dependent dose and exposure assessment of contaminant intakes would improve by accounting for gender and growth where it is currently neglected. Health risk is evaluated as the product of the exposure and hazard factors, the latter being about 10-fold greater in infants than in adults. The exposure factor is also approximately 10-fold higher for ingestion by infants than by adults, and unity for inhalation varying with the contaminant. Qualitative and quantitative physiological and epidemiological evidence supports infants being more vulnerable to cancer and neurological deficit than older children.

Radiological Exposure Devices (RED) Technical Basis for Threat Profile.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Bland, Jesse John; Potter, Charles A.; Homann, Steven

Facilities that manufacture, store or transport significant quantities of radiological material must protect against the risk posed by sabotage events. Much of the analysis of this type of event has been focused on the threat from a radiological dispersion device (RDD) or "dirty bomb" scenario, in which a malicious assailant would, by explosives or other means, loft a significant quantity of radioactive material into a plume that would expose and contaminate people and property. Although the consequences in cost and psychological terror would be severe, no intentional RDD terrorism events are on record. Conversely, incidents in which a victim ormore » victims were maliciously exposed to a Radiological Exposure Device (RED), without dispersal of radioactive material, are well documented. This paper represents a technical basis for the threat profile related to the risk of nefarious use of an RED, including assailant and material characterization. Radioactive materials of concern are detailed in Appendix A.« less

Effective radiological contamination control and monitoring techniques in high alpha environments.

PubMed

Funke, Kevin C

2003-02-01

In the decommissioning of a highly contaminated alpha environment, such as the one at Hanford's 233-S Plutonium Concentration Facility, one of the key elements of a successful radiological control program is an integrated safety approach. This approach begins with the job-planning phase where the scope of the work is described. This is followed by a brainstorming session involving engineering and craft to identify how to perform the work in a logical sequence of events. Once the brainstorming session is over, a Job Hazard Analysis is performed to identify any potential problems. Mockups are utilized to enable the craft to get hands on experience and provide feedback and ideas to make the job run smoother. Ideas and experience gained during mockups are incorporated into the task instruction. To assure appropriate data are used in planning and executing the job, our principal evaluation tools included lapel and workplace air sampling, plus continuous air monitors and frequent surveys to effectively monitor job progress. In this highly contaminated alpha environment, with contamination levels ranging from 0.3 Bq cm-2 to approximately 100,000 Bq cm-2 (2,000 dpm per 100 cm2 to approximately 600 million dpm per 100 cm2), with average working levels of 1,600-3,200 Bq cm-2 (10-20 million dpm per 100 cm2) without concomitant ambient radiation levels, control of the spread of contamination is key to keeping airborne levels As Low As Reasonably Achievable.

Effective Radiological Contamination Control and Monitoring Techniques In High Alpha Environments.

PubMed

Funke, Kevin C.

2003-02-01

In the decommissioning of a highly contaminated alpha environment, such as the one at Hanford's 233-S Plutonium Concentration Facility, one of the key elements of a successful radiological control program is an integrated safety approach. This approach begins with the job-planning phase where the scope of the work is described. This is followed by a brainstorming session involving engineering and craft to identify how to perform the work in a logical sequence of events. Once the brainstorming session is over, a Job Hazard Analysis is performed to identify any potential problems. Mockups are utilized to enable the craft to get hands on experience and provide feedback and ideas to make the job run smoother. Ideas and experience gained during mockups are incorporated into the task instruction. To assure appropriate data are used in planning and executing the job, our principal evaluation tools included lapel and workplace air sampling, plus continuous air monitors and frequent surveys to effectively monitor job progress. In this highly contaminated alpha environment, with contamination levels ranging from 0.3 Bq cm to approximately 100,000 Bq cm (2,000 dpm per 100 cm to approximately 600 million dpm per 100 cm ), with average working levels of 1,600-3,200 Bq cm (10-20 million dpm per 100 cm ) without concomitant ambient radiation levels, control of the spread of contamination is key to keeping airborne levels As Low As Reasonably Achievable.

TOP 08-2-111B Chemical, Biological, and Radiological (CBR) Contamination Survivability, Small Items of Equipment

DTIC Science & Technology

2016-03-16

e.g., mud, grease, and other). j. Pretest (baseline) and posttest (30 days after the first contamination and/or other defined long-term time...item surface condition (pretest and posttest ), materials of construction, paint type, and surface cleanliness (e.g., mud, grease, decontamination...penetrate. h. Pretest and posttest ME functional performance characteristics used as the measure of the test item’s mission performance before

USE OF THE AERIAL MEASUREMENT SYSTEM HELICOPTER EMERGENCY RESPONSE ACQUISITION SYSTEMS WITH GEOGRAPHIC INFORMATION SYSTEM FOR RADIOACTIVE SOIL REMEDIATION - [11504

DOE Office of Scientific and Technical Information (OSTI.GOV)

BROCK CT

2011-02-15

The Aerial Measurement System (AMS) Helicopter Emergency Response Acquisition System provides a thorough and economical means to identify and characterize the contaminants for large area radiological surveys. The helicopter system can provide a 100-percent survey of an area that qualifies as a scoping survey under the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) methodology. If the sensitivity is adequate when compared to the clean up values, it may also be used for the characterization survey. The data from the helicopter survey can be displayed and manipulated to provide invaluable data during remediation activities.

Educating medical staff about responding to a radiological or nuclear emergency.

PubMed

McCurley, M Carol; Miller, Charles W; Tucker, Florie E; Guinn, Amy; Donnelly, Elizabeth; Ansari, Armin; Holcombe, Maire; Nemhauser, Jeffrey B; Whitcomb, Robert C

2009-05-01

A growing body of audience research reveals medical personnel in hospitals are unprepared for a large-scale radiological emergency such as a terrorist event involving radioactive or nuclear materials. Also, medical personnel in hospitals lack a basic understanding of radiation principles, as well as diagnostic and treatment guidelines for radiation exposure. Clinicians have indicated that they lack sufficient training on radiological emergency preparedness; they are potentially unwilling to treat patients if those patients are perceived to be radiologically contaminated; and they have major concerns about public panic and overloading of clinical systems. In response to these findings, the Centers for Disease Control and Prevention (CDC) has developed a tool kit for use by hospital medical personnel who may be called on to respond to unintentional or intentional mass-casualty radiological and nuclear events. This tool kit includes clinician fact sheets, a clinician pocket guide, a digital video disc (DVD) of just-in-time basic skills training, a CD-ROM training on mass-casualty management, and a satellite broadcast dealing with medical management of radiological events. CDC training information emphasizes the key role that medical health physicists can play in the education and support of emergency department activities following a radiological or nuclear mass-casualty event.

Reducing Contingency through Sampling at the Luckey FUSRAP Site - 13186

DOE Office of Scientific and Technical Information (OSTI.GOV)

Frothingham, David; Barker, Michelle; Buechi, Steve

2013-07-01

Typically, the greatest risk in developing accurate cost estimates for the remediation of hazardous, toxic, and radioactive waste sites is the uncertainty in the estimated volume of contaminated media requiring remediation. Efforts to address this risk in the remediation cost estimate can result in large cost contingencies that are often considered unacceptable when budgeting for site cleanups. Such was the case for the Luckey Formerly Utilized Sites Remedial Action Program (FUSRAP) site near Luckey, Ohio, which had significant uncertainty surrounding the estimated volume of site soils contaminated with radium, uranium, thorium, beryllium, and lead. Funding provided by the American Recoverymore » and Reinvestment Act (ARRA) allowed the U.S. Army Corps of Engineers (USACE) to conduct additional environmental sampling and analysis at the Luckey Site between November 2009 and April 2010, with the objective to further delineate the horizontal and vertical extent of contaminated soils in order to reduce the uncertainty in the soil volume estimate. Investigative work included radiological, geophysical, and topographic field surveys, subsurface borings, and soil sampling. Results from the investigative sampling were used in conjunction with Argonne National Laboratory's Bayesian Approaches for Adaptive Spatial Sampling (BAASS) software to update the contaminated soil volume estimate for the site. This updated volume estimate was then used to update the project cost-to-complete estimate using the USACE Cost and Schedule Risk Analysis process, which develops cost contingencies based on project risks. An investment of $1.1 M of ARRA funds for additional investigative work resulted in a reduction of 135,000 in-situ cubic meters (177,000 in-situ cubic yards) in the estimated base volume estimate. This refinement of the estimated soil volume resulted in a $64.3 M reduction in the estimated project cost-to-complete, through a reduction in the uncertainty in the contaminated soil volume estimate and the associated contingency costs. (authors)« less

Corrective Action Investigation Plan for Corrective Action Unit 413: Clean Slate II Plutonium Dispersion (TTR) Tonopah Test Range, Nevada, Revision 1

DOE Office of Scientific and Technical Information (OSTI.GOV)

Matthews, Patrick; Burmeister, Mark; Gallo, Patricia

Corrective Action Unit (CAU) 413 is located on the Tonopah Test Range, which is approximately 130 miles northwest of Las Vegas, Nevada, and approximately 40 miles southeast of Tonopah, Nevada. The CAU 413 site consists of the release of radionuclides to the surface and shallow subsurface from the conduct of the Clean Slate II (CSII) storage–transportation test conducted on May 31, 1963. CAU 413 includes one corrective action site (CAS), TA-23-02CS (Pu Contaminated Soil). The known releases at CAU 413 are the result of the atmospheric deposition of contamination from the 1963 CSII test. The CSII test was a non-nuclearmore » detonation of a nuclear device located inside a reinforced concrete bunker covered with 2 feet of soil. This test dispersed radionuclides, primarily plutonium, on the ground surface. The presence and nature of contamination at CAU 413 will be evaluated based on information collected from a corrective action investigation (CAI). The investigation is based on the data quality objectives (DQOs) developed on June 17, 2015, by representatives of the Nevada Division of Environmental Protection; the U.S. Air Force; and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 413. The CAI will include radiological surveys, geophysical surveys, collection and analyses of soil samples, and assessment of investigation results. The collection of soil samples will be accomplished using both probabilistic and judgmental sampling approaches. To facilitate site investigation and the evaluation of DQO decisions, the releases at CAU 413 have been divided into seven study groups.« less

Radiological Monitoring Equipment For Real-Time Quantification Of Area Contamination In Soils And Facility Decommissioning

DOE Office of Scientific and Technical Information (OSTI.GOV)

M. V. Carpenter; Jay A. Roach; John R Giles

2005-09-01

The environmental restoration industry offers several sys¬tems that perform scan-type characterization of radiologically contaminated areas. The Idaho National Laboratory (INL) has developed and deployed a suite of field systems that rapidly scan, characterize, and analyse radiological contamination in surface soils. The base system consists of a detector, such as sodium iodide (NaI) spectrometers, a global positioning system (GPS), and an integrated user-friendly computer interface. This mobile concept was initially developed to provide precertifica¬tion analyses of soils contaminated with uranium, thorium, and radium at the Fernald Closure Project, near Cincinnati, Ohio. INL has expanded the functionality of this basic system tomore » create a suite of integrated field-deployable analytical systems. Using its engineering and radiation measurement expertise, aided by computer hardware and software support, INL has streamlined the data acquisition and analysis process to provide real-time information presented on wireless screens and in the form of coverage maps immediately available to field technicians. In addition, custom software offers a user-friendly interface with user-selectable alarm levels and automated data quality monitoring functions that validate the data. This system is deployed from various platforms, depending on the nature of the survey. The deployment platforms include a small all-terrain vehicle used to survey large, relatively flat areas, a hand-pushed unit for areas where manoeuvrability is important, an excavator-mounted system used to scan pits and trenches where personnel access is restricted, and backpack- mounted systems to survey rocky shoreline features and other physical settings that preclude vehicle-based deployment. Variants of the base system include sealed proportional counters for measuring actinides (i.e., plutonium-238 and americium-241) in building demolitions, soil areas, roadbeds, and process line routes at the Miamisburg Closure Project near Dayton, Ohio. In addition, INL supports decontamination operations at the Oak Ridge National Laboratory.« less

Are emergency care nurses prepared for chemical, biological, radiological, nuclear or explosive incidents?

PubMed

Mitchell, Christina J; Kernohan, W George; Higginson, Ray

2012-07-01

Two main areas exist within emergency care where chemical, biological, radiological, nuclear and explosive preparedness can be focused: departmental preparedness and staff preparedness. This study focused upon the latter. To identify areas where nurses require training in order to improve preparedness for a CBRNe incident. A competency questionnaire was developed from the literature and completed by 50 nursing staff across three Emergency Departments within one NHS Trust in Northern Ireland. Descriptive analysis was used for the quantitative data along with content analysis for the qualitative questions. Six key areas were identified for training; waste management (including clinical waste, contaminated clothing, contaminated water and the management of the contaminated deceased), Triage, Chain of command, PODs, awareness of the range of Personal Protective Equipment and its appropriate use and the decontamination of people and equipment. There is a need for a standardised 'blueprint' of role-specific competency criteria for a CBRNe incident for all emergency healthcare staff. The assessment tool used in this study can help to assess levels of preparedness amongst nursing staff and, if adapted accordingly, help gauge preparedness of other key healthcare professionals. Copyright © 2011 Elsevier Ltd. All rights reserved.

Population dose near the Semipalatinsk test site.

PubMed

Hille, R; Hill, P; Bouisset, P; Calmet, D; Kluson, J; Seisebaev, A; Smagulov, S

1998-10-01

To determine the consequences of atmospheric atomic bomb tests for the population in the surroundings of the former nuclear weapons test site near Semipalatinsk in Kazakhstan, a pilot study was performed by an international cooperation between Kazakh, French, Czech and German institutions at two villages, Mostik and Maisk. Together with Kazakh scientists, eight experts from Europe carried out a field mission in September 1995 to assess, within the framework of a NATO supported project, the radiological situation as far as external doses, environmental contamination and body burden of man were concerned. A summary of the results obtained is presented. The actual radiological situation near the test site is characterized by fallout contaminations. Cs was found in upper soil layers in concentrations similar to those of the global fallout. Also Sr, Am and Co were observed. The resulting present dose to the population is low. Mean external doses from soil contamination for Maisk and Mostik (0.60-0.63 mSv/year) presently correspond to mean external doses in normal environments. Mean values of the annual internal doses observed in these two villages are below 2 microSv/year for 90Sr. For other radionuclides the internal doses are also negligible.

Homeland Security Research Improves the Nation's Ability to ...

EPA Pesticide Factsheets

Technical Brief Homeland Security (HS) Research develops data, tools, and technologies to minimize the impact of accidents, natural disasters, terrorist attacks, and other incidents that can result in toxic chemical, biological or radiological (CBR) contamination. HS Research develops ways to detect contamination, sampling strategies, sampling and analytical methods, cleanup methods, waste management approaches, exposure assessment methods, and decision support tools (including water system models). These contributions improve EPA’s response to a broad range of environmental disasters.

Mobile laboratories: An innovative and efficient solution for radiological characterization of sites under or after decommissioning.

PubMed

Goudeau, V; Daniel, B; Dubot, D

2017-04-21

During the operation and the decommissioning of a nuclear site the operator must assure the protection of the workers and the environment. It must furthermore identify and classify the various wastes, while optimizing the associated costs. At all stages of the decommissioning radiological measurements are performed to determine the initial situation, to monitor the demolition and clean-up, and to verify the final situation. Radiochemical analysis is crucial for the radiological evaluation process to optimize the clean-up operations and to the respect limits defined with the authorities. Even though these types of analysis are omnipresent in activities such as the exploitation, the monitoring, and the cleaning up of nuclear plants, some nuclear sites do not have their own radiochemical analysis laboratory. Mobile facilities can overcome this lack when nuclear facilities are dismantled, when contaminated sites are cleaned-up, or in a post-accident situation. The current operations for the characterization of radiological soils of CEA nuclear facilities, lead to a large increase of radiochemical analysis. To manage this high throughput of samples in a timely manner, the CEA has developed a new mobile laboratory for the clean-up of its soils, called SMaRT (Shelter for Monitoring and nucleAR chemisTry). This laboratory is dedicated to the preparation and the radiochemical analysis (alpha, beta, and gamma) of potentially contaminated samples. In this framework, CEA and Eichrom laboratories has signed a partnership agreement to extend the analytical capacities and bring on site optimized and validated methods for different problematic. Gamma-emitting radionuclides can usually be measured in situ as little or no sample preparation is required. Alpha and beta-emitting radionuclides are a different matter. Analytical chemistry laboratory facilities are required. Mobile and transportable laboratories equipped with the necessary tools can provide all that is needed. The main advantage of a mobile laboratory is its portability; the shelter can be placed in the vicinity of nuclear facilities under decommissioning, or of contaminated sites with infrastructures unsuitable for the reception and treatment of radioactive samples. Radiological analysis can then be performed without the disadvantages of radioactive material transport. This paper describes how this solution allows a fast response and control of costs, with a high analytical capacity. Copyright © 2017 Elsevier Ltd. All rights reserved.

Plutonium mining for cleanup.

PubMed

Bramlitt, E T

1988-08-01

Cleanup is the act of making a contaminated site relatively free of Pu so it may be used without radiological safety restrictions. Contaminated ground is the focus of major cleanups. Cleanup traditionally involves determining Pu content of soil, digging up soil in which radioactivity exceeds guidelines, and relocating excised soil to a waste-disposal site. Alternative technologies have been tested at Johnston Atoll (JA), where there is as much as 100,000 m3 of Pu-contaminated soil. A mining pilot plant operated for the first 6 mo of 1986 and made 98% of soil tested "clean", from more than 40 kBq kg-1 (1000 pCi g-1) to less than about 500 Bq kg-1 (15 pCi g-1) by concentrating Pu in 2% of the soil. The pilot plant is now installed at the U.S. Department of Energy Nevada Test Site for evaluating cleanup of other contaminated soils and refining cleanup effectiveness. A full-scale cleanup plant has been programmed for JA in 1988. In this paper, previous cleanups are reviewed, and the mining endeavor at JA is detailed. "True soil cleanup" is contrasted with the classical "soil relocation cleanup." The mining technology used for Pu cleanup has been in use for more than a century. Mining for cleanup, however, is unique. It is envisioned as being prominent for radiological and other cleanups in the future.

Health Risks to Ecological Workers on Contaminated Sites - the Department of Energy as a Case Study

PubMed Central

Burger, Joanna; Gochfeld, Michael

2016-01-01

Background At most contaminated sites the risk to workers focuses on those ‘hazardous waste workers’ directly exposed to chemicals or radionuclides, and to the elaborate approaches implemented to protecting their health and safety. Ecological workers generally are not considered. Objectives To explore the risks to the health and safety of ecological workers on sites with potential chemical and radiological exposures before, during or after remediation of contamination. To use the U.S. Department of Energy as a case study, and to develop concepts that apply generally to sites contaminated with hazardous or nuclear wastes, Methods Develop categories of ecological workers, describe their usual jobs, and provide information on the kinds of risks they face. Ecological activities include continued surveillance and monitoring work on any sites with residual contamination, subject to institutional controls and engineered barriers following closure as well as the restoration. Results The categories of ecological workers and their tasks include 1) Ecological characterization, mapping and monitoring, 2) biodiversity studies, 2) Contaminant fate and transport, 3) On-going industrial activities 4) Remediation activities (environmental management), 5) Environmental restoration, 6) Post-cleanup surveillance and monitoring, and 7) Post-closure future site activities. There are a set of functional activities that can occur with different frequencies and intensities, including visual inspection, collecting biological samples, collecting media physical samples, collecting biological debris, restoration planting, and maintaining ecosystems. Conclusions Ecological workers face different exposures and risks than other environmental cleanup workers. Many of their tasks mimic shift work with long hours leading to fatigue, and they are exposed to biological as well as chemical/radiological hazards. DOE and other entities need to examine the risks to ecological workers on site with an eye to risk reduction. PMID:27668128

Sample Collection Information Document for Chemical & Radiochemical Analytes – Companion to Selected Analytical Methods for Environmental Remediation and Recovery (SAM) 2012

EPA Pesticide Factsheets

Sample Collection Information Document is intended to provide sampling information to be used during site assessment, remediation and clearance activities following a chemical or radiological contamination incident.

Ground Penetrating Radar as a Contextual Sensor for Multi-Sensor Radiological Characterisation

PubMed Central

Ukaegbu, Ikechukwu K.; Gamage, Kelum A. A.

2017-01-01

Radioactive sources exist in environments or contexts that influence how they are detected and localised. For instance, the context of a moving source is different from a stationary source because of the effects of motion. The need to incorporate this contextual information in the radiation detection and localisation process has necessitated the integration of radiological and contextual sensors. The benefits of the successful integration of both types of sensors is well known and widely reported in fields such as medical imaging. However, the integration of both types of sensors has also led to innovative solutions to challenges in characterising radioactive sources in non-medical applications. This paper presents a review of such recent applications. It also identifies that these applications mostly use visual sensors as contextual sensors for characterising radiation sources. However, visual sensors cannot retrieve contextual information about radioactive wastes located in opaque environments encountered at nuclear sites, e.g., underground contamination. Consequently, this paper also examines ground-penetrating radar (GPR) as a contextual sensor for characterising this category of wastes and proposes several ways of integrating data from GPR and radiological sensors. Finally, it demonstrates combined GPR and radiation imaging for three-dimensional localisation of contamination in underground pipes using radiation transport and GPR simulations. PMID:28387706

Chernobyl and Goiânia lessons for responding to radiological terrorism.

PubMed

Steinhausler, Friedrich

2005-11-01

The deployment of a radiological dispersal device (RDD) is likely to result in relatively low radiation exposure of the targeted population, insufficient to cause a severe radiation detriment. Nevertheless, due to atmospheric dispersion of the radioactive material, an urban area equaling several city blocks could be affected. The current knowledge base concerning the response to radiological terrorism, focusing mainly on environmental cleanup and site recovery (CSR) of areas with radioactive contamination due to the deployment of an RDD, is largely derived from military scientific tests or exercises assembled over the past 50 y with only limited applicability to the consequences of an RDD detonating in a city. This paper focuses on the extensive experience in CSR gained in the management of the radiological accident contaminating the Brazilian city of Goiânia in 1987, and managing the aftermath of the Chernobyl reactor accident in 1986. The incident in Goiânia demonstrated the numerous practical difficulties of implementing a sound CSR, based on a balanced judgment of all relevant factors, such as radiation safety, environmental issues, economic consequences, and public fear. A review of the different stages of the intervention policy in the former Soviet Union reveals that risk-benefit cost analysis was not used for the decision-making process during the later stages of the post-accident situation. Instead, a CSR policy was adopted that resulted in continuously escalating costs. The results of this analysis are used to develop an Integrated Cleanup and Site Restoration Concept and recommend practically applicable solutions from Lessons Learned.

AMS Ground Truth Measurements: Calibrations and Test Lines

DOE Office of Scientific and Technical Information (OSTI.GOV)

Wasiolek, Piotr T.

2015-12-01

Airborne gamma spectrometry is one of the primary techniques used to define the extent of ground contamination after a radiological incident. Its usefulness was demonstrated extensively during the response to the Fukushima NPP accident in March-May 2011. To map ground contamination, a set of scintillation detectors is mounted on an airborne platform (airplane or helicopter) and flown over contaminated areas. The acquisition system collects spectral information together with the aircraft position and altitude every second. To provide useful information to decision makers, the count data, expressed in counts per second (cps), need to be converted to a terrestrial component ofmore » the exposure rate at 1 meter (m) above ground, or surface activity of the isotopes of concern. This is done using conversion coefficients derived from calibration flights. During a large-scale radiological event, multiple flights may be necessary and may require use of assets from different agencies. However, because production of a single, consistent map product depicting the ground contamination is the primary goal, it is critical to establish a common calibration line very early into the event. Such a line should be flown periodically in order to normalize data collected from different aerial acquisition systems and that are potentially flown at different flight altitudes and speeds. In order to verify and validate individual aerial systems, the calibration line needs to be characterized in terms of ground truth measurements This is especially important if the contamination is due to short-lived radionuclides. The process of establishing such a line, as well as necessary ground truth measurements, is described in this document.« less

AMS Ground Truth Measurements: Calibration and Test Lines

DOE Office of Scientific and Technical Information (OSTI.GOV)

Wasiolek, P.

2013-11-01

Airborne gamma spectrometry is one of the primary techniques used to define the extent of ground contamination after a radiological incident. Its usefulness was demonstrated extensively during the response to the Fukushima nuclear power plant (NPP) accident in March-May 2011. To map ground contamination a set of scintillation detectors is mounted on an airborne platform (airplane or helicopter) and flown over contaminated areas. The acquisition system collects spectral information together with the aircraft position and altitude every second. To provide useful information to decision makers, the count rate data expressed in counts per second (cps) needs to be converted tomore » the terrestrial component of the exposure rate 1 m above ground, or surface activity of isotopes of concern. This is done using conversion coefficients derived from calibration flights. During a large scale radiological event, multiple flights may be necessary and may require use of assets from different agencies. However, as the production of a single, consistent map product depicting the ground contamination is the primary goal, it is critical to establish very early into the event a common calibration line. Such a line should be flown periodically in order to normalize data collected from different aerial acquisition systems and potentially flown at different flight altitudes and speeds. In order to verify and validate individual aerial systems, the calibration line needs to be characterized in terms of ground truth measurements. This is especially important if the contamination is due to short-lived radionuclides. The process of establishing such a line, as well as necessary ground truth measurements, is described in this document.« less

Environmental risks of radioactive discharges from a low-level radioactive waste disposal site at Dessel, Belgium.

PubMed

Batlle, J Vives I; Sweeck, L; Wannijn, J; Vandenhove, H

2016-10-01

The potential radiological impact of releases from a low-level radioactive waste (Category A waste) repository in Dessel, Belgium on the local fauna and flora was assessed under a reference scenario for gradual leaching. The potential impact situations for terrestrial and aquatic fauna and flora considered in this study were soil contamination due to irrigation with contaminated groundwater from a well at 70 m from the repository, contamination of the local wetlands receiving the highest radionuclide flux after migration through the aquifer and contamination of the local river receiving the highest radionuclide flux after migration through the aquifer. In addition, an exploratory study was carried out for biota residing in the groundwater. All impact assessments were performed using the Environmental Risk from Ionising Contaminants: Assessment and Management (ERICA) tool. For all scenarios considered, absorbed dose rates to biota were found to be well below the ERICA 10 μGy h -1 screening value. The highest dose rates were observed for the scenario where soil was irrigated with groundwater from the vicinity of the repository. For biota residing in the groundwater well, a few dose rates were slightly above the screening level but significantly below the dose rates at which the smallest effects are observed for those relevant species or groups of species. Given the conservative nature of the assessment, it can be concluded that manmade radionuclides deposited into the environment by the near surface disposal of category A waste at Dessel do not have a significant radiological impact to wildlife. Copyright © 2016 Elsevier Ltd. All rights reserved.

Radiological Assessment for the Removal of Legacy BPA Power Lines that Cross the Hanford Site

DOE Office of Scientific and Technical Information (OSTI.GOV)

Millsap, William J.; Brush, Daniel J.

This paper discusses some radiological field monitoring and assessment methods used to assess the components of an old electrical power transmission line that ran across the Hanford Site between the production reactors area (100 Area) and the chemical processing area (200 Area). This task was complicated by the presence of radon daughters -- both beta and alpha emitters -- residing on the surfaces, particularly on the surfaces of weathered metals and metals that had been electrically-charged. In many cases, these activities were high compared to the DOE Surface Contamination Guidelines, which were used as guides for the assessment. These methodsmore » included the use of the Toulmin model of argument, represented using Toulmin diagrams, to represent the combined force of several strands of evidences, rather than a single measurement of activity, to demonstrate beyond a reasonable doubt that no or very little Hanford activity was present and mixed with the natural activity. A number of forms of evidence were used: the overall chance of Hanford contamination; measurements of removable activity, beta and alpha; 1-minute scaler counts of total surface activity, beta and alpha, using "background makers"; the beta activity to alpha activity ratios; measured contamination on nearby components; NaI gamma spectral measurements to compare uncontaminated and potentially-contaminated spectra, as well as measurements for the sentinel radionuclides, Am- 241 and Cs-137 on conducting wire; comparative statistical analyses; and in-situ measurements of alpha spectra on conducting wire showing that the alpha activity was natural Po-210, as well as to compare uncontaminated and potentially-contaminated spectra.« less

[Economic damage caused by lowered prices in the agro-food sector in areas contaminated by radioactive materials leaked from the nuclear power plant severely damaged by the 2011 Great East Japan Earthquake--consideration from the viewpoints of epidemiology, economics and social psychology].

PubMed

Sugita, Minoru; Miyakawa, Michiko

2013-01-01

Large amounts of radioactive materials were leaked into the environment from the Fukushima Daiichi Nuclear Power Plant (FDNPP) of the Tokyo Electric Power Company, which was severely damaged by the 2011 Tohoku Region Pacific Coast Earthquake and accompanying tsunami. Economic damage due to lowered prices and supplies of food products produced in the areas contaminated by the radioactive materials leaked from the damaged FDNPP to the agro-food sector in the affected areas is notable. In Japanese, this is known as fuhyo higai. In this study, we investigated fuhyo higai from the viewpoints of epidemiology, economics, and social psychology in an effort to seek solutions. Information was obtained from articles in print and on the Internet. Fuhyo higai, or economic damage of the agro-food sector, which is the main industry in the contaminated areas, is serious because it is difficult to reassure the general population regarding food safety. This fuhyo higai does not derive solely from rumor. It has been reported that improving the science literacy of the general population is important as a countermeasure against fuhyo higai, but this may not be effective because of the human social structure and behavior of people who seek subjective safety. Almost all radiological laboratory results of samples of food produced in the contaminated areas were below detectable limits. Very high values were rarely detected. In general, information about the dose-response relationship is obtained under the assumption that there may be error in the response but not in the dose. The rare cases of extremely high radiological values of food samples from the contaminated areas may correspond to large errors in dose. However, it is difficult to deny a high-dose risk. The reported information on the dose-response relationship obtained under the assumption that there is no error in dose is not sufficient. Thus, response, i.e., health risk, cannot be correctly estimated. This leads the general population to choose food products from areas far from the FDNPP over those from the contaminated areas. In order to resolve this problem, thorough decontamination of radioactive areas, including large forests, is necessary for the market to regain competitiveness to the level it was before the accident. The cost of such decontamination is enormous and requires much labor. Decontamination will create employment and is indispensable in restoring the deteriorated economic conditions of the affected areas.

An assessment on the environmental contamination caused by the Fukushima accident.

PubMed

Song, Jin Ho

2018-01-15

The radiological releases from the damaged fuel to the atmosphere and into the cooling water in the Fukushima Daiich Nuclear Power Plant (FDNPP) accident are investigated. Atmospheric releases to the land and ocean mostly occurred during the first week after the accident whereas continuous release from the damaged fuel into the cooling water resulted in an accumulation of contaminated water in the plant during last six years. An evaluation of measurement data and analytical model for the release of radionuclides indicated that atmospheric releases were mainly governed by the volatility of the radionuclides. Using the measurement data on the contaminated water, the mechanism for the release of long-lived radionuclides into the cooling water was analyzed. It was found that the radioactivity concentrations of 90 Sr in the contaminated water in the Primary Containment Vessel (PCV) of unit 2 and unit 3 were consistently higher than that of 137 Cs and the radioactivity concentration of 90 Sr in the turbine building of unit 1 in year 2015 was higher than that in year 2011. It was also observed that the radioactivity concentration of long-lived radionuclides in the contaminated water in the FDNPP is still high even in year 2015. The activity ratio of 238 Pu/ 239+240 Pu for the contaminated water was in the range of 1.7-5.4, which was significantly different from the ratios from the soil samples representing the atmospheric releases of FDNPP. It is concluded that the release mechanisms into the atmosphere and cooling water are clearly different and there has been significant amount of long-lived radionuclides released into the contaminated water. Copyright © 2017 Elsevier Ltd. All rights reserved.

40 CFR 2.304 - Special rules governing certain information obtained under the Safe Drinking Water Act.

Code of Federal Regulations, 2014 CFR

2014-07-01

...) Contaminant means any physical, chemical, biological, or radiological substance or matter in water. (3... assistance under the Act; and (ii) Which was provided by a person— (A) Who is a supplier of water, as defined...

Defending the Military Food Supply Acquisition, Preparation, and Protection of Food at U.S. Military Installations

DTIC Science & Technology

2009-09-01

former KGB official, with polonium - 210 in 2006.25 However, a number of factors make radiological contamination of food unlikely. First, it is...attempts to poison the military food supply,1,2 one cannot ignore the fact that contaminated food could rapidly and effectively reduce the combat readiness...peppers from Mexico in the summer of 2008)5 can be an effective vector for illness. The cases mentioned above are due to lapses in food safety, so what

First detection of lead in black paper from intraoral film: an environmental concern.

PubMed

Guedes, Débora F C; Silva, Reginaldo S; da Veiga, Márcia A M S; Pecora, Jesus D

2009-10-30

Lead (Pb) contamination in the black paper that recovers intraoral films (BKP) has been investigated. BKP samples were collected from the Radiology Clinics of the Dental School of Ribeirão Preto, University of São Paulo, Brazil. For sake of comparison, four different methods were used. The results revealed the presence of high lead levels, well above the maximum limit allowed by the legislation. Pb contamination levels achieved after the following treatments: paper digestion in nitric acid, microwave treatment, DIN38414-54 method and TCLP method were 997 microg g(-1), 189 microg g(-1), 20.8 microg g(-1), and 54.0 microg g(-1), respectively. Flame atomic absorption spectrometry (FAAS) and inductively coupled plasma mass spectrometry (ICP-MS) were employed for lead determination according to the protocols of the applied methods. Lead contamination in used BKP was confirmed by scanning electron microscopy coupled with energy dispersive X-ray microanalysis (SEM-EDS). All the SEM imaging was carried out in the secondary electron mode (SE) and backscattered-electron mode (QBSD) following punctual X-ray fluorescence spectra. Soil contamination derived from this product revealed the urgent need of addressing this problem. These elevated Pb levels, show that a preliminary treatment of BKP is mandatory before it is disposed into the common trash. The high lead content of this material makes its direct dumping into the environment unwise.

Nevada National Security Site Radiological Control Manual

DOE Office of Scientific and Technical Information (OSTI.GOV)

Radiological Control Managers’ Council

2012-03-26

This document supersedes DOE/NV/25946--801, 'Nevada Test Site Radiological Control Manual,' Revision 1 issued in February 2010. Brief Description of Revision: A complete revision to reflect a recent change in name for the NTS; changes in name for some tenant organizations; and to update references to current DOE policies, orders, and guidance documents. Article 237.2 was deleted. Appendix 3B was updated. Article 411.2 was modified. Article 422 was re-written to reflect the wording of DOE O 458.1. Article 431.6.d was modified. The glossary was updated. This manual contains the radiological control requirements to be used for all radiological activities conducted bymore » programs under the purview of the U.S. Department of Energy (DOE) and the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection.' Programs covered by this manual are located at the Nevada National Security Site (NNSS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Livermore, California; and Andrews Air Force Base, Maryland. In addition, fieldwork by NNSA/NSO at other locations is covered by this manual. Current activities at NNSS include operating low-level radioactive and mixed waste disposal facilities for United States defense-generated waste, assembly and execution of subcritical experiments, assembly/disassembly of special experiments, the storage and use of special nuclear materials, performing criticality experiments, emergency responder training, surface cleanup and site characterization of contaminated land areas, environmental activity by the University system, and nonnuclear test operations, such as controlled spills of hazardous materials at the Hazardous Materials Spill Center. Currently, the major potential for occupational radiation exposure is associated with the burial of low-level radioactive waste and the handling of radioactive sources. Remediation of contaminated land areas may also result in radiological exposures.« less

40 CFR 82.156 - Required practices.

Code of Federal Regulations, 2012 CFR

2012-07-01

... appliance to four inches of mercury vacuum. (i)(1) Owners or operators of commercial refrigeration equipment...) Owners or operators of federally-owned commercial refrigeration equipment may have more than 30 days to repair leaks if the refrigeration appliance is located in an area subject to radiological contamination...

40 CFR 82.156 - Required practices.

Code of Federal Regulations, 2013 CFR

2013-07-01

... appliance to four inches of mercury vacuum. (i)(1) Owners or operators of commercial refrigeration equipment...) Owners or operators of federally-owned commercial refrigeration equipment may have more than 30 days to repair leaks if the refrigeration appliance is located in an area subject to radiological contamination...

40 CFR 82.156 - Required practices.

Code of Federal Regulations, 2011 CFR

2011-07-01

... appliance to four inches of mercury vacuum. (i)(1) Owners or operators of commercial refrigeration equipment...) Owners or operators of federally-owned commercial refrigeration equipment may have more than 30 days to repair leaks if the refrigeration appliance is located in an area subject to radiological contamination...

40 CFR 82.156 - Required practices.

Code of Federal Regulations, 2014 CFR

2014-07-01

... appliance to four inches of mercury vacuum. (i)(1) Owners or operators of commercial refrigeration equipment...) Owners or operators of federally-owned commercial refrigeration equipment may have more than 30 days to repair leaks if the refrigeration appliance is located in an area subject to radiological contamination...

500 E Illinois St, June 2013, Lindsay Light Radiological Survey

EPA Pesticide Factsheets

In the immediatevicinity of the area of the potential contamination the surface gamma readings were 8,400 to 9,500 cpm.The unshielded Ludlum threshold value equivalent to the USEPA cleanup value of 7.1 pCi/g total radiumwas 17,920 cpm.

SNIFFER: An aerial platform for the plume phase of a nuclear emergency

NASA Astrophysics Data System (ADS)

Castelluccio, D. M.; Cisbani, E.; Frullani, S.

2012-04-01

When a nuclear or radiological accident results in a release of a radioactive plume, AGS (Aerial Gamma Spectrometry) systems used in many countries, equipped with passive detectors, can help in giving quantitative assessment on the radiological situation (land surface contamination level) only when the air contamination due to the passage of the travelling plume has become negligible. To overcome this limitation, the Italian Institute of Health has developed and implemented a multi purpose air sampling system based on a fixed wing aircraft, for time-effective, large areas radiological surveillance (to face radiological emergency and to support homeland security). A fixed wing aircraft (Sky Arrow 650) with the front part of the fuselage properly adapted to house the detection equipment has been equipped with a compact air sampling line where the isokinetic sampling is dynamically maintained. Aerosol is collected on a Teflon® filter positioned along the line and hosted on a rotating 4-filters disk. A complex of detectors allows radionuclide identification in the collected aerosol samples. A correlated analysis of these two detectors data allows a quantitative measurement of air as well as ground surface concentration of gamma emitting radioisotopes. Environmental sensors and a GPS receiver support the characterization of the sampling conditions and the temporal and geolocation of the acquired data. Acquisition and control system based on compact electronics and real time software that operate the sampling line actuators, guarantee the dynamical isokinetic condition, and acquire the detectors and sensor data. The system is also equipped with other sampling lines to provide information on the concentration of other chemical pollutants. Operative flights have been carried out in the last years, and performances and results are presented.

NV/YMP radiological control manual, Revision 2

DOE Office of Scientific and Technical Information (OSTI.GOV)

Gile, A.L.

The Nevada Test Site (NTS) and the adjacent Yucca Mountain Project (YMP) are located in Nye County, Nevada. The NTS has been the primary location for testing nuclear explosives in the continental US since 1951. Current activities include operating low-level radioactive and mixed waste disposal facilities for US defense-generated waste, assembly/disassembly of special experiments, surface cleanup and site characterization of contaminated land areas, and non-nuclear test operations such as controlled spills of hazardous materials at the hazardous Materials (HAZMAT) Spill Center (HSC). Currently, the major potential for occupational radiation exposure is associated with the burial of low-level nuclear waste andmore » the handling of radioactive sources. Planned future remediation of contaminated land areas may also result in radiological exposures. The NV/YMP Radiological Control Manual, Revision 2, represents DOE-accepted guidelines and best practices for implementing Nevada Test Site and Yucca Mountain Project Radiation Protection Programs in accordance with the requirements of Title 10 Code of Federal Regulations Part 835, Occupational Radiation Protection. These programs provide protection for approximately 3,000 employees and visitors annually and include coverage for the on-site activities for both personnel and the environment. The personnel protection effort includes a DOE Laboratory Accreditation Program accredited dosimetry and personnel bioassay programs including in-vivo counting, routine workplace air sampling, personnel monitoring, and programmatic and job-specific As Low as Reasonably Achievable considerations.« less

Monitored Natural Attenuation as a Remediation Strategy for Nuclear Power Plant Applications

NASA Astrophysics Data System (ADS)

Kim, K.; Bushart, S.

2009-12-01

A NRC Information Notice (IN 2006-13) was produced to inform holders of nuclear operating licenses “of the occurrence of radioactive contamination of ground water at multiple facilities due to undetected leakage from facility structures, systems, or components (SSCs) that contain or transport radioactive fluids” so that they could consider actions, as appropriate, to avoid similar problems. To reinforce their commitment to environmental stewardship the nuclear energy industry has committed to improving management of situations that have the potential to lead to the inadvertent release of radioactive fluids. This Industry Groundwater Protection Initiative, finalized in June 2007 as [NEI 07-07], calls for implementation and improvement of on-site groundwater monitoring programs and enhanced communications with stakeholders and regulators about situations related to inadvertent releases. EPRI developed its Groundwater Protection Program to provide the nuclear energy industry with the technical support needed to implement the Industry Groundwater Initiative. An objective of the EPRI Groundwater Protection Program is to provide the nuclear industry with technically sound guidance for implementing and enhancing on-site groundwater monitoring programs. EPRI, in collaboration with the EPRI Groundwater Protection Committee of utility members, developed the EPRI Groundwater Protection Guidelines for Nuclear Power Plants (EPRI Report 1015118, November 2007), which provides site-specific guidance for implementing a technically sound groundwater monitoring program. The guidance applies a graded approach for nuclear plants to tailor a technically effective and cost efficient groundwater monitoring program to the site’s hydrogeology and risk for groundwater contamination. As part of the Groundwater Protection Program, EPRI is also investigating innovative remediation technologies for addressing low-level radioactive contamination in soils and groundwater at nuclear power plant sites. One of these remediation technologies is monitored natural attenuation (MNA), which has been widely used in other industries for the remediation of contaminants in soil and groundwater. Monitored natural attenuation (MNA) is a non-intervention, but not a no-action, groundwater and soil remediation approach that involves monitoring the dilution, dispersion, and decay of contaminants to meet remediation objectives. MNA has been commonly applied at sites where soil and groundwater have been contaminated by volatile organic compounds. This method has also been applied to remediation of radiological contamination at U.S. DOE facilities and decommissioning nuclear power plant sites. The EPRI published report (1016764) provides guidance for implementing MNA at nuclear power plants for remediation of radiological contaminants in groundwater and soil. The goal of the EPRI Groundwater Protection program is to bring together experience and technologies - both from within the nuclear industry and other industries - to support the industry’s commitment to environmental stewardship. Results from the program are being published in an extensive series of reports and software, and are being communicated to members in an annual EPRI Groundwater Protection technical exchange workshop.

Radionuclide decorporation: matching the biokinetics of actinides by transdermal delivery of pro-chelators.

PubMed

Zhang, Yong; Sadgrove, Matthew P; Mumper, Russell J; Jay, Michael

2013-10-01

The threat of nuclear terrorism by the deliberate detonation of a nuclear weapon or radiological dispersion device ("dirty bomb") has made emergency response planning a priority. The only FDA-approved treatments for contamination with isotopes of the transuranic elements Am, Pu, and Cm are the Ca and Zn salts of diethylenetriaminepentaacetic acid (DTPA). These injectable products are not well suited for use in a mass contamination scenario as they require skilled professionals for their administration and are rapidly cleared from the circulation. To overcome the mismatch in the pharmacokinetics of the DTPA and the biokinetics of these transuranic elements, which are slowly released from contamination sites, the penta-ethyl ester of DTPA (C2E5) was prepared and formulated in a nonaqueous gel for transdermal administration. When gels comprised of 40% C2E5, 40-45% Miglyol® 840, and 15-20% ethyl cellulose were spiked with [(14)C]-C2E5 and applied to rat skin; over 60% of the applied dose was absorbed within a 24-h period. Radioactivity was observed in urinary and fecal excretions for over 3 days after removal of the gel. Using an (241)Am wound contamination model, transdermal C2E5 gels were able to enhance total body elimination and reduce the liver and skeletal burden of (241)Am in a dose-dependent manner. The efficacy achieved by a single 1,000 mg/kg dose to contaminated rats was statistically comparable to intravenous Ca-DTPA at 14 mg/kg. The effectiveness of this treatment, favorable sustained release profile of pro-chelators, and ease of administration support its use following radiological emergencies and for its inclusion in the Strategic National Stockpile.

A United States perspective on long-term management of areas contaminated with radioactive materials.

PubMed

Jones, C Rick

2004-01-01

The US has far-reaching and extensive experience in the long-term management of areas contaminated with radioactive materials. This experience base includes the Department of Energy's continued follow-up with Hiroshima and Nagasaki from the 1940s at the Radiological Effects Research Foundation in Hiroshima, Japan, the long-term management of the Marshall Islands Programme, the clean-up of the US nuclear weapons complex and the ongoing management of accident sites such as in Palomares, Spain. This paper discusses the lessons learnt and best practices gained from this far-reaching and extensive experience in the long-term management of areas contaminated with radioactive materials. Copyright 2004 Oxford University Press

Closure Report for Corrective Action Unit 539: Areas 25 and 26 Railroad Tracks Nevada National Security Site, Nevada with ROTC-1, Revision 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Mark Kauss

2011-06-01

This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 539: Areas 25 and 26 Railroad Tracks, Nevada National Security Site, Nevada. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. The corrective action sites (CASs) within CAU 539 are located within Areas 25 and 26 of the Nevada National Security Site. Corrective Action Unit 539 comprises the following CASs: • 25-99-21, Area 25 Railroad Tracksmore » • 26-99-05, Area 26 Railroad Tracks The purpose of this CR is to provide documentation supporting the completed corrective actions and provide data confirming that the closure objectives for CASs within CAU 539 were met. To achieve this, the following actions were performed: • Reviewed documentation on historical and current site conditions, including the concentration and extent of contamination. • Conducted radiological walkover surveys of railroad tracks in both Areas 25 and 26. • Collected ballast and soil samples and calculated internal dose estimates for radiological releases. • Collected in situ thermoluminescent dosimeter measurements and calculated external dose estimates for radiological releases. • Removed lead bricks as potential source material (PSM) and collected verification samples. • Implemented corrective actions as necessary to protect human health and the environment. • Properly disposed of corrective action and investigation wastes. • Implemented an FFACO use restriction (UR) for radiological contamination at CAS 25-99-21. The approved UR form and map are provided in Appendix F and will be filed in the DOE, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Facility Information Management System; the FFACO database; and the NNSA/NSO CAU/CAS files. From November 29, 2010, through May 2, 2011, closure activities were performed as set forth in the Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 539: Areas 25 and 26 Railroad Tracks, Nevada Test Site, Nevada. The purposes of the activities as defined during the data quality objectives process were as follows: • Determine whether contaminants of concern (COCs) are present. • If COCs are present, determine their nature and extent, implement appropriate corrective actions, and properly dispose of wastes. Analytes detected during the closure activities were evaluated against final action levels (FALs) to determine COCs for CAU 539. Assessment of the data generated from closure activities revealed the following: • At CAS 26-99-05, the total effective dose for radiological releases did not exceed the FAL of 25 millirem per Industrial Area year. Potential source material in the form of lead bricks was found at three locations. A corrective action of clean closure was implemented at these locations, and verification samples indicated that no further action is necessary. • At CAS 25-99-21, the total effective dose for radiological releases exceeds the FAL of 25 millirem per Industrial Area year. Potential source material in the form of lead bricks was found at eight locations. A corrective action was implemented by removing the lead bricks and soil above FALs at these locations, and verification samples indicated that no further action is necessary. Pieces of debris with high radioactivity were identified as PSM and remain within the CAS boundary. A corrective action of closure in place with a UR was implemented at this CAS because closure activities showed evidence of remaining soil contamination and radioactive PSM. Future land use will be restricted from surface and intrusive activities. Closure activities generated waste streams consisting of industrial solid waste, recyclable materials, low-level radioactive waste, and mixed low-level radioactive waste. Wastes were disposed of in the appropriate onsite landfills. The NNSA/NSO provides the following recommendations: • Clean closure is required at CAS 26-99-05. • Closure in place is required at CAS 25-99-21. • A UR is required at CAS 25-99-21. • A Notice of Completion to the NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 539. • Corrective Action Unit 539 should be moved from Appendix III to Appendix IV of the FFACO.« less

What causes increasing and unnecessary use of radiological investigations? a survey of radiologists' perceptions

PubMed Central

Lysdahl, Kristin B; Hofmann, Bjørn M

2009-01-01

Background Growth in use and overuse of diagnostic imaging significantly impacts the quality and costs of health care services. What are the modifiable factors for increasing and unnecessary use of radiological services? Various factors have been indentified, but little is known about their relative impact. Radiologists hold key positions for providing such knowledge. Therefore the purpose of this study was to obtain radiologists' perspective on the causes of increasing and unnecessary use of radiological investigations. Methods In a mailed questionnaire radiologist members of the Norwegian Medical Association were asked to rate potential causes of increased investigation volume (fifteen items) and unnecessary investigations (six items), using five-point-scales. Responses were analysed by using summary statistics and Factor Analysis. Associations between variables were determined using Students' t-test, Spearman rank correlation and Chi-Square tests. Results The response rate was 70% (374/537). The highest rated causes of increasing use of radiological investigations were: a) new radiological technology, b) peoples' demands, c) clinicians' intolerance for uncertainty, d) expanded clinical indications, and e) availability. 'Over-investigation' and 'insufficient referral information' were reported the most frequent causes of unnecessary investigations. Correlations between causes of increasing and unnecessary radiology use were identified. Conclusion In order to manage the growth in radiological imaging and curtail inappropriate investigations, the study findings point to measures that influence the supply and demand of services, specifically to support the decision-making process of physicians. PMID:19723302

The impact of communication materials on public responses to a radiological dispersal device (RDD) attack.

PubMed

Rogers, M Brooke; Amlôt, Richard; Rubin, G James

2013-03-01

It is a common assumption that, in the event of a chemical, biological, radiological, or nuclear (CBRN) attack, a well-prepared and informed public is more likely to follow official recommendations regarding the appropriate safety measures to take. We present findings from a UK study investigating the ability of crisis communication to influence perceptions of risk and behavioral intentions in the general public in response to CBRN terrorism. We conducted a focus group study involving a scenario presented in mock news broadcasts to explore levels of public knowledge, information needs, and intended behavioral reactions to an attack involving an overt radiological dispersal device (RDD), or dirty bomb. We used the findings from these focus groups to design messages for the public that could be presented in a short leaflet. We then tested the effects of the leaflet on reactions to the same scenario in 8 further focus groups. The impact of the new messages on levels of knowledge, information needs, and intended compliance with official recommendations was assessed. The provision of information increased the perceived credibility of official messages and increased reported levels of intended compliance with advice to return to normal/stop sheltering, attend a facility for assessment and treatment, and return to a previously contaminated area after decontamination of the environment has taken place. Should a real attack with an RDD occur, having pretested messages available to address common concerns and information needs should facilitate the public health response to the attack.

10 CFR 835.603 - Radiological areas and radioactive material areas.

Code of Federal Regulations, 2010 CFR

2010-01-01

... Danger, Very High Radiation Area” shall be posted at each very high radiation area. (d) Airborne radioactivity area. The words “Caution, Airborne Radioactivity Area” or “Danger, Airborne Radioactivity Area” shall be posted at each airborne radioactivity area. (e) Contamination area. The words “Caution...

Return to normality after a radiological emergency.

PubMed

Lochard, J; Prêtre, S

1995-01-01

Some preliminary considerations from the management of post-accident situations connected to large scale and high land contamination are presented. The return to normal, or at least acceptable living conditions, as soon as reasonably achievable, and the prevention of the possible emergence of a post-accident crisis is of key importance. A scheme is proposed for understanding the dynamics of the various phases after an accident. An attempt is made to characterize some of the parameters driving the acceptability of post-accident situations. Strategies to return to normal living conditions in contaminated areas are considered.

Scenario of a dirty bomb in an urban environment and acute management of radiation poisoning and injuries.

PubMed

Chin, F K C

2007-10-01

In the new security environment, there is a clear and present danger of terrorists using non-conventional weapons to inflict maximum psychological and economic damage on their targets. This article examines two scenarios of radiation contamination and injury, one accidental in nature leading to environmental contamination, and another of deliberate intent resulting in injury and death. This article also discusses the management of injury from radiological dispersion devices or dirty bombs, with emphasis on the immediate aftermath as well as strategy recommendations.

DOE Office of Scientific and Technical Information (OSTI.GOV)

ALTIC, NICK A

In March 2011, the USNS Bridge was deployed off northeastern Honshu, Japan with the carrier USS Ronald Reagan to assist with relief efforts after the 2011 Tōhoku earthquake and tsunami. During that time, the Bridge was exposed to air-borne radioactive materials leaking from the damaged Fukushima I Nuclear Power Plant. The proximity of the Bridge to the air-borne impacted area resulted in the contamination of the ship’s air-handling systems and the associated components, as well as potential contamination of other ship surfaces due to either direct intake/deposition or inadvertent spread from crew/operational activities. Preliminary surveys in the weeks after themore » event confirmed low-level contamination within the heating, ventilation, and air conditioning (HVAC) ductwork and systems, and engine and other auxiliary air intake systems. Some partial decontamination was performed at that time. In response to the airborne contamination event, Military Sealift Fleet Support Command (MSFSC) contracted Oak Ridge Associated Universities (ORAU), under provisions of the Oak Ridge Institute for Science and Education (ORISE) contract, to assess the radiological condition of the Bridge. Phase I identified contamination within the CPS filters, ventilation systems, miscellaneous equipment, and other suspect locations that could not accessed at that time (ORAU 2011b). Because the Bridge was underway during the characterization, all the potentially impacted systems/spaces could not be investigated. As a result, MSFSC contracted with ORAU to perform Phase II of the characterization, specifically to survey systems/spaces previously inaccessible. During Phase II of the characterization, the ship was in port to perform routine maintenance operations, allowing access to the previously inaccessible systems/spaces.« less

Compared in vivo efficiency of nanoemulsions unloaded and loaded with calixarene and soapy water in the treatment of superficial wounds contaminated by uranium.

PubMed

Grivès, Sophie; Phan, Guillaume; Bouvier-Capely, Céline; Suhard, David; Rebière, François; Agarande, Michelle; Fattal, Elias

2017-04-01

No emergency decontamination treatment is currently available in the case of radiological skin contamination by uranium compounds. First responders in the workplace or during an industrial nuclear accident must be able to treat internal contamination through skin. For this purpose, a calixarene nanoemulsion was developed for the treatment of intact skin or superficial wounds contaminated by uranium, and the decontamination efficiency of this nanoemulsion was investigated in vitro and ex vivo. The present work addresses the in vivo decontamination efficiency of this nanoemulsion, using a rat model. This efficiency is compared to the radio-decontaminant soapy water currently used in France (Trait rouge ® ) in the workplace. The results showed that both calixarene-loaded nanoemulsion and non-loaded nanoemulsion allowed a significant decontamination efficiency compared to the treatment with soapy water. Early application of the nanoemulsions on contaminated excoriated rat skin allowed decreasing the uranium content by around 85% in femurs, 95% in kidneys and 93% in urines. For skin wounded by microneedles, mimicking wounds by microstings, nanoemulsions allowed approximately a 94% decrease in the uranium retention in kidneys. However, specific chelation of uranium by calixarene molecules within the nanoemulsion was not statistically significant, probably because of the limited calixarene-to-uranium molar ratio in these experiment conditions. Moreover, these studies showed that the soapy water treatment potentiates the transcutaneous passage of uranium, thus making it bioavailable, in particular when the skin is superficially wounded. Copyright © 2016 Elsevier Ireland Ltd. All rights reserved.

Transfer factor of (90)Sr and (137)Cs to lettuce and winter wheat at different growth stage applications.

PubMed

Al Attar, Lina; Al-Oudat, Mohammad; Safia, Bassam; Ghani, Basem Abdul

2015-12-01

The effect of clay soil contamination time on the transfer factors (Fvs) of (137)Cs and (90)Sr was investigated in four different growth stages of winter wheat and lettuce crops. The experiment was performed in an open field using lysimeters. The Fvs were the ratio of the activity concentrations of the radionuclides in crops to those in soil, both as dry weight (Bq kg(-1)). Significant difference of log-Fvs was evaluated using one-way Analysis of Variance (ANOVA). Basically, Fvs of (90)Sr were higher than those of (137)Cs, despite of the application stage or crop' variety. Higher Fvs for both radionuclides were observed for lettuce in comparison to winter wheat. Fvs of (90)Sr showed comparable trends for both crops with enhanced Fvs obtained when contamination occurred in early stages, i.e. 1.20 for lettuce and 0.88 and 0.02 for winter wheat, straw and grains, respectively. Despite the fluctuation noted in the pattern of Fvs for (137)Cs, soil contaminated at the second stage gave the highest Fvs for lettuce and grains, with geometric means of 0.21 and 0.01, respectively. However, wheat-straw showed remarkable increase in Fv for the latest contamination (ripening stage), about 0.06. It could be concluded that soil contamination at early growth stages would represent high radiological risk for the scenarios studied with an exception to (137)Cs in winter wheat-straw which reflected greater hazard at the latest application. Copyright © 2015 Elsevier Ltd. All rights reserved.

Quadrant III RFI draft report: Appendix B-I, Volume 3

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1992-12-01

In order to determine the nature and extent of contamination at a RCRA site it is often necessary to investigate and characterize the chemical composition of the medium in question that represents background conditions. Background is defined as current conditions present at a site which are unaffected by past treatment, storage, or disposal of hazardous waste (OEPA, 1991). The background composition of soils at the Portsmouth Gaseous Diffusion Plant (PORTS) site was characterized for the purpose of comparing investigative soil data to a background standard for each metal on the Target Compound List/Target Analyte List and each radiological parameter ofmore » concern in this RFI. Characterization of background compositions with respect to organic parameters was not performed because the organic parameters in the TCL/TAL are not naturally occurring at the site and because the site is not located in a highly industrialized area nor downgradient from another unrelated hazardous waste site. Characterization of the background soil composition with respect to metals and radiological parameters was performed by collecting and analyzing soil boring and hand-auger samples in areas deemed unaffected by past treatment, storage, or disposal of hazardous waste. Criteria used in determining whether a soil sample location would be representative of the true background condition included: environmental history of the location, relation to Solid Waste Management Units (SWMU`s), prevailing wind direction, surface runoff direction, and ground-water flow direction.« less

Quadrant III RFI draft report: Appendix B-I, Volume 3

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1992-12-01

In order to determine the nature and extent of contamination at a RCRA site it is often necessary to investigate and characterize the chemical composition of the medium in question that represents background conditions. Background is defined as current conditions present at a site which are unaffected by past treatment, storage, or disposal of hazardous waste (OEPA, 1991). The background composition of soils at the Portsmouth Gaseous Diffusion Plant (PORTS) site was characterized for the purpose of comparing investigative soil data to a background standard for each metal on the Target Compound List/Target Analyte List and each radiological parameter ofmore » concern in this RFI. Characterization of background compositions with respect to organic parameters was not performed because the organic parameters in the TCL/TAL are not naturally occurring at the site and because the site is not located in a highly industrialized area nor downgradient from another unrelated hazardous waste site. Characterization of the background soil composition with respect to metals and radiological parameters was performed by collecting and analyzing soil boring and hand-auger samples in areas deemed unaffected by past treatment, storage, or disposal of hazardous waste. Criteria used in determining whether a soil sample location would be representative of the true background condition included: environmental history of the location, relation to Solid Waste Management Units (SWMU's), prevailing wind direction, surface runoff direction, and ground-water flow direction.« less

The visual and radiological inspection of a pipeline using a teleoperated pipe crawler

DOE Office of Scientific and Technical Information (OSTI.GOV)

Fogle, R.F.; Kuelske, K.; Kellner, R.A.

1996-07-01

In the 1950s the Savannah River Site built an open, unlined retention basin for temporary storage of potentially radionuclide-contaminated cooling water form a chemical separations process and storm water drainage from a nearby waste management facility which stored large quantities of nuclear fission by-products in carbon steel tanks. An underground process pipeline lead to the basin. Once the closure of the basin in 1972, further assessment has been required. A visual and radiological inspection of the pipeline was necessary to aid in the decision about further remediation. This article describes the inspection using a teleoperated pipe crawler. 5 figs.

Columbus Closure Project Released without Radiological Restrictions

DOE Office of Scientific and Technical Information (OSTI.GOV)

Henderson, G.

2007-07-01

The Columbus Closure Project (CCP), a historic radiological research complex, was cleaned up for future use without radiological restriction in 2006. The CCP research and development site contributed to national defense, nuclear fuel fabrication, and the development of safe nuclear reactors in the United States until 1988 when research activities were concluded for site decommissioning. In November of 2003, the Ohio Field Office of the U.S. Department of Energy contracted ECC/E2 Closure Services, LLC (Closure Services) to complete the removal of radioactive contamination from of a 1955 era nuclear sciences area consisting of a large hot cell facility, research reactormore » building and underground piping. The project known as the Columbus Closure Project (CCP) was completed in 27 months and brought to a close 16 years of D and D in Columbus, Ohio. This paper examines the project innovations and challenges presented during the Columbus Closure Project. The examination of the CCP includes the project regulatory environment, the CS safety program, accelerated clean up innovation, project execution strategies and management of project waste issues and the regulatory approach to site release 'without radiological restrictions'. (authors)« less

Naturally Occurring Radioactive Materials (NORM)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Gray, P.

1997-02-01

This paper discusses the broad problems presented by Naturally Occuring Radioactive Materials (NORM). Technologically Enhanced naturally occuring radioactive material includes any radionuclides whose physical, chemical, radiological properties or radionuclide concentration have been altered from their natural state. With regard to NORM in particular, radioactive contamination is radioactive material in an undesired location. This is a concern in a range of industries: petroleum; uranium mining; phosphorus and phosphates; fertilizers; fossil fuels; forestry products; water treatment; metal mining and processing; geothermal energy. The author discusses in more detail the problem in the petroleum industry, including the isotopes of concern, the hazards theymore » present, the contamination which they cause, ways to dispose of contaminated materials, and regulatory issues. He points out there are three key programs to reduce legal exposure and problems due to these contaminants: waste minimization; NORM assesment (surveys); NORM compliance (training).« less

The visual and radiological inspection of a pipeline using a teleoperated pipe crawler

DOE Office of Scientific and Technical Information (OSTI.GOV)

Fogle, R.F.; Kuelske, K.; Kellner, R.

1995-01-01

In the 1950s, the Savannah River Site built an open, unlined retention basin to temporarily store potentially radionuclide contaminated cooling water from a chemical separations process and storm water drainage from a nearby waste management facility that stored large quantities of nuclear fission byproducts in carbon steel tanks. The retention basin was retired from service in 1972 when a new, lined basin was completed. In 1978, the old retention basin was excavated, backfilled with uncontaminated dirt, and covered with grass. At the same time, much of the underground process pipeline leading to the basin was abandoned. Since the closure ofmore » the retention basin, new environmental regulations require that the basin undergo further assessment to determine whether additional remediation is required. A visual and radiological inspection of the pipeline was necessary to aid in the remediation decision making process for the retention basin system. A teleoperated pipe crawler inspection system was developed to survey the abandoned sections of underground pipelines leading to the retired retention basin. This paper will describe the background to this project, the scope of the investigation, the equipment requirements, and the results of the pipeline inspection.« less

Corrective Action Investigation Plan for Corrective Action Unit 428: Area 3 Septic Waste Systems 1 and 5, Tonopah Test Range, Nevada, REVISION 0, march 1999

DOE Office of Scientific and Technical Information (OSTI.GOV)

DOE /NV

1999-03-26

The Corrective Action Investigation Plan for Corrective Action Unit 428, Area 3 Septic Waste Systems 1 and 5, has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the U. S. Department of Energy, Nevada Operations Office; the State of Nevada Division of Environmental Protection; and the U. S. Department of Defense. Corrective Action Unit 428 consists of Corrective Action Sites 03- 05- 002- SW01 and 03- 05- 002- SW05, respectively known as Area 3 Septic Waste System 1 and Septic Waste System 5. This Corrective Action Investigation Plan is used inmore » combination with the Work Plan for Leachfield Corrective Action Units: Nevada Test Site and Tonopah Test Range, Nevada , Rev. 1 (DOE/ NV, 1998c). The Leachfield Work Plan was developed to streamline investigations at leachfield Corrective Action Units by incorporating management, technical, quality assurance, health and safety, public involvement, field sampling, and waste management information common to a set of Corrective Action Units with similar site histories and characteristics into a single document that can be referenced. This Corrective Action Investigation Plan provides investigative details specific to Corrective Action Unit 428. A system of leachfields and associated collection systems was used for wastewater disposal at Area 3 of the Tonopah Test Range until a consolidated sewer system was installed in 1990 to replace the discrete septic waste systems. Operations within various buildings at Area 3 generated sanitary and industrial wastewaters potentially contaminated with contaminants of potential concern and disposed of in septic tanks and leachfields. Corrective Action Unit 428 is composed of two leachfield systems in the northern portion of Area 3. Based on site history collected to support the Data Quality Objectives process, contaminants of potential concern for the site include oil/ diesel range total petroleum hydrocarbons, and Resource Conservation and Recovery Act characteristic volatile organic compounds, semivolatile organic compounds, and metals. A limited number of samples will be analyzed for gamma- emitting radionuclides and isotopic uranium from four of the septic tanks and if radiological field screening levels are exceeded. Additional samples will be analyzed for geotechnical and hydrological properties and a bioassessment may be performed. The technical approach for investigating this Corrective Action Unit consists of the following activities: (1) Perform video surveys of the discharge and outfall lines. (2) Collect samples of material in the septic tanks. (3) Conduct exploratory trenching to locate and inspect subsurface components. (4) Collect subsurface soil samples in areas of the collection system including the septic tanks and outfall end of distribution boxes. (5) Collect subsurface soil samples underlying the leachfield distribution pipes via trenching. (6) Collect surface and near- surface samples near potential locations of the Acid Sewer Outfall if Septic Waste System 5 Leachfield cannot be located. (7) Field screen samples for volatile organic compounds, total petroleum hydrocarbons, and radiological activity. (8) Drill boreholes and collect subsurface soil samples if required. (9) Analyze samples for total volatile organic compounds, total semivolatile organic compounds, total Resource Conservation and Recovery Act metals, and total petroleum hydrocarbons (oil/ diesel range organics). Limited number of samples will be analyzed for gamma- emitting radionuclides and isotopic uranium from particular septic tanks and if radiological field screening levels are exceeded. (10) Collect samples from native soils beneath the distribution system and analyze for geotechnical/ hydrologic parameters. (11) Collect and analyze bioassessment samples at the discretion of the Site Supervisor if total petroleum hydrocarbons exceed field- screening levels.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Jeremy Gwin and Douglas Frenette

This document contains process knowledge and radiological data and analysis to support approval for release of the 25-ton locomotive, Serial Number 21547, at the Area 25 Engine Maintenance, Assembly, and Disassembly (EMAD) Facility, located on the Nevada Test Site (NTS). The 25-ton locomotive is a small, one-of-a-kind locomotive used to move railcars in support of the Nuclear Engine for Rocket Vehicle Application project. This locomotive was identified as having significant historical value by the Nevada State Railroad Museum in Boulder City, Nevada, where it will be used as a display piece. A substantial effort to characterize the radiological conditions ofmore » the locomotive was undertaken by the NTS Management and Operations Contractor, National Security Technologies, LLC (NSTec). During this characterization process, seven small areas on the locomotive had contamination levels that exceeded the NTS release criteria (limits consistent with U.S. Department of Energy [DOE] Order DOE O 5400.5, “Radiation Protection of the Public and the Environment”). The decision was made to perform radiological decontamination of these known accessible impacted areas to further the release process. On February 9, 2010, NSTec personnel completed decontamination of these seven areas to within the NTS release criteria. Although all accessible areas of the locomotive had been successfully decontaminated to within NTS release criteria, it was plausible that inaccessible areas of the locomotive (i.e., those areas on the locomotive where it was not possible to perform radiological surveys) could potentially have contamination above unrestricted release limits. To access the majority of these inaccessible areas, the locomotive would have to be disassembled. A complete disassembly for a full radiological survey could have permanently destroyed parts and would have ruined the historical value of the locomotive. Complete disassembly would also add an unreasonable financial burden for the contractor. A decision was reached between the NTS regulator and NSTec, opting for alternative authorized limits from DOE Headquarters. In doing so, NSTec personnel performed a dose model using the DOE-approved modeling code RESRAD-BUILD v3.5 to evaluate scenarios. The parameters used in the dose model were conservative. NSTec’s Radiological Engineering Calculation, REC-2010-001, “Public Dose Estimate from the EMAD 25 Ton Locomotive,” concluded that the four scenarios evaluated were below the 25-millirem per year limit, the “likely” dose scenarios met the “few millirem in a year” criteria, and that the EMAD 25-ton locomotive met the radiological requirements to be released with residual radioactivity to the public.« less

Radiological protection issues arising during and after the Fukushima nuclear reactor accident.

PubMed

González, Abel J; Akashi, Makoto; Boice, John D; Chino, Masamichi; Homma, Toshimitsu; Ishigure, Nobuhito; Kai, Michiaki; Kusumi, Shizuyo; Lee, Jai-Ki; Menzel, Hans-Georg; Niwa, Ohtsura; Sakai, Kazuo; Weiss, Wolfgang; Yamashita, Shunichi; Yonekura, Yoshiharu

2013-09-01

Following the Fukushima accident, the International Commission on Radiological Protection (ICRP) convened a task group to compile lessons learned from the nuclear reactor accident at the Fukushima Daiichi nuclear power plant in Japan, with respect to the ICRP system of radiological protection. In this memorandum the members of the task group express their personal views on issues arising during and after the accident, without explicit endorsement of or approval by the ICRP. While the affected people were largely protected against radiation exposure and no one incurred a lethal dose of radiation (or a dose sufficiently large to cause radiation sickness), many radiological protection questions were raised. The following issues were identified: inferring radiation risks (and the misunderstanding of nominal risk coefficients); attributing radiation effects from low dose exposures; quantifying radiation exposure; assessing the importance of internal exposures; managing emergency crises; protecting rescuers and volunteers; responding with medical aid; justifying necessary but disruptive protective actions; transiting from an emergency to an existing situation; rehabilitating evacuated areas; restricting individual doses of members of the public; caring for infants and children; categorising public exposures due to an accident; considering pregnant women and their foetuses and embryos; monitoring public protection; dealing with 'contamination' of territories, rubble and residues and consumer products; recognising the importance of psychological consequences; and fostering the sharing of information. Relevant ICRP Recommendations were scrutinised, lessons were collected and suggestions were compiled. It was concluded that the radiological protection community has an ethical duty to learn from the lessons of Fukushima and resolve any identified challenges. Before another large accident occurs, it should be ensured that inter alia: radiation risk coefficients of potential health effects are properly interpreted; the limitations of epidemiological studies for attributing radiation effects following low exposures are understood; any confusion on protection quantities and units is resolved; the potential hazard from the intake of radionuclides into the body is elucidated; rescuers and volunteers are protected with an ad hoc system; clear recommendations on crisis management and medical care and on recovery and rehabilitation are available; recommendations on public protection levels (including infant, children and pregnant women and their expected offspring) and associated issues are consistent and understandable; updated recommendations on public monitoring policy are available; acceptable (or tolerable) 'contamination' levels are clearly stated and defined; strategies for mitigating the serious psychological consequences arising from radiological accidents are sought; and, last but not least, failures in fostering information sharing on radiological protection policy after an accident need to be addressed with recommendations to minimise such lapses in communication.

Concentration and characteristics of depleted uranium in water, air and biological samples collected in Serbia and Montenegro.

PubMed

Jia, Guogang; Belli, Maria; Sansone, Umberto; Rosamilia, Silvia; Gaudino, Stefania

2005-09-01

During the Balkan conflicts, in 1995 and 1999, depleted uranium (DU) rounds were employed and were left in the battlefield. Health concern is related to the risk arising from contamination of the environment with DU penetrators and dust. In order to evaluate the impact of DU on the environment and population in Serbia and Montenegro, radiological surveys of DU in water, air and biological samples were carried out over the period 27 October-5 November 2001. The uranium isotopic concentrations in biological samples collected in Serbia and Montenegro, mainly lichens and barks, were found to be in the range of 0.67-704 Bqkg(-1) for (238)U, 0.48-93.9 Bqkg(-1) for (234)U and 0.02-12.2 Bqkg(-1) for (235)U, showing uranium levels to be higher than in the samples collected at the control sites. Moreover, (236)U was detectable in some of the samples. The isotopic ratios of (234)U/(238)U showed DU to be detectable in many biological samples at all examined sites, especially in Montenegro, indicating widespread ground-surface DU contamination, albeit at very low level. The uranium isotopic concentrations in air obtained from the air filter samples collected in Serbia and Montenegro were found to be in the range of 1.99-42.1 microBqm(-3) for (238)U, 0.96-38.0 microBqm(-3) for (234)U, and 0.05-1.83 microBqm(-3) for (235)U, being in the typical range of natural uranium values. Thus said, most of the air samples are DU positive, this fact agreeing well with the widespread DU contamination detected in the biological samples. The uranium concentrations in water samples collected in Serbia and Montenegro were found to be in the range of 0.40-21.9 mBql(-1) for (238)U, 0.27-28.1 mBql(-1) for (234)U, and 0.01-0.88 mBql(-1) for (235)U, these values being much lower than those in mineral water found in central Italy and below the WHO guideline for drinking water. From a radiotoxicological point of view, at this moment there is no significant radiological risk related to these investigated sites in terms of possible DU contamination of water, air and/or plants.

Forage grasses with lower uptake of caesium and strontium could provide ‘safer’ crops for radiologically contaminated areas

PubMed Central

Beresford, Nicholas A.; Crout, Neil M. J.; Lovatt, J. Alan; Thomson, Russell; Broadley, Martin R.

2017-01-01

Substitution of a species or cultivar with higher uptake of an element by one with lower uptake has been proposed as a remediation strategy following accidental releases of radioactivity. However, despite the importance of pasture systems for radiological dose, species/cultivar substitution has not been thoroughly investigated for forage grasses. 397 cultivars from four forage grass species; hybrid ryegrass (Lolium perenne L. x Lolium multiflorum Lam.), perennial ryegrass (Lolium perenne L.), Italian ryegrass (Lolium multiflorum Lam.) and tall fescue (Festuca arundinacea Shreb.); were sampled from 19 field-based breeding experiments in Aberystwyth and Edinburgh (UK) in spring 2013 and analysed for caesium (Cs) and strontium (Sr) concentrations. In order to calculate concentration ratios (CRs; the concentration of an element in a plant in relation to the concentration in the soil), soils from the experiments were also analysed to calculate extractable concentrations of Cs and Sr. To test if cultivars have consistently low Cs and Sr concentration ratios, 17 hybrid ryegrass cultivars were sampled from both sites again in summer 2013 and spring and summer 2014. Tall fescue cultivars had lower Cs and Sr CRs than the other species. Three of the selected 17 hybrid ryegrass cultivars had consistently low Cs CRs, two had consistently low Sr CRs and one had consistently low Cs and Sr CRs. Cultivar substitution could reduce Cs CRs by up to 14-fold and Sr CRs by 4-fold in hybrid ryegrass. The identification of species and cultivars with consistently low CRs suggests that species or cultivar substitution could be an effective remediation strategy for contaminated areas. PMID:28459808

Plutonium release from Fukushima Daiichi fosters the need for more detailed investigations

NASA Astrophysics Data System (ADS)

Schneider, Stephanie; Walther, Clemens; Bister, Stefan; Schauer, Viktoria; Christl, Marcus; Synal, Hans-Arno; Shozugawa, Katsumi; Steinhauser, Georg

2013-10-01

The contamination of Japan after the Fukushima accident has been investigated mainly for volatile fission products, but only sparsely for actinides such as plutonium. Only small releases of actinides were estimated in Fukushima. Plutonium is still omnipresent in the environment from previous atmospheric nuclear weapons tests. We investigated soil and plants sampled at different hot spots in Japan, searching for reactor-borne plutonium using its isotopic ratio 240Pu/239Pu. By using accelerator mass spectrometry, we clearly demonstrated the release of Pu from the Fukushima Daiichi power plant: While most samples contained only the radionuclide signature of fallout plutonium, there is at least one vegetation sample whose isotope ratio (0.381 +/- 0.046) evidences that the Pu originates from a nuclear reactor (239+240Pu activity concentration 0.49 Bq/kg). Plutonium content and isotope ratios differ considerably even for very close sampling locations, e.g. the soil and the plants growing on it. This strong localization indicates a particulate Pu release, which is of high radiological risk if incorporated.

Assessing environmental risk of the retired filter bed area, Battelle West Jefferson

DOE Office of Scientific and Technical Information (OSTI.GOV)

Miller, S.F.; Thompson, M.D.; Glennon, M.A.

1997-04-01

Initial investigations conducted by the U.S. Department of Energy, Chicago Operations Office, and by Argonne National Laboratory used seismic refraction profiling, electrical resistivity depth sounding, conductivity profiling, magnetic gradiometry, and ground-penetrating radar to study environmental geophysics in the area of the Battelle West Jefferson site`s radiologically contaminated retired filter beds. The investigators used a combination of nonintrusive technologies and innovative drilling techniques to assess environmental risk at the filter beds and to improve understanding of the geology of the Big Darby Creek floodplain. The geophysical investigation, which showed that the preferred groundwater pathway is associated with a laterally extensive depositmore » of silty sand to sand that is less than 12 ft deep in the floodplain area, also guided the location of cone penetrometer test sites and piezometer installation. Cone penetrometer testing was useful for comparing continuous logging data with surface geophysical data in establishing correlations among unconsolidated materials.« less

[Contamination of the food chain with caesium-137 and strontium-90 in Switzerland].

PubMed

Riond, J L

2004-12-01

One task of the field physiology of nutrition is the monitoring of the quality of feedstuffs. Rations may consequently be prepared with unadulterated components. This review uses the example of contamination with the radionuclides caesium-137 und strontium-90 and shows how these two unwanted substances reach the end host via the food chain and how their untoward effects are expressed in animals and humans. The extent of the contamination with artificial radioactivity is followed with periodical measurements according to the program of the Division for Radiological Protection of the Swiss Federal Office of Public Health. The interpretation of the measurements and the directives of this division are designed to protect primarily human health, but also that of animals.

Rad-Release

ScienceCinema

None

2017-12-09

The R&D 100 Award winning Rad-Release Chemical Decontamination Technology is a highly effective (up to 99% removal rate), affordable, patented chemical-foam-clay decontamination process tailored to specific radiological and metal contaminants, which is applicable to a wide variety of substrates. For more information about this project, visit http://www.inl.gov/rd100/2011/rad-release/

Monte Carlo Simulations for Homeland Security Using Anthropomorphic Phantoms

DOE Office of Scientific and Technical Information (OSTI.GOV)

Burns, Kimberly A.

A radiological dispersion device (RDD) is a device which deliberately releases radioactive material for the purpose of causing terror or harm. In the event that a dirty bomb is detonated, there may be airborne radioactive material that can be inhaled as well as settle on an individuals leading to external contamination.

Nutrition in emergencies: Issues involved in ensuring proper nutrition in post-chemical, biological, radiological, and nuclear disaster

PubMed Central

Singh, Som Nath

2010-01-01

Accidental or deliberate exposure to chemical, biological, radiological, and nuclear (CBRN) agents poses considerable threat throughout the world. Under such conditions, ensuring proper nutrition is a difficult task due to contamination of food available in the affected area. Generally, food is not prepared or served in an environment contaminated by CBRN agents. Foods that are properly packed need to be decontaminated from outside before use. These agents get incorporated in to food chain. Therefore, especially the foliage vegetables, milk and meat products from affected area are not fit for consumption. Potassium iodide has protective role, as radioiodine uptake into the thyroid can be blocked by its pharmacological doses. This is most effective when taken before exposure, but still has significant effects up to five to six hours postexposure. The antioxidant vitamins and minerals may be included in therapeutic feeding programs, as they are known to protect against oxidative stress. Minimum requirement of calories and nutrients are similar to other disasters and are discussed in the present review. PMID:21829320

Nutrition in emergencies: Issues involved in ensuring proper nutrition in post-chemical, biological, radiological, and nuclear disaster.

PubMed

Singh, Som Nath

2010-07-01

Accidental or deliberate exposure to chemical, biological, radiological, and nuclear (CBRN) agents poses considerable threat throughout the world. Under such conditions, ensuring proper nutrition is a difficult task due to contamination of food available in the affected area. Generally, food is not prepared or served in an environment contaminated by CBRN agents. Foods that are properly packed need to be decontaminated from outside before use. These agents get incorporated in to food chain. Therefore, especially the foliage vegetables, milk and meat products from affected area are not fit for consumption. Potassium iodide has protective role, as radioiodine uptake into the thyroid can be blocked by its pharmacological doses. This is most effective when taken before exposure, but still has significant effects up to five to six hours postexposure. The antioxidant vitamins and minerals may be included in therapeutic feeding programs, as they are known to protect against oxidative stress. Minimum requirement of calories and nutrients are similar to other disasters and are discussed in the present review.

Health effects of SRS non-radiological air emissions

DOE Office of Scientific and Technical Information (OSTI.GOV)

Stewart, J.

1997-06-16

This report examines the potential health effects of non radiological emissions to the air resulting from operations at the Savannah River Site (SRS). The scope of this study was limited to the 55 air contaminants for which the US Environmental Protection Agency (EPA) has quantified risk by determining unit risk factors (excess cancer risks) and/or reference concentrations (deleterious non cancer risks). Potential health impacts have been assessed in relation to the maximally exposed individual. This is a hypothetical person who resides for a lifetime at the SRS boundary. The most recent (1994) quality assured SRS emissions data available were used.more » Estimated maximum site boundary concentrations of the air contaminants were calculated using air dispersion modeling and 24-hour and annual averaging times. For the emissions studied, the excess cancer risk was found to be less than the generally accepted risk level of 1 in 100,000 and, in most cases, was less than 1 in 1,000,000. Deleterious non cancer effects were also found to be very unlikely.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Dubart, Philippe; Hautot, Felix; Morichi, Massimo

Good management of dismantling and decontamination (D and D) operations and activities is requiring safety, time saving and perfect radiological knowledge of the contaminated environment as well as optimization for personnel dose and minimization of waste volume. In the same time, Fukushima accident has imposed a stretch to the nuclear measurement operational approach requiring in such emergency situation: fast deployment and intervention, quick analysis and fast scenario definition. AREVA, as return of experience from his activities carried out at Fukushima and D and D sites has developed a novel multi-sensor solution as part of his D and D research, approachmore » and method, a system with real-time 3D photo-realistic spatial radiation distribution cartography of contaminated premises. The system may be hand-held or mounted on a mobile device (robot, drone, e.g). In this paper, we will present our current development based on a SLAM technology (Simultaneous Localization And Mapping) and integrated sensors and detectors allowing simultaneous topographic and radiological (dose rate and/or spectroscopy) data acquisitions. This enabling technology permits 3D gamma activity cartography in real-time. (authors)« less

Corrective Action Investigation Plan for Corrective Action Unit 127: Areas 25 and 26 Storage Tanks, Nevada Test Site, Nevada (Rev. No.: 0, August 2002)

DOE Office of Scientific and Technical Information (OSTI.GOV)

NNSA /NV

This Corrective Action Investigation Plan (CAIP) contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Offices's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 127 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 127 is located on the Nevada Test Site approximately 65 miles northwest of Las Vegas, Nevada. This CAU is comprised of 12 Corrective Action Sites (CASs) located at Test Cell C; the Engine Maintenance, Assembly, and Disassembly (E-MAD) Facility; the X-Tunnel in Area 25; the Pluto Disassembly Facility; themore » Pluto Check Station; and the Port Gaston Training Facility in Area 26. These CASs include: CAS 25-01-05, Aboveground Storage Tank (AST); CAS 25-02-02, Underground Storage Tank (UST); CAS 25-23-11, Contaminated Materials; CAS 25-12-01, Boiler; CAS 25-01-06, AST; CAS 25-01-07, AST; CAS 25-02-13, UST; CAS 26- 01-01, Filter Tank (Rad) and Piping; CAS 26-01-02, Filter Tank (Rad); CAS 26-99-01, Radioactively Contaminated Filters; CAS 26-02-01, UST; CAS 26-23-01, Contaminated Liquids Spreader. Based on site history, process knowledge, and previous field efforts, contaminants of potential concern for CAU 127 include radionuclides, metals, total petroleum hydrocarbons, volatile organic compounds, asbestos, and polychlorinated biphenyls. Additionally, beryllium may be present at some locations. The sources of potential releases are varied, but releases of contaminated liquids may have occurred and may have migrated into and impacted soil below and surrounding storage vessels at some of the CASs. Also, at several CASs, asbestos-containing materials may be present on the aboveground structures and may be friable. Exposure pathways are limited to ingestion, inhalation, and dermal contact (adsorption) of soils/sediments or liquids, or inhalation of contaminants by site workers due to disturbance of contaminated materials. Future land-use scenarios limit subsequent uses of the CASs to various nonresidential (i.e., industrial) activities. Field activities will consist of radiological walkover and screening surveys, and field-screening and collecting of both tank content and soil samples, and further sample testing as appropriate. A two-step data quality objective strategy will be followed: (1) Phase I will be to collect environmental samples for laboratory analysis to confirm the presence or absence of contaminants at concentrations exceeding preliminary action levels; and (2) Phase II will be to collect additional environmental samples for laboratory analysis to determine the extent of contamination identified in Phase I. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.« less

Corrective Action Investigation Plan for Corrective Action Unit 371: Johnnie Boy Crater and Pin Stripe Nevada Test Site, Nevada, Revision 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Patrick Matthews

Corrective Action Unit (CAU) 371 is located in Areas 11 and 18 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 371 is comprised of the two corrective action sites (CASs) listed below: • 11-23-05, Pin Stripe Contamination Area • 18-45-01, U-18j-2 Crater (Johnnie Boy) These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation before evaluating corrective action alternatives and selecting the appropriate correctivemore » action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on November 19, 2008, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 371. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the corrective action investigation for CAU 371 includes the following activities: • Move surface debris and/or materials, as needed, to facilitate sampling. • Conduct radiological surveys. • Measure in situ external dose rates using thermoluminescent dosimeters or other dose measurement devices. • Collect and submit environmental samples for laboratory analysis to determine internal dose rates. • Combine internal and external dose rates to determine whether total dose rates exceed final action levels (FALs). • Collect and submit environmental samples for laboratory analysis to determine whether chemical contaminants are present at concentrations exceeding FALs. • If contamination exceeds FALs, define the extent of the contamination exceeding FALs. • Investigate waste to determine whether potential source material is present. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy; and U.S. Department of Defense. Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted following approval of the plan.« less

Autonomous mobile robot for radiologic surveys

DOEpatents

Dudar, A.M.; Wagner, D.G.; Teese, G.D.

1994-06-28

An apparatus is described for conducting radiologic surveys. The apparatus comprises in the main a robot capable of following a preprogrammed path through an area, a radiation monitor adapted to receive input from a radiation detector assembly, ultrasonic transducers for navigation and collision avoidance, and an on-board computer system including an integrator for interfacing the radiation monitor and the robot. Front and rear bumpers are attached to the robot by bumper mounts. The robot may be equipped with memory boards for the collection and storage of radiation survey information. The on-board computer system is connected to a remote host computer via a UHF radio link. The apparatus is powered by a rechargeable 24-volt DC battery, and is stored at a docking station when not in use and/or for recharging. A remote host computer contains a stored database defining paths between points in the area where the robot is to operate, including but not limited to the locations of walls, doors, stationary furniture and equipment, and sonic markers if used. When a program consisting of a series of paths is downloaded to the on-board computer system, the robot conducts a floor survey autonomously at any preselected rate. When the radiation monitor detects contamination, the robot resurveys the area at reduced speed and resumes its preprogrammed path if the contamination is not confirmed. If the contamination is confirmed, the robot stops and sounds an alarm. 5 figures.

Autonomous mobile robot for radiologic surveys

DOEpatents

Dudar, Aed M.; Wagner, David G.; Teese, Gregory D.

1994-01-01

An apparatus for conducting radiologic surveys. The apparatus comprises in the main a robot capable of following a preprogrammed path through an area, a radiation monitor adapted to receive input from a radiation detector assembly, ultrasonic transducers for navigation and collision avoidance, and an on-board computer system including an integrator for interfacing the radiation monitor and the robot. Front and rear bumpers are attached to the robot by bumper mounts. The robot may be equipped with memory boards for the collection and storage of radiation survey information. The on-board computer system is connected to a remote host computer via a UHF radio link. The apparatus is powered by a rechargeable 24-volt DC battery, and is stored at a docking station when not in use and/or for recharging. A remote host computer contains a stored database defining paths between points in the area where the robot is to operate, including but not limited to the locations of walls, doors, stationary furniture and equipment, and sonic markers if used. When a program consisting of a series of paths is downloaded to the on-board computer system, the robot conducts a floor survey autonomously at any preselected rate. When the radiation monitor detects contamination, the robot resurveys the area at reduced speed and resumes its preprogrammed path if the contamination is not confirmed. If the contamination is confirmed, the robot stops and sounds an alarm.

Position-sensitive radiation monitoring (surface contamination monitor). Innovative technology summary report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1999-06-01

The Shonka Research Associates, Inc. Position-Sensitive Radiation Monitor both detects surface radiation and prepares electronic survey map/survey report of surveyed area automatically. The electronically recorded map can be downloaded to a personal computer for review and a map/report can be generated for inclusion in work packages. Switching from beta-gamma detection to alpha detection is relatively simple and entails moving a switch position to alpha and adjusting the voltage level to an alpha detection level. No field calibration is required when switching from beta-gamma to alpha detection. The system can be used for free-release surveys because it meets the federal detectionmore » level sensitivity limits requires for surface survey instrumentation. This technology is superior to traditionally-used floor contamination monitor (FCM) and hand-held survey instrumentation because it can precisely register locations of radioactivity and accurately correlate contamination levels to specific locations. Additionally, it can collect and store continuous radiological data in database format, which can be used to produce real-time imagery as well as automated graphics of survey data. Its flexible design can accommodate a variety of detectors. The cost of the innovative technology is 13% to 57% lower than traditional methods. This technology is suited for radiological surveys of flat surfaces at US Department of Energy (DOE) nuclear facility decontamination and decommissioning (D and D) sites or similar public or commercial sites.« less

Corrective Action Plan for Corrective Action Unit 366: Area 11 Plutonium Valley Dispersion Sites, Nevada National Security Site, Nevada

DOE Office of Scientific and Technical Information (OSTI.GOV)

None

This Corrective Action Plan has been prepared for Corrective Action Unit (CAU) 366, Area 11 Plutonium Valley Dispersion Sites, in accordance with the Federal Facility Agreement and Consent Order (FFACO, 1996 as amended). CAU 366 consists of the following six Corrective Action Sites (CASs) located in Area 11 of the Nevada National Security Site: · CAS 11-08-01, Contaminated Waste Dump #1 · CAS 11-08-02, Contaminated Waste Dump #2 · CAS 11-23-01, Radioactively Contaminated Area A · CAS 11-23-02, Radioactively Contaminated Area B · CAS 11-23-03, Radioactively Contaminated Area C · CAS 11-23-04, Radioactively Contaminated Area D Site characterization activities weremore » performed in 2011 and 2012, and the results are presented in Appendix A of the Corrective Action Decision Document (CADD) for CAU 366 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2012a). The following closure alternatives were recommended in the CADD: · No further action for CAS 11-23-01 · Closure in place for CASs 11-08-01, 11-08-02, 11-23-02, 11-23-03, and 11-23-04 The scope of work required to implement the recommended closure alternatives includes the following: · Non-engineered soil covers approximately 3 feet thick will be constructed at CAS 11-08-01 over contaminated waste dump (CWD) #1 and at CAS 11-08-02 over CWD #2. · FFACO use restrictions (URs) will be implemented for the areas where the total effective dose (TED) exceeds the final action level (FAL) of 25 millirems per Occasional Use Area year (mrem/OU-yr). The FAL is based on an assumption that the future use of the site includes occasional work activities and that workers will not be assigned to the area on a regular basis. A site worker under this scenario is assumed to be on site for a maximum of 80 hours per year for 5 years. The FFACO UR boundaries will encompass the areas where a worker would be exposed to 25 millirems of radioactivity per year if they are present for 80 hours per year. These boundaries will be defined as follows: – It is assumed that radiological contaminants are present at CAS 11-08-01 and CAS 11-08-02 within CWDs #1 and #2 at levels exceeding the FAL. Therefore, UR boundaries will be established around the perimeters of the soil covers that will be constructed at CWD #1 and CWD #2. A geophysical survey revealed buried metallic debris outside the fence and adjacent to CWD #1. Therefore, the UR boundary for CWD #1 will be expanded to include the mound containing buried material. – It is assumed that radiological contaminants are present at CAS 11-23-02, CAS 11-23-03, and CAS 11-23-04, within the three High Contamination Area (HCA) boundaries associated with the 11b, 11c, and 11d test areas at levels exceeding the FAL. Therefore, the UR boundaries will be established around the perimeters of the HCAs. The TED at an area of soil impacted by radiological debris outside the fence and adjacent to the 11c test area HCA exceeds the FAL of 25 mrem/OU-yr. Because the radiological impact from the debris at this location is visible on the aerial flyover radiological survey, all other areas within this isopleth of the flyover survey are conservatively also assumed to exceed the FAL. Therefore, the UR boundaries for the 11b, 11c, and 11d test areas will be expanded to include the areas within this isopleth. · The FFACO URs will all be located within the large Contamination Area (CA) that encompasses Plutonium Valley. Because access to the CA is limited and entry into the CA for post-closure inspections and maintenance would be impractical, UR warning signs will be posted along the existing CA fence. In accordance with the Soils Risk-Based Corrective Action Evaluation Process (NNSA/NSO, 2012b), an administrative UR will be implemented as a best management practice for the areas where the TED exceeds 25 millirems per Industrial Area year. This limit is based on continuous industrial use of the site and addresses exposure to industrial workers who would regularly be assigned to the work area for an entire career (250 days per year, 8 hours per day, for 25 years). Establishing an administrative UR will prevent inadvertent exposure of workers to radioactivity if a more intensive use of the site were to be considered in the future. As a precautionary measure, the administrative UR boundary will be expanded to include the areas where removable contamination is present that exceeds the criterion for a CA. This will further ensure that workers will not perform future activities within this area without being notified of the presence of site contaminants. Therefore, the administrative UR boundary will be established around the perimeters of the large CA that encompasses the site and the CAs associated with the decontamination station and hot park.« less

Radiological characterization of skyshine from a retired, low-level, radioactive liquid effluent disposal facility at Hanford

DOE Office of Scientific and Technical Information (OSTI.GOV)

Brown, R.C.; Perkins, C.J.

1991-02-01

The 1301-N Liquid Waste Disposal Facility, located on the Hanford Site received N Reactor low-level radioactive liquid process effluent from 1962 to 1985. Radiation emanating from the top of the trench sections was not significant because of the sediments were normally under several meters of water, which provided the necessary shielding. Following retirement of the facility, the liquid in the trench sections percolated into the ground leaving the residual radioactively contaminated sediments unshielded along the bottom and sides of the trench sections. The radioactive constituents of the contaminated sediments include the gamma-emitting isotopes Co-60 and Cs-137. Because of the lackmore » of water covering, some of the gamma photons that were emitted upward were scattered downward due to Compton interaction with atmospheric constituents. This phenomenon is known as skyshine.'' A radiological characterization was required to provide guidance for determining the effectiveness of interim stabilization alternatives that would not adversely affect future Resource Conservation and Recovery Act site closure activities, (e.g., filling in trench sections with spoils from excavation activities). A noninvasive radiological characterization of this disposal facility and the affected area of the Columbia River shoreline was conducted. This characterization confirmed that skyshine is the cause of the elevated shoreline exposure rates and provided a model that could be used to rate the effectiveness of alternative interim stabilization measures. 4 refs., 5 figs.« less

Efficacy evaluation of managed population shift in Ukraine from zone of obligate (compulsory) resettlement as a measure of public radiation protection.

PubMed

Gunko, N V

2015-12-01

Evaluation of efficacy of the managed population transmigration from zone of obligate (compulsory) resettlement as a measure of civil protection after the Chernobyl NPP accident from the perspective of radiation biology. Legislative and statutory tutorial documents that regulate the managed population shift from radiologically contaminated territories of Ukraine and data from the Ukrainian State Service of Statistics on time limits and scopes of population transmigration from contaminated settlements were the informational back ground of the study. Data on retrospective and expected/anticipated radiation doses in population of settlements exposed to radiological contamination in Ukraine after the Chernobyl disaster summarized for the 1986-1997 peri od and up to 2055 were the information source for calculation of averted doses due to population shift. Battery of basic research empirical evidence review methods was applied under the calculation, systemic, and biomedical approach. Population shift from zone of obligate (compulsore) resettlement (hereafter referred to as Zone 2) to stop the radiation exposure as a tool of civil protection from emergency ionizing radiation after the Chernobyl NPP accident was scientifically substantiated and expedient from the perspective of radiation biology. Estimability of a managed population shift from "dose effect" perspective and "benefit/harm" principle is worse because of data absence on individual radiation doses to migrants in the country. Public shift in 1990 and 1991 was most effective from the viewpoint of level of averted lifetime dose. Due to transmigration the averted lifetime dose to the most vulnerable group of the Chernobyl disaster survivors i.e. children aged 0 years varied from 11.2 to 28.8 mSv (calculated for the Perejizdiv village council of Zhytomyr province). Since 2000 there was almost no public shift being not accomplished in the scheduled scope. Delay and incompleteness of transmigration have diminished the efficacy of this measure in the framework of radiological protection of population. N. V. Gunko.

Attitudes to coping with radiologically suspect or contaminated milk in the UK: a dairy industry viewpoint.

PubMed

Komorowski, E S

2005-01-01

The attitudes of the UK milk processing industry to a nuclear incident which resulted in milk supplies being suspected of being contaminated, or actually being contaminated, with radioactivity is examined. The factors influencing these attitudes are discussed, together with their implications. In the event of a nuclear incident in which part of the United Kingdom's milk supply is possibly contaminated, the milk processing industry will want to ensure that consumers and retailers maintain complete confidence in dairy products. As a consequence the industry will require that solutions are not adopted merely to avoid wastage of milk, or awkward milk disposal problems. In the early history of the BSE crisis the government wrongly assured consumers that beef was completely safe to eat. It will be necessary to ensure that any assurances that milk is safe, following a nuclear incident, are well founded.

Water Shortage: Lessons in Conservation From the Great California Drought, 1976-1977

NASA Astrophysics Data System (ADS)

Showstack, Randy

Legislation moving quickly through both houses of the U.S. Congress would establish a fund to promote and support research and development to increase the security of the nation's water infrastructure from source to faucet.The House of Representatives bill, "The Water Infrastructure Security and Research and Development Act" (HR 3178), would provide $12 million per year for fiscal years 2002-2006 for a number of research areas. These include assessing water supply systems for physical vulnerabilities, including biological, chemical, and radiological contamination; devising real-time systems to monitor water for contamination; determining mitigation options; and upgrading security technologies.

Contaminated Human Remains: Transportable Decontamination - 1. Technical Readiness Level Estimate. 2. Vaccinia Virus Ionizing Radiation Inactivation in a Human Phantom. 3. Current State of Technology Relevant to Development of a Transportable System for Treatment of Contaminated Human Remains

DTIC Science & Technology

2011-05-30

affect chemical agents. Therefore no change in the methods for chemical or radiological decontamination would be necessary. 14. Radiation...here is the high radiation doses do affect the ability to polymerase chain reaction methods. It appears, depending on the dose and target, these...2001) Bacillus spore inactivation methods affect detection assays. Appl Environ Microbiol. 67(8): p. 3665‐70. DeCarlos, A. and Paez, E. (1991

A Comparative Study Environmental and Radiological Causes Of Cancer In River Nile State, Sudan

NASA Astrophysics Data System (ADS)

Hamid, Eyad; Khair, Hatim

The causes of cancer in River Nile state are differ between environmental and radiological, this paper tried to make comparison between the two causes, to determine the real cause behind the large rising of cancer cases in this state, considering the daily habits for the patients and the possible contamination in the natural resources around them. The noticeable thing that most of cancer cases are might be due to the high concentration of nitrate pollutant detected in natural resources such as drinking water; also by looking to the radioactive elements we see there's high concentration of some radioactive elements specially the K-40 which found in Portulaca Oleracea.

Ecotoxicity literature review of selected Hanford Site contaminants

DOE Office of Scientific and Technical Information (OSTI.GOV)

Driver, C.J.

1994-03-01

Available information on the toxicity, food chain transport, and bioconcentration of several Hanford Site contaminants were reviewed. The contaminants included cesium-137, cobalt-60, europium, nitrate, plutonium, strontium-90, technetium, tritium, uranium, and chromium (III and VI). Toxicity and mobility in both aquatic and terrestrial systems were considered. For aquatic systems, considerable information was available on the chemical and/or radiological toxicity of most of the contaminants in invertebrate animals and fish. Little information was available on aquatic macrophyte response to the contaminants. Terrestrial animals such as waterfowl and amphibians that have high exposure potential in aquatic systems were also largely unrepresented in themore » toxicity literature. The preponderance of toxicity data for terrestrial biota was for laboratory mammals. Bioconcentration factors and transfer coefficients were obtained for primary producers and consumers in representative aquatic and terrestrial systems; however, little data were available for upper trophic level transfer, particularly for terrestrial predators. Food chain transport and toxicity information for the contaminants were generally lacking for desert or sage brush-steppe organisms, particularly plants and reptiles« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Bourne, H.G. Jr.; Wynd, J.C.; Dwork, R.E.

Measures in use or being considered by the Ohio Dept. of Health to reduce radiation hazards, particularly from fallout radionuclides and from excessive medical and dental diagnostic exposure, are discussed. The extent of contamination of Ohio milk with radiostrontium, cesium, and iodine has been a source of apprehension. however, more important in attempts to halt the upward trend in exposure to radiation is reduction of exposure in radiodiagnosis. The individual physician or dentist is the appropriate responsible agent who must weigh benefit against nisk, and this right of the physician or dentist is guaranteed in the statutes whlch do notmore » limit the kind and amount of radiation that may be intentionally applied to a person for diagnostic or therapeutic purposes by or under the direction of a physician or dentist. To fulfill this responsibility the following precepts are recommended: There should be clear-cut clinical indications before any x-ray examination is undertaken, and it should be ascertained whether there has been a previous radiological examination which would make further examination unnecessary. There should be consultation between clinician and radiologist before extensive or repeated radiological examinations of young individuals are undertaken. To reduce repeat studies, strict attention should be paid to adequate preparation before abdominal investigation. Special precautions should be adopted in radiography of pregnant women. Previous history of radiotherapy should be ascertained before a new course of treatment is undertaken. Radiotherapy should not be employed in benign conditions which respond to other types of treatment. Specific ways of reducing exposure during radiologic and fluoroscopic tests are also considered. (BBB)« less

40 CFR 2.304 - Special rules governing certain information obtained under the Safe Drinking Water Act.

Code of Federal Regulations, 2012 CFR

2012-07-01

...) Contaminant means any physical, chemical, biological, or radiological substance or matter in water. (3... released by EPA because of the relevance of the information to a proceeding, notwithstanding the fact that... information to which this section applies because of its relevance to a proceeding shall be made only in...

40 CFR 2.304 - Special rules governing certain information obtained under the Safe Drinking Water Act.

Code of Federal Regulations, 2013 CFR

2013-07-01

...) Contaminant means any physical, chemical, biological, or radiological substance or matter in water. (3... released by EPA because of the relevance of the information to a proceeding, notwithstanding the fact that... information to which this section applies because of its relevance to a proceeding shall be made only in...

Development of a statewide hospital plan for radiologic emergencies

DOE Office of Scientific and Technical Information (OSTI.GOV)

Dainiak, Nicholas; Delli Carpini, Domenico; Bohan, Michael

Although general guidelines have been developed for triage of victims in the field and for hospitals to plan for a radiologic event, specific information for clinicians and administrators is not available for guidance in efficient management of radiation victims during their early encounter in the hospital. A consensus document was developed by staff members of four Connecticut hospitals, two institutions of higher learning, and the State of Connecticut Department of Environmental Protection and Office of Emergency Preparedness, with assistance of the American Society for Therapeutic Radiology and Oncology. The objective was to write a practical manual for clinicians (including radiationmore » oncologists, emergency room physicians, and nursing staff), hospital administrators, radiation safety officers, and other individuals knowledgeable in radiation monitoring that would be useful for evaluation and management of radiation injury. The rationale for and process by which the radiation response plan was developed and implemented in the State of Connecticut are reviewed. Hospital admission pathways are described, based on classification of victims as exposed, contaminated, and/or physically injured. This manual will be of value to those involved in planning the health care response to a radiologic event.« less

Chemical, physical, and radiological quality of selected public water supplies in Florida, February-April 1980

USGS Publications Warehouse

Franks, Bernard J.; Irwin, G.A.

1981-01-01

Virtually all treated public water supplies in Florida meet the National Interim Primary and Secondary Drinking Water Regulations. These findings are based on a water-quality reconnaissance of 126 raw and treated public water supplies throughout the State during the period February through April 1980. Primary drinking water regulations maximum contaminant levels were rarely exceeded, although mercury (1 site), fluoride (2 sites), and radionuclides (3 sites) in water supplies were above established maximum contaminant levels. Dissolved solids, chloride, copper, manganese, iron, color, sulfate, and pH, were occasionally slightly in excess of the recommended maximum contaminant levels of the secondary drinking water regulation. The secondary regulations, however, pertain mainly to the esthetic quality of drinking water and not directly to public health aspects. (USGS)

Decommissioning a phosphoric acid production plant: a radiological protection case study.

PubMed

Stamatis, V; Seferlis, S; Kamenopoulou, V; Potiriadis, C; Koukouliou, V; Kehagia, K; Dagli, C; Georgiadis, S; Camarinopoulos, L

2010-12-01

During a preliminary survey at the area of an abandoned fertilizer plant, increased levels of radioactivity were measured at places, buildings, constructions and materials. The extent of the contamination was determined and the affected areas were characterized as controlled areas. After the quantitative and qualitative determination of the contaminated materials, the decontamination was planned and performed step by step: the contaminated materials were categorized according to their physical characteristics (scrap metals, plastic pipes, scales and residues, building materials, etc) and according to their level of radioactivity. Depending on the material type, different decontamination and disposal options were proposed; the most appropriate technique was chosen taking into account apart from technical issues, the legal framework, radiation protection issues, the opinion of the local authorities involved as well as the owner's wish. After taking away the biggest amount of the contaminated materials, an iterative process consisting of surveys and decontamination actions was performed in order to remove the residual traces of contamination from the area. During the final survey, no residual surface contamination was detected; some sparsely distributed low level contaminated materials deeply immersed into the soil were found and removed. Copyright © 2010 Elsevier Ltd. All rights reserved.

Formerly utilized MED/AEC sites remedial action program. Radiological survey of The George Herbert Jones Chemical Laboratory, The University of Chicago, Chicago, Illinois, June 13-17, 1977

DOE Office of Scientific and Technical Information (OSTI.GOV)

Wynveen, R.A.; Smith, W.H.; Mayes, C.B.

A comprehensive radiological survey was conducted at George Herbert Jones Chemical Laboratory at the University of Chicago, Chicago, Illinois. Radiochemistry for the MED/AEC project was performed in this building in the 1940s. The building is now used as laboratories, offices, and classrooms. The survey was undertaken to determine the location and quantities of any radioactive materials remaining from the MED/AEC operations. Forty-three spots of contamination possibly resulting from MED/AEC occupancy in 17 rooms exceeded the allowable limits as given in the ANSI Standard N13.12. Under current use conditions, the potential for radiation exposure to occupants of this building from thesemore » sources of contamination is remote. Concentrations of radon daughters in the air of the building, as measured with grab-sampling techniques, were below the limit of 0.01 WL above background as given in the Surgeon General's Guidelines. No long-lived radionuclides were detected in any air sample. Concentrations of radionuclides in soil samples from near the laboratory generally indicated background levels. In order to reduce the potential for radiation exposure, remedial measures such as stabilization of the contamination in place would be applicable as a short-term measure. In order to reduce the risk in the event that building modifications take place in the future, health physics procedures and coverage are recommended. The long-term solution would involve decontamination by removal of the radioactive residues from the 17 rooms or areas where contamination possibly resulting from MED/AEC activities was detected.« less

Worker and environmental protection issues in the remediation of an abandoned source manufacturing facility.

PubMed

Hoffman, Daniel E

2003-02-01

The Gulf Nuclear Superfund Site located in Odessa, Texas, was an abandoned radioactive source production facility slated for cleanup as a Removal Action under the U.S. Environmental Protection Agency Region VI Superfund program. Prior to cessation of operations and abandonment of the facility in 1992, it was used for the production of radioactive sources used in the oil and gas industry and nuclear medicine applications. Pangea Group was contracted by the U.S. Army Corps of Engineers (USACE) Kansas City District to perform remediation of the site and other contaminated debris, cleaning of interior building surfaces, building demolition, and excavation/removal of contaminated soils and septic system. The project scope also included loading, containerization and transportation of low-level radioactive wastes for offsite disposal. Primary radionuclides present at the facility were 137Cs, 60Co, and 241Am. The project also included packaging and removal of radioactive sources and mixed waste consisting of radiologically contaminated lead shot and lead source containers. Included in the paper is a discussion of primary worker protection and environmental protection measures employed on the project. Worker protection issues included the control of industrial and construction safety hazards as well as control of external and internal radiation dose. Control of air emissions and contaminated wastewater were also very important, especially due to the location of the site. The site was located in an area containing both residential and commercial properties. Several residences and businesses were located immediately adjacent to the site. The project involved the participation of the USACE Kansas City District, EPA Region 6, and the Texas Bureau of Radiological Health. Field work on the project started in April 2001 and was completed approximately five months later.

Worker and Environmental Protection Issues in the Remediation Of an Abandoned Source Manufacturing Facility.

PubMed

Hoffman, Daniel E.

2003-02-01

The Gulf Nuclear Superfund Site located in Odessa, Texas, was an abandoned radioactive source production facility slated for cleanup as a Removal Action under the U.S. Environmental Protection Agency Region VI Superfund program. Prior to cessation of operations and abandonment of the facility in 1992, it was used for the production of radioactive sources used in the oil and gas industry and nuclear medicine applications. Pangea Group was contracted by the U.S. Army Corps of Engineers (USACE) Kansas City District to perform remediation of the site and other contaminated debris, cleaning of interior building surfaces, building demolition, and excavation/removal of contaminated soils and septic system. The project scope also included loading, containerization and transportation of low-level radioactive wastes for offsite disposal. Primary radionuclides present at the facility were Cs, Co, and Am. The project also included packaging and removal of radioactive sources and mixed waste consisting of radiologically contaminated lead shot and lead source containers. Included in the paper is a discussion of primary worker protection and environmental protection measures employed on the project. Worker protection issues included the control of industrial and construction safety hazards as well as control of external and internal radiation dose. Control of air emissions and contaminated wastewater were also very important, especially due to the location of the site. The site was located in an area containing both residential and commercial properties. Several residences and businesses were located immediately adjacent to the site. The project involved the participation of the USACE Kansas City District, EPA Region 6, and the Texas Bureau of Radiological Health. Field work on the project started in April 2001 and was completed approximately five months later.

Surrogate Indicators of Radionuclide Migration at the Amargosa Desert Research Site, Nye County, Nevada

NASA Astrophysics Data System (ADS)

Stonestrom, D. A.; Andraski, B. J.; Baker, R. J.; Luo, W.; Michel, R. L.

2005-05-01

Contaminant-transport processes are being investigated at the U.S. Geological Survey's Amargosa Desert Research Site (ADRS), adjacent to the Nation's first commercial disposal facility for low-level radioactive waste. Gases containing tritium and radiocarbon are migrating through a 110-m thick unsaturated zone from unlined trenches that received waste from 1962 to 1992. Information on plume dynamics comes from an array of shallow (<2 m) and two vertical arrays of deep (5-109 m) gas-sampling ports, plus ground-water monitoring wells. Migration is dominated by lateral transport in the upper 50 m of sediments. Radiological analyses require ex-situ wet-chemical techniques, because in-situ sensors for the radionuclides of interest do not exist. As at other LLRW-disposal facilities, radionuclides at the ADRS are mixed with varying amounts of volatile organic compounds (VOCs) and other substances. Halogenated-methanes, -ethanes, and -ethenes dominate the complex mixture of VOCs migrating from the disposal area. These compounds and their degradates provide a distinctive "fingerprint" of contamination originating from low-level radioactive waste. Carbon-dioxide and VOC anomalies provide indicator proxies for radionuclide contamination. Spatial and temporal patterns of co-disposed and byproduct constituents provide field-scale information about physical and biochemical processes involved in transport. Processes include reduction and biorespiration within trenches, and largely non-reactive, barometrically dispersed diffusion away from trenches.

Medical Student Perceptions of Radiology Use in Anatomy Teaching

ERIC Educational Resources Information Center

Murphy, Kevin P.; Crush, Lee; O'Malley, Eoin; Daly, Fergus E.; Twomey, Maria; O'Tuathaigh, Colm M. P.; Maher, Michael M.; Cryan, John F.; O'Connor, Owen J.

2015-01-01

The use of radiology in the teaching of anatomy to medical students is gaining in popularity; however, there is wide variation in how and when radiology is introduced into the curriculum. The authors sought to investigate students' perceptions regarding methods used to depict and teach anatomy and effects of integrated radiology instruction on…

2016 Annual Inspection and Radiological Survey Results for the Piqua, Ohio, Decommissioned Reactor Site, July 2016

DOE Office of Scientific and Technical Information (OSTI.GOV)

Zimmerman, Brian; Miller, Michele

This report presents the findings of the annual inspection and radiological survey of the Piqua, Ohio, Decommissioned Reactor Site (site). The decommissioned nuclear power demonstration facility was inspected and surveyed on April 15, 2016. The site, located on the east bank of the Great Miami River in Piqua, Ohio, was in fair physical condition. There is no requirement for a follow-up inspection, partly because City of Piqua (City) personnel participated in a March 2016 meeting to address reoccurring safety concerns. Radiological survey results from 104 locations revealed no removable contamination. One direct beta activity reading in a floor drain onmore » the 56-foot level (1674 disintegrations per minute [dpm]/100 square centimeters [cm2]) exceeded the minimum detectable activity (MDA). Beta activity has been detected in the past at this floor drain. The reading was well below the action level of 5000 dpm/100 cm2.« less

Nearest Neighbor Averaging and its Effect on the Critical Level and Minimum Detectable Concentration for Scanning Radiological Survey Instruments that Perform Facility Release Surveys.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Fournier, Sean Donovan; Beall, Patrick S; Miller, Mark L

2014-08-01

Through the SNL New Mexico Small Business Assistance (NMSBA) program, several Sandia engineers worked with the Environmental Restoration Group (ERG) Inc. to verify and validate a novel algorithm used to determine the scanning Critical Level (L c ) and Minimum Detectable Concentration (MDC) (or Minimum Detectable Areal Activity) for the 102F scanning system. Through the use of Monte Carlo statistical simulations the algorithm mathematically demonstrates accuracy in determining the L c and MDC when a nearest-neighbor averaging (NNA) technique was used. To empirically validate this approach, SNL prepared several spiked sources and ran a test with the ERG 102F instrumentmore » on a bare concrete floor known to have no radiological contamination other than background naturally occurring radioactive material (NORM). The tests conclude that the NNA technique increases the sensitivity (decreases the L c and MDC) for high-density data maps that are obtained by scanning radiological survey instruments.« less

Designing the ideal model for assessment of wound contamination after gunshot injuries: a comparative experimental study

PubMed Central

2012-01-01

Background Modern high-velocity projectiles produce temporary cavities and can thus cause extensive tissue destruction along the bullet path. It is still unclear whether gelatin blocks, which are used as a well-accepted tissue simulant, allow the effects of projectiles to be adequately investigated and how these effects are influenced by caliber size. Method Barium titanate particles were distributed throughout a test chamber for an assessment of wound contamination. We fired .22-caliber Magnum bullets first into gelatin blocks and then into porcine hind limbs placed behind the chamber. Two other types of bullets (.222-caliber bullets and 6.5 × 57 mm cartridges) were then shot into porcine hind limbs. Permanent and temporary wound cavities as well as the spatial distribution of barium titanate particles in relation to the bullet path were evaluated radiologically. Results A comparison of the gelatin blocks and hind limbs showed significant differences (p < 0.05) in the mean results for all parameters. There were significant differences between the bullets of different calibers in the depth to which barium titanate particles penetrated the porcine hind limbs. Almost no particles, however, were found at a penetration depth of 10 cm or more. By contrast, gas cavities were detected along the entire bullet path. Conclusion Gelatin is only of limited value for evaluating the path of high-velocity projectiles and the contamination of wounds by exogenous particles. There is a direct relationship between the presence of gas cavities in the tissue along the bullet path and caliber size. These cavities, however, are only mildly contaminated by exogenous particles. PMID:22490236

Single-centre experience of radiation exposure in acute surgical patients: assessment of therapeutic impact and future recommendations.

PubMed

Fitzmaurice, Gerard J; Brown, Robin; Cranley, Brian; Conlon, Enda F; Todd, R Alan J; O'Donnell, Mark E

2010-09-01

Radiological investigations have become a key adjunct in patient management and consequently radiation exposure to patients is increasing. The study objectives were to examine the use of radiological investigations in the management of acute surgical patients and to assess whether a guideline-based radiation exposure risk/benefit analysis can aid in the choice of radiological investigation used. A prospective observational study was completed over a 12-week period from April to July 2008 for all acute surgical admissions. Data recorded included demographics, clinical presentation, differential diagnosis, investigations, surgical interventions, and final clinical outcome. The use of radiological investigative modalities as an adjunct to clinical assessment was then evaluated against The Royal College of Radiologists (RCR) guidelines. A total of 380 acute surgical admissions (M = 174, F = 185, children = 21) were assessed during the study period. Seven hundred thirty-four radiological investigations were performed with a mean of 1.93 investigations per patient. Based on the RCR guidelines, 680 (92.6%) radiological investigations were warranted and included 142 CT scans (19.3%), 129 chest X-rays (17.6%), and 85 abdominal X-rays (11.6%). Clinically, radiological imaging complemented surgical management in 326 patients (85.8%) and the management plan remained unchanged for the remaining 54 patients (14.2%). This accounted for an average radiation dose of 4.18 millisievert (mSv) per patient or 626 days of background radiation exposure. CT imaging was responsible for the majority of the radiation exposure, with a total of 1310 mSv (82.6%) of the total radiation exposure being attributed to CT imaging in 20.8% of acute admissions. Subgroup analysis demonstrated that 92.8% of the CT scans performed were appropriate. Radiation exposure was generally low for the majority of acute surgical admissions. However, it is recommended that CT imaging requests be evaluated carefully, particularly for patients with clinically confirmed pathologies and in younger women.

Bibliometric Analysis of Manuscript Characteristics That Influence Citations: A Comparison of Six Major Radiology Journals.

PubMed

Shekhani, Haris Naseem; Shariff, Shoaib; Bhulani, Nizar; Khosa, Faisal; Hanna, Tarek Noel

2017-12-01

The objective of our study was to investigate radiology manuscript characteristics that influence citation rate, capturing features of manuscript construction that are discrete from study design. Consecutive articles published from January 2004 to June 2004 were collected from the six major radiology journals with the highest impact factors: Radiology (impact factor, 5.076), Investigative Radiology (2.320), American Journal of Neuroradiology (AJNR) (2.384), RadioGraphics (2.494), European Radiology (2.364), and American Journal of Roentgenology (2.406). The citation count for these articles was retrieved from the Web of Science, and 29 article characteristics were tabulated manually. A point-biserial correlation, Spearman rank-order correlation, and multiple regression model were performed to predict citation number from the collected variables. A total of 703 articles-211 published in Radiology, 48 in Investigative Radiology, 106 in AJNR, 52 in RadioGraphics, 129 in European Radiology, and 157 in AJR-were evaluated. Punctuation was included in the title in 55% of the articles and had the highest statistically significant positive correlation to citation rate (point-biserial correlation coefficient [r pb ] = 0.85, p < 0.05). Open access status provided a low-magnitude, but significant, correlation to citation rate (r pb = 0.140, p < 0.001). The following variables created a significant multiple regression model to predict citation count (p < 0.005, R 2 = 0.186): study findings in the title, abstract word count, abstract character count, total number of words, country of origin, and all authors in the field of radiology. Using bibliometric knowledge, authors can craft a title, abstract, and text that may enhance visibility and citation count over what they would otherwise experience.

Evaluation of Calendar Year 1997 Groundwater and Surface Water Quality Data For The Upper East Fork Poplar Creek Hydrogeologic Regime At The U.S. Department of Energy Y-12 Plant, Oak Ridge, Tennessee

DOE Office of Scientific and Technical Information (OSTI.GOV)

Jones, S.B.

1998-09-01

1 1.0 INTRODUCTION This report presents an evaluation of the groundwater quality monitoring data reported in: Calendar Year 1997 Annual Groundwatw Monitoring Report for the Upper East Fork Poplar Creek Hydrogeologtc Rep-meat the US. Department of Energy Y-12 Plant, Oak Ridge, Tennessee (AJA Technical Services, Inc. 1998), which is hereafter referenced as the Annual Monitoring Report. Section 2.0 presents background information for the Upper East Fork Poplar Creek Hydrogeologic Regime (East Fork Regime) that is relevant to data evaluation, including brief descriptions of the geology, the groundwater flow system, the contaminant source areas, and the extent of groundwater contamination inmore » the regime. Section 3.0 provides an overview of the groundwater sampling and analysis activities petiormed during calendar year (CY) 1997, including monitoring well locations, sampling frequency and methods, and laboratory analyses. Evaluation and interpretation of the monitoring da% described in Section 4.0, is generally focused on an overview of data quality assurance/quality control (QA/QC), long-term concentration trends for selected inorganic, organic, and radiological contaminants, and consistency with applicable site-specific conceptual contaminant transport models described in: Report on the Remedial Investigation of the Upper East Fork Poplar Creek Characterization Area at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee (U.S. Department of Energy 1998), which is referenced hereafter as the Remedial Investigation @I) Report. Findings of the data evaluations are summarized :in Section 5.0 and a list of technical reports and regulatory documents cited for more detailed irdormation (Section 6.0) concludes the report. All of the illustrations (maps and trend graphs) and data summary tables referenced in the text are presented in Appendm A and Appendix B, respectively. Appendix C provides a summary of the analytical results that meet applicable data quality objectives (DQOS) of the Y-12 Plant Groundwater Protection Program.« less

Microbiological contamination in digital radiography: evaluation at the radiology clinic of an educational institution.

PubMed

Malta, Cristiana P; Damasceno, Naiana Nl; Ribeiro, Rosangela A; Silva, Carolina Sf; Devito, Karina L

2016-12-01

The aim of this study was to evaluate the contamination rate of intra and extraoral digital X ray equipment in a dental radiology clinic at a public educational institution. Samples were collected on three different days, at two times in the day: in the morning, before attending patients, and at the end of the day, after appointment hours and before cleaning and disinfection procedures. Samples were collected from the periapical X-ray machine (tube head, positioning device, control panel and activator button), the panoramic X- ray machine (temporal support, bite block, control panel and activator button), the intraoral digital system (sensor), and the digital system computers (keyboard and mouse). The samples were seeded in different culture media, incubated, and colony forming units (CFU/mL) counted. Biochemical tests were performed for suspected colonies of Staphylococcus, Streptococcus and Gramnegative bacilli (GNB). Fungi were visually differentiated into filamentous fungi and yeasts. The results indicated the growth of fungi and Staphylococcus fromall sampling locations. GNB growth was observed from all sites sampled from the intraoral X-ray equipment. On the panoramic unit, GNB growth was observed in samples from activator button, keyboard and mouse. In general, a higher number of CFU/mL was present before use. It can be concluded that more stringent protocols are needed to control infection and prevent X-ray exams from acting as vehicle for cross contamination. Sociedad Argentina de Investigación Odontológica.

[Interventional Radiology for Intra-Abdominal Abscess after Gastrectomy].

PubMed

Matsuura, Norihiro; Fujitani, Kazumasa; Kawada, Junji; Nishikawa, Kazuhiro; Nakatsuka, Rie; Miyazaki, Susumu; Danno, Katsuki; Motoori, Masaaki; Kubota, Masaru; Matsuda, Chu; Yoshida, Hiroshi; Iwase, Kazuhiro; Tanaka, Yasuhiro

2015-11-01

Approximately 20% of patients develop some complications after gastrectomy. These complications should be treated appropriately to achieve a positive outcome. The records of 6 patients with postoperative intra-abdominal abscesses treated with interventional radiology (IVR) were analyzed. The cause of abscess was anastomotic leakage in 4 patients and contaminated surgery after gastric perforation in 2 patients. Intra-abdominal abscesses were detected on postoperative day 12 (median), and an IVR-guided drainage tube was inserted with a median interval of 1 day. The drainage tube was kept in place for 26 days (median), and patients were discharged 6.5 days (median) after drainage tube removal. No patients were converted to open surgery. Early IVR-guided drainage was essential and effective for intra-abdominal abscess treatment after gastrectomy.

Health Aspects of a Nuclear or Radiological Attack

DTIC Science & Technology

2010-07-01

treatment capabilities, population monitoring, decontamination, and so on. The requirements should be developed by a process that engages stakeholders...IND or reactor accident would release radioiodine that could result in hypothyroidism or late thyroid nodules or cancer. External contamination... Treatment and Long-Term Monitoring Victims of acute radiation-related events will require prompt diagnosis and treatment of emergency medical and

Decontamination Equipment Standards Workshop for Civilian First Responders

DTIC Science & Technology

2009-12-01

Hazardous Materials Decontamination Radiological Survey Nuclear Chemical 16. SECURITY CLASSIFICATION OF: a. REPORT u b. ABSTRACT u c. THIS...Washington, DC) sponsored the production of this material under an Interagency Agreement with the National Institute of Standards and Technology...responders currently use wet decontamination (i.e., soap and water) to remove contamination from personnel, the standard will not be specific to the

Medical radiation countermeasures for nuclear and radiological emergencies: Current status and future perspectives

PubMed Central

Arora, Rajesh; Chawla, Raman; Marwah, Rohit; Kumar, Vinod; Goel, Rajeev; Arora, Preeti; Jaiswal, Sarita; Sharma, Rakesh Kumar

2010-01-01

Nuclear and radiological emergencies (NREs) occurred globally and recent incidences in India are indicating toward the need for comprehensive medical preparedness required both at incident site and hospitals. The enhanced threat attributed toward insurgency is another causative factor of worry. The response capabilities and operational readiness of responders (both health and non-health service providers) in contaminated environment need to be supported by advancement in R & D and technological efforts to develop prophylactics and radiation mitigators. It is essential to develop phase 1 alternatives of such drugs for unseen threats as a part of initial preparedness. At the incident site and hospital level, external decontamination procedures need to be standardized and supported by protective clothing and Shudika kits developed by INMAS. The medical management of exposure requires systematic approach to perform triage, resuscitation and curative care. The internal contamination requires decorporation agents to be administered based on procedural diagnostics. Various key issues pertaining to policy decisions, R & D promotion, community awareness, specialized infrastructure for NREs preparedness has been discussed. The present review is an attempt to provide vital information about the current status of various radiation countermeasures and future perspective(s) ahead. PMID:21829316

A series of low-altitude aerial radiological surveys of selected regions within Areas 3, 5, 8, 9, 11, 18, and 25 at the Nevada Test Site

DOE Office of Scientific and Technical Information (OSTI.GOV)

Colton, D.P.

1999-12-01

A series of low-altitude, aerial radiological surveys of selected regions within Areas 3, 5, 8, 9, 11, 18,and 25 of the Nevada Test Site was conducted from December 1996 through June 1999. The surveys were conducted for the US Department of Energy by the Remote Sensing Laboratory, located in Las Vegas, Nevada, and maintained and operated by Bechtel Nevada. The flights were conducted at a nominal altitude of 15 meters above ground level along a set of parallel flight lines spaced 23 meters apart. The purpose of these low-altitude surveys was to measure, map, and define the areas of americium-241more » activity. The americium contamination will be used to determine the areas of plutonium contamination. Americium-241 activity was detected within 8 of the 11 regions. The three regions where americium-241 was not detected were in the inactive Nuclear Rocket Development Station complex in Area 25, which encompassed the Test Cell A and Test Cell C reactor test stands and the Reactor Maintenance Assembly and Disassembly facility.« less

Optimisation of nasal swab analysis by liquid scintillation counting.

PubMed

Dai, Xiongxin; Liblong, Aaron; Kramer-Tremblay, Sheila; Priest, Nicholas; Li, Chunsheng

2012-06-01

When responding to an emergency radiological incident, rapid methods are needed to provide the physicians and radiation protection personnel with an early estimation of possible internal dose resulting from the inhalation of radionuclides. This information is needed so that appropriate medical treatment and radiological protection control procedures can be implemented. Nasal swab analysis, which employs swabs swiped inside a nostril followed by liquid scintillation counting of alpha and beta activity on the swab, could provide valuable information to quickly identify contamination of the affected population. In this study, various parameters (such as alpha/beta discrimination, swab materials, counting time and volume of scintillation cocktail etc) were evaluated in order to optimise the effectiveness of the nasal swab analysis method. An improved nasal swab procedure was developed by replacing cotton swabs with polyurethane-tipped swabs. Liquid scintillation counting was performed using a Hidex 300SL counter with alpha/beta pulse shape discrimination capability. Results show that the new method is more reliable than existing methods using cotton swabs and effectively meets the analysis requirements for screening personnel in an emergency situation. This swab analysis procedure is also applicable to wipe tests of surface contamination to minimise the source self-absorption effect on liquid scintillation counting.

Potential radiological impact of tornadoes on the safety of Nuclear Fuel Services' West Valley Fuel Reprocessing Plant. Volume I. Tornado effects on head-end cell airflow

DOE Office of Scientific and Technical Information (OSTI.GOV)

Holloway, L.J.; Andrae, R.W.

1981-09-01

This report describes results of a parametric study of the impacts of a tornado-generated depressurization on airflow in the contaminated process cells within the presently inoperative Nuclear Fuel Services fuel reprocessing facility near West Valley, NY. The study involved the following tasks: (1) mathematical modeling of installed ventilation and abnormal exhaust pathways from the cells and prediction of tornado-induced airflows in these pathways; (2) mathematical modeling of individual cell flow characteristics and prediction of in-cell velocities induced by flows from step 1; and (3) evaluation of the results of steps 1 and 2 to determine whether any of the pathwaysmore » investigated have the potential for releasing quantities of radioactively contaminated air from the main process cells. The study has concluded that in the event of a tornado strike, certain pathways from the cells have the potential to release radioactive materials of the atmosphere. Determination of the quantities of radioactive material released from the cells through pathways identified in step 3 is presented in Part II of this report.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Farina, R.; Brandao-Mello, C.E.; Oliveira, A.R.

In September 1987, the Goiania radiological accident involving a source of {sup 137}Cs culminated in about 140 victims who presented internal and/or external contamination and/or external exposure to radiation and/or radiation burns. Internal contamination was verified through analysis of urine and fecal samples. Internal contamination was also evaluated by measurements performed at the whole-body counter installed in Goiania in November 1987. To enhance the decorporation of 137Cs, patients were treated with the following: (1) Prussian Blue, oral administration, in 46 patients; (2) diuretics, oral administration, in 17 patients; (3) induced perspiration, increasing {sup 137}Cs elimination. These procedures were done undermore » rigorous clinical evaluation and considering the data from assay of excreta and data obtained from the whole-body counter. The doses of Prussian Blue exceeded about 6.5 times the dose previously indicated in the literature. It was the first time diuretics were used in humans to treat {sup 137}Cs internal contamination. The results of these procedures are discussed.« less

Some reflections on the role of the Scientific Advisory Panel to the Marshall Islands nationwide radiological study.

PubMed

McEwan, A C; Simon, S L; Baverstock, K F; Trott, K R; Sankaranarayanan, K; Paretzke, H G

1997-07-01

As a consequence of the U.S. Atomic Weapons Testing Program in the Trust Territory of the Pacific, now the Republic of the Marshall Islands, numerous scientists have advised the Marshallese on matters of radiation and radioactive contamination. Some of the previous advice has appeared to vary or conflict resulting in consequent uncertainty for the people. In a new initiative in 1989, the RMI Government engaged a five member multi-disciplinary Scientific Advisory Panel to oversee the assessment of, and to advise on, the radiological status of the entire nation. The formation of the Panel was accompanied by the establishment of a Resident Scientist position, and ultimately a small scientific team and laboratory on Majuro. The nationwide radiological study was conducted using ground survey methods over the period 1990-1994. Tasks undertaken by the Panel included formulating reasonable objectives for the study and attempting to establish effective communication and understanding of issues with political leaders and RMI Government agencies and people, as well as advising on and monitoring the scientific integrity of the study itself. The attempt was also made to initiate investigations to address matters of concern that emerged. The problem was faced of providing not only technical guidance on radioactivity and radiation measurements, but also explaining the significance of measured values and concepts, such as risk and probability of health effects to a diverse but nontechnical audience, generally across cultural and language barriers. The experience of the Panel in providing advice and guidance to the Republic of the Marshall Islands, while unique in many ways, parallels the difficulties experienced elsewhere in communicating information about risks from radiation exposure.

The Patroon Creek Contamination Migration Investigation

DOE Office of Scientific and Technical Information (OSTI.GOV)

Dufek, K.; Zafran, A.; Moore, J.T.

2006-07-01

Shaw performed a Site Investigation (SI) for sediment within the Unnamed Tributary of the Patroon Creek, a section of the Patroon Creek, and the Three Mile Reservoir as part of the overall contract with the United States Army Corps of Engineers (USACE) to remediate the Colonie Formerly Utilized Sites Remedial Action Program (FUSRAP) Site. The Unnamed Tributary formerly flowed through the former Patroon Lake, which was located on the main site property and was used as a landfill for radiological and chemical wastes. The objective of the investigation was to determine the absence/presence of radioactive contamination within the three Areasmore » of Concern (AOC). In order to accomplish this objective, Shaw assembled a team to produce a Technical Memorandum that provided an in-depth understanding of the environmental conditions related to the Patroon Creek. Upon completion and analysis of the Technical Memorandum, a Conceptual Site Model (CSM) was constructed and a Technical Planning Program (TPP) was held to develop a Sediment Investigation Work Plan and Sediment Investigation Sampling and Analysis Plan. A total of 32 sample locations were analyzed using on-site direct gamma scans with a Pancake Geiger-Mueller (PGM) instrument for screening purposes and samples were analyzed at on-site and off-site laboratories. The highest interval from each core scan was selected for on-site analysis utilizing a High Purity Germanium (HPGe) detector. Eight of these samples were sent off-site for gamma/alpha spectroscopy confirmation. The data collected during the SI indicated that the U-238 cleanup criterion was exceeded in sediment samples collected from two locations within the Unnamed Tributary but not in downstream sections of Patroon Creek or Three Mile Reservoir. Future actions for impacted sediment in the Unnamed Tributary will be further evaluated. Concentrations of U-238 and Th-232 in all other off-site sediment samples collected from the Unnamed Tributary, Patroon Creek, and the Three Mile Reservoir indicate that no further action is required in these areas. The data was also compared to ecological screening criteria. None of the contaminants of concern (U-238, Th-232, and U-235) had concentrations exceeding the screening values. The evaluation indicates no adverse impacts to ecological receptors. (authors)« less

NCRP Program Area Committee 2: Operational Radiation Safety

DOE Office of Scientific and Technical Information (OSTI.GOV)

Pryor, Kathryn H.; Goldin, Eric M.

2016-02-29

Program Area Committee 2 of the National Council on Radiation Protection and Measurements provides guidance for radiation safety in occupational settings in a variety of industries and activities. The committee completed three reports in recent years covering recommendations for the development and administration of radiation safety programs for smaller educational institutions, requirements for self-assessment programs that improve radiation safety and identify and correct deficiencies, and a comprehensive process for effective investigation of radiological incidents. Ongoing work includes a report on sealed radioactive source controls and oversight of a report on radioactive nanomaterials focusing on gaps within current radiation safety programs.more » Future efforts may deal with operational radiation safety programs in fields such as the safe use of handheld and portable X-Ray fluorescence analyzers, occupational airborne radioactive contamination, unsealed radioactive sources, or industrial accelerators.« less

DISPOSITION PATHS FOR ROCKY FLATS GLOVEBOXES: EVALUATING OPTIONS

DOE Office of Scientific and Technical Information (OSTI.GOV)

Lobdell, D.; Geimer, R.; Larsen, P.

2003-02-27

The Kaiser-Hill Company, LLC has the responsibility for closure activities at the Rocky Flats Environmental Technology Site (RFETS). One of the challenges faced for closure is the disposition of radiologically contaminated gloveboxes. Evaluation of the disposition options for gloveboxes included a detailed analysis of available treatment capabilities, disposal facilities, and lifecycle costs. The Kaiser-Hill Company, LLC followed several processes in determining how the gloveboxes would be managed for disposition. Currently, multiple disposition paths have been chosen to accommodate the needs of the varying styles and conditions of the gloveboxes, meet the needs of the decommissioning team, and to best managemore » lifecycle costs. Several challenges associated with developing a disposition path that addresses both the radiological and RCRA concerns as well as offering the most cost-effective solution were encountered. These challenges included meeting the radiological waste acceptance criteria of available disposal facilities, making a RCRA determination, evaluating treatment options and costs, addressing void requirements associated with disposal, and identifying packaging and transportation options. The varying disposal facility requirements affected disposition choices. Facility conditions that impacted decisions included radiological and chemical waste acceptance criteria, physical requirements, and measurement for payment options. The facility requirements also impacted onsite activities including management strategies, decontamination activities, and life-cycle cost.« less

Final report: survey and removal of radioactive surface contamination at environmental restoration sites, Sandia National Laboratories/New Mexico. Volume 2

DOE Office of Scientific and Technical Information (OSTI.GOV)

Lambert, K.A.; Mitchell, M.M.; Jean, D.

1997-09-01

This report contains the Appendices A-L including Voluntary Corrective Measure Plans, Waste Management Plans, Task-Specific Health and Safety Plan, Analytical Laboratory Procedures, Soil Sample Results, In-Situ Gamma Spectroscopy Results, Radionuclide Activity Summary, TCLP Soil Sample Results, Waste Characterization Memoranda, Waste Drum Inventory Data, Radiological Risk Assessment, and Summary of Site-Specific Recommendations.

Chemical, Biological, and Radiological Contamination Survivability: Material Effects Testing

DTIC Science & Technology

2012-06-22

form that can be compared to pretest and posttest functional performance data. If Soldiers are desired, ensure a Test Schedule and Review Committee...test execution. f. The material’s performance specification should also be reviewed before planning test execution. For example , the...test data, and conformance with specified test and operating procedures cannot be overemphasized. 3.1 Test Planning. 3.1.1 Pretest Preparation

Status of the waste assay for nonradioactive disposal (WAND) project

NASA Astrophysics Data System (ADS)

Arnone, Gaetano L.; Foster, Lynn A.; Foxx, Charles L.; Hagan, Roland C.; Martin, E. R.; Myers, Steven C.; Parker, Jack L.

1999-01-01

The WAND (Waste Assay for Nonradioactive Disposal) system scans thought-to-be-clean, low-density waste (mostly paper and plastics) to verify the absence of radioactive contaminants at very low-levels. Much of the low-density waste generated in radiologically controlled areas, formally considered `suspect' radioactive, is now disposed more cheaply at the Los Alamos County Landfill as opposed to the LANL Radioactive Waste Landfill.

Medical Management of Radiological Casualties. Online Third Edition

DTIC Science & Technology

2010-06-01

contaminated should be surveyed before entering and responders should be advised to limit their time in high dose-rate areas. There is generally no hazard...early oral enteral feeding when feasible. • Povidone-iodine or chlorhexidine for skin disinfection and shampoo . Meticulous oral hygiene. Clinical...signs, normal primary and second survey , but has vomited repeatedly, beginning approximately 2 hours post-event. Solution. Using the simple scoring

Dynamic Modeling of the Economic Impacts of a Terrorist Attack using a Radiological Dispersion Device

DTIC Science & Technology

2009-03-01

Coverage to Loss Ratio Increasing Indiv idual Losses f rom Contamination Daining Recovery Decreasing Losses Through Community Recov ery Community...Localized Stimulus Plan Switch Noname 1 Daining Recov ery Converter Business Loss Structure 64 were never directly refunded by federal...Incentiv es Revitalization Plan Legislative Financial Backing of Localized Stimulus Plan Switch Daining Recovery Converter Tax Rev enue Loss Structure

Health risks resulting from contaminants transfers in soil-plants systems: case study of Atrazine in Lactuca sativa.

NASA Astrophysics Data System (ADS)

Mathieu, Camoin

2015-04-01

Food safety is presently at the center of great part of scientific and political debates. This represents a field of study in its own right of health risks, including ingestion by humans of hazardous biological, physical, chemical or radiological substances, from contaminated foods during different stages of production. Plant cultivation step is often one of the main sources of contamination, whether of voluntary (pesticide application) or accidental (nuclear, industrial waste, etc.) origin. As a result, the plants growth in an contaminated environment may increase the risk of transfer within the plant, and finally the exposure of humans. Furthermore, pesticides are among the main contaminants investigated in the frame of human health risks resulting from food intakes. However, most of these scientific works focus mainly on their occurrence and persistence in water bodies, and few of them are interested in soil/plants transfer. In this context, the understanding of the processes governing transfers of pesticides in plants is become a necessity, in particular to prevent human risks linked the ingestion of food produced in contaminated environments. This objective can be reached by studying the pollutants behavior in soils/plants transfers, and using various substances/plants couples. In our study, we selected a salad/pesticide couple as our experimental model. Atrazine was chosen as model contaminant because of its problematic presence in a large amount of environmental compartments, its physico-chemical properties and because of its long-term toxicity. Lactuca sativa has been selected as model plant because of its importance in French agriculture, and specifically in Languedoc-Roussillon. Salad has been cultivated in peats and irrigated with an atrazine spiked water solution (concentrations from 10 to 100 μg/L). Plant growth in such conditions has been compared to a growth in clean condition (irrigation with non spiked water). Measurements of atrazine contents in different parts of the plant were performed by HPLC-MS after a specific extraction pretreatment. At the same time, atrazine evolution in soil has been also determined by chemical analyses after soil sampling all along the salad's development, and extraction by soxhlet.

Analysis of environmental contamination resulting from catastrophic incidents: part 2. Building laboratory capability by selecting and developing analytical methodologies.

PubMed

Magnuson, Matthew; Campisano, Romy; Griggs, John; Fitz-James, Schatzi; Hall, Kathy; Mapp, Latisha; Mullins, Marissa; Nichols, Tonya; Shah, Sanjiv; Silvestri, Erin; Smith, Terry; Willison, Stuart; Ernst, Hiba

2014-11-01

Catastrophic incidents can generate a large number of samples of analytically diverse types, including forensic, clinical, environmental, food, and others. Environmental samples include water, wastewater, soil, air, urban building and infrastructure materials, and surface residue. Such samples may arise not only from contamination from the incident but also from the multitude of activities surrounding the response to the incident, including decontamination. This document summarizes a range of activities to help build laboratory capability in preparation for sample analysis following a catastrophic incident, including selection and development of fit-for-purpose analytical methods for chemical, biological, and radiological contaminants. Fit-for-purpose methods are those which have been selected to meet project specific data quality objectives. For example, methods could be fit for screening contamination in the early phases of investigation of contamination incidents because they are rapid and easily implemented, but those same methods may not be fit for the purpose of remediating the environment to acceptable levels when a more sensitive method is required. While the exact data quality objectives defining fitness-for-purpose can vary with each incident, a governing principle of the method selection and development process for environmental remediation and recovery is based on achieving high throughput while maintaining high quality analytical results. This paper illustrates the result of applying this principle, in the form of a compendium of analytical methods for contaminants of interest. The compendium is based on experience with actual incidents, where appropriate and available. This paper also discusses efforts aimed at adaptation of existing methods to increase fitness-for-purpose and development of innovative methods when necessary. The contaminants of interest are primarily those potentially released through catastrophes resulting from malicious activity. However, the same techniques discussed could also have application to catastrophes resulting from other incidents, such as natural disasters or industrial accidents. Further, the high sample throughput enabled by the techniques discussed could be employed for conventional environmental studies and compliance monitoring, potentially decreasing costs and/or increasing the quantity of data available to decision-makers. Published by Elsevier Ltd.

[The application of radiological image in forensic medicine].

PubMed

Zhang, Ji-Zong; Che, Hong-Min; Xu, Li-Xiang

2006-04-01

Personal identification is an important work in forensic investigation included sex discrimination, age and stature estimation. Human identification depended on radiological image technique analysis is a practice and proper method in forensic science field. This paper intended to understand the advantage and defect by reviewed the employing of forensic radiology in forensic science field broadly and provide a reference to perfect the application of forensic radiology in forensic science field.

Actinide-contaminated Skin: Comparing Decontamination Efficacy of Water, Cleansing Gels, and DTPA Gels.

PubMed

Tazrart, A; Bolzinger, M A; Lamart, S; Coudert, S; Angulo, J F; Jandard, V; Briançon, S; Griffiths, N M

2018-07-01

Skin contamination by alpha-emitting actinides is a risk to workers during nuclear fuel production and reactor decommissioning. Also, the list of items for potential use in radiological dispersal devices includes plutonium and americium. The actinide chemical form is important and solvents such as tributyl phosphate, used to extract plutonium, can influence plutonium behavior. This study investigated skin fixation and efficacy of decontamination products for these actinide forms using viable pig skin in the Franz cell diffusion system. Commonly used or recommended decontamination products such as water, cleansing gel, diethylenetriamine pentaacetic acid, or octadentate hydroxypyridinone compound 3,4,3-LI(1,2-HOPO), as well as diethylenetriamine pentaacetic acid hydrogel formulations, were tested after a 2-h contact time with the contaminant. Analysis of skin samples demonstrated that more plutonium nitrate is bound to skin as compared to plutonium-tributyl phosphate, and fixation of americium to skin was also significant. The data show that for plutonium-tributyl phosphate all the products are effective ranging from 80 to 90% removal of this contaminant. This may be associated with damage to the skin by this complex and suggests a mechanical/wash-out action rather than chelation. For removal of americium and plutonium, both Trait Rouge cleansing gel and diethylenetriamine pentaacetic acid are better than water, and diethylenetriamine pentaacetic acid hydrogel is better than Osmogel. The different treatments, however, did not significantly affect the activity in deeper skin layers, which suggests a need for further improvement of decontamination procedures. The new diethylenetriamine pentaacetic acid hydrogel preparation was effective in removing americium, plutonium, and plutonium-tributyl phosphate from skin; such a formulation offers advantages and thus merits further assessment.

Use of DandD for dose assessment under NRC`s radiological criteria for license termination rule

DOE Office of Scientific and Technical Information (OSTI.GOV)

Gallegos, D.P.; Brown, T.J.; Davis, P.A.

The Decontamination and Decommissioning (DandD) software package has been developed by Sandia National Laboratories for the Nuclear Regulatory Commission (NRC) specifically for the purpose of providing a user-friendly analytical tool to address the dose criteria contained in NRC`s Radiological Criteria for License Termination rule (10 CFR Part 20 Subpart E; NRC, 1997). Specifically, DandD embodies the NRC`s screening methodology to allow licensees to convert residual radioactivity contamination levels at their site to annual dose, in a manner consistent with both 10 CFR Part 20 and the corresponding implementation guidance developed by NRC. The screening methodology employs reasonably conservative scenarios, fatemore » and transport models, and default parameter values that have been developed to allow the NRC to quantitatively estimate the risk of releasing a site given only information about the level of contamination. Therefore, a licensee has the option of specifying only the level of contamination and running the code with the default parameter values, or in the case where site specific information is available to alter the appropriate parameter values and then calculate dose. DandD can evaluate dose for fur different scenarios: residential, building occupancy, building renovation, or drinking water. The screening methodology and DandD are part of a larger decision framework that allows and encourages licensees to optimize decisions on choice of alternative actions at their site, including collection of additional data and information. This decision framework is integrated into and documented in NRC`s technical guidance for decommissioning.« less

Fatal and nonfatal risk associated with recycle of D&D-generated concrete

DOE Office of Scientific and Technical Information (OSTI.GOV)

Boren, J.K.; Ayers, K.W.; Parker, F.L.

1997-02-01

As decontamination and decommissioning activities proceed within the U.S. Department of Energy Complex, vast volumes of uncontaminated and contaminated concrete will be generated. The current practice of decontaminating and landfilling the concrete is an expensive and potentially wasteful practice. Research is being conducted at Vanderbilt University to assess the economic, social, legal, and political ramifications of alternate methods of dealing with waste concrete. An important aspect of this research work is the assessment of risk associated with the various alternatives. A deterministic risk assessment model has been developed which quantifies radiological as well as non-radiological risks associated with concrete disposalmore » and recycle activities. The risk model accounts for fatal as well as non-fatal risks to both workers and the public. Preliminary results indicate that recycling of concrete presents potentially lower risks than the current practice. Radiological considerations are shown to be of minor importance in comparison to other sources of risk, with conventional transportation fatalities and injuries dominating. Onsite activities can also be a major contributor to non-fatal risk.« less

An aerial radiological survey of the Evans Area, US Army Communications-Electronics Command, Fort Monmouth, New Jersey

DOE Office of Scientific and Technical Information (OSTI.GOV)

Maurer, R.J.

1989-12-01

An aerial radiological survey was conducted over the Evans Area, US Army Communications-Electronics Command, Fort Monmouth, New Jersey, during the period November 14--18, 1988. The purposes of the survey were to document the terrestrial gamma environment of the Evans site and surrounding area and to determine if there had been any radiological impact on the area due to past laboratory operations. The results of the aerial survey are reported as inferred radiation exposure rates at 1 meter above ground level in the form of a contour map. The aerial data were compared to ground-based benchmark'' exposure rate measurements and radionuclidemore » assay of soil samples obtained at sites outside the survey perimeter. Similar ground-based measurements were also made at several locations on the Evans site and at the bank of the Shark River bordering the Evans Area. No evidence for contamination was identified by either radionuclide assay of soil samples or the aerial survey. 6 refs., 5 figs., 2 tabs.« less

GrayQb TM Single-Faced Version 2 (SF2) Hanford Plutonium Reclamation Facility (PRF) deployment report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Plummer, J. R.; Immel, D. M.; Serrato, M. G.

2015-11-18

The Savannah River National Laboratory (SRNL) in partnership with CH2M Plateau Remediation Company (CHPRC) deployed the GrayQb TM SF2 radiation imaging device at the Hanford Plutonium Reclamation Facility (PRF) to assist in the radiological characterization of the canyon. The deployment goal was to locate radiological contamination hot spots in the PRF canyon, where pencil tanks were removed and decontamination/debris removal operations are on-going, to support the CHPRC facility decontamination and decommissioning (D&D) effort. The PRF canyon D&D effort supports completion of the CHPRC Plutonium Finishing Plant Decommissioning Project. The GrayQb TM SF2 (Single Faced Version 2) is a non-destructive examinationmore » device developed by SRNL to generate radiation contour maps showing source locations and relative radiological levels present in the area under examination. The Hanford PRF GrayQbTM Deployment was sponsored by CH2M Plateau Remediation Company (CHPRC) through the DOE Richland Operations Office, Inter-Entity Work Order (IEWO), DOE-RL IEWO- M0SR900210.« less

Characterization Report for the David Witherspoon Screen Art Site

DOE Office of Scientific and Technical Information (OSTI.GOV)

Phyllis C. Weaver

The U.S. Department of Energy (DOE) Oak Ridge Office (ORO) of Environmental Management (EM) requested the technical assistance of Oak Ridge Institute for Science and Education (ORISE) to characterize a tract of land associated with the David Witherspoon, Incorporated (DWI) Volunteer Equipment and Supply Company (VESC). This tract of land (hereinafter referred to as Screen Arts) is located in the Vestal Community in the 2000-block of Maryville Pike in south Knoxville, Tennessee, as shown in Figure A-1. This tract of land has been used primarily to store salvaged equipment and materials for resale, recycle, or for disposal in the formermore » landfill once operated by DWI. The DWI Site industrial landfill and metal recycling business had been permitted by the Tennessee Division of Radiological Health to accept low-level radiologically contaminated metals. DWI received materials and equipment associated with operations from DOE sites, including those in Oak Ridge, Tennessee; Paducah, Kentucky; and Portsmouth, Ohio. It is likely that items stored at Screen Arts may have contained some residual radiological materials.« less

Radionuclide Retention in Concrete Wasteforms

DOE Office of Scientific and Technical Information (OSTI.GOV)

Bovaird, Chase C.; Jansik, Danielle P.; Wellman, Dawn M.

2011-09-30

Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation); the mechanism of contaminant release; the significance of contaminant release pathways; how wasteform performance is affected by the full range of environmental conditions within the disposal facility; the process of wasteform aging under conditions that are representative of processes occurring in response to changing environmental conditions within the disposal facility; the effect of wasteform aging on chemical, physical, and radiological properties; and the associated impact on contaminant release. This knowledge will enable accurate predictionmore » of radionuclide fate when the wasteforms come in contact with groundwater. The information present in the report provides data that (1) measures the effect of concrete wasteform properties likely to influence radionuclide migration; and (2) quantifies the rate of carbonation of concrete materials in a simulated vadose zone repository.« less

Use of a CO{sub 2} pellet non-destructive cleaning system to decontaminate radiological waste and equipment in shielded hot cells at the Bettis Atomic Power Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

Bench, T.R.

1997-05-01

This paper details how the Bettis Atomic Power Laboratory modified and utilized a commercially available, solid carbon dioxide (CO{sub 2}) pellet, non-destructive cleaning system to support the disposition and disposal of radioactive waste from shielded hot cells. Some waste materials and equipment accumulated in the shielded hot cells cannot be disposed directly because they are contaminated with transuranic materials (elements with atomic numbers greater than that of uranium) above waste disposal site regulatory limits. A commercially available CO{sub 2} pellet non-destructive cleaning system was extensively modified for remote operation inside a shielded hot cell to remove the transuranic contaminants frommore » the waste and equipment without generating any secondary waste in the process. The removed transuranic contaminants are simultaneously captured, consolidated, and retained for later disposal at a transuranic waste facility.« less

Verification of screening level for decontamination implemented after Fukushima nuclear accident

PubMed Central

Ogino, Haruyuki; Ichiji, Takeshi; Hattori, Takatoshi

2012-01-01

The screening level for decontamination that has been applied for the surface of the human body and contaminated handled objects after the Fukushima nuclear accident was verified by assessing the doses that arise from external irradiation, ingestion, inhalation and skin contamination. The result shows that the annual effective dose that arises from handled objects contaminated with the screening level for decontamination (i.e. 100 000 counts per minute) is <1 mSv y−1, which can be considered as the intervention exemption level in accordance with the International Commission on Radiological Protection recommendations. Furthermore, the screening level is also found to protect the skin from the incidence of a deterministic effect because the absorbed dose of the skin that arises from direct deposition on the surface of the human body is calculated to be lower than the threshold of the deterministic effect assuming a practical exposure duration. PMID:22228683

Challenges in disposing of anthrax waste.

PubMed

Lesperance, Ann M; Stein, Steve; Upton, Jaki F; Toomey, Chris

2011-09-01

Disasters often create large amounts of waste that must be managed as part of both immediate response and long-term recovery. While many federal, state, and local agencies have debris management plans, these plans often do not address chemical, biological, and radiological contamination. The Interagency Biological Restoration Demonstration's (IBRD) purpose was to holistically assess all aspects of an anthrax incident and assist in the development of a plan for long-term recovery. In the case of wide-area anthrax contamination and the follow-on response and recovery activities, a significant amount of material would require decontamination and disposal. Accordingly, IBRD facilitated the development of debris management plans to address contaminated waste through a series of interviews and workshops with local, state, and federal representatives. The outcome of these discussions was the identification of 3 primary topical areas that must be addressed: planning, unresolved research questions, and resolving regulatory issues.

Challenges in Disposing of Anthrax Waste

DOE Office of Scientific and Technical Information (OSTI.GOV)

Lesperance, Ann M.; Stein, Steven L.; Upton, Jaki F.

2011-09-01

Disasters often create large amounts of waste that must be managed as part of both immediate response and long-term recovery. While many federal, state, and local agencies have debris management plans, these plans often do not address chemical, biological, and radiological contamination. The Interagency Biological Restoration Demonstration’s (IBRD) purpose was to holistically assess all aspects of an anthrax incident and assist the development of a plan for long-term recovery. In the case of wide-area anthrax contamination and the follow-on response and recovery activities, a significant amount of material will require decontamination and disposal. Accordingly, IBRD facilitated the development of debrismore » management plans to address contaminated waste through a series of interviews and workshops with local, state, and federal representatives. The outcome of these discussion was the identification of three primary topical areas that must be addressed: 1) Planning; 2) Unresolved research questions, and resolving regulatory issues.« less

Validation of the Proficiency Examination for Diagnostic Radiologic Technology. Final Report.

ERIC Educational Resources Information Center

Educational Testing Service, Princeton, NJ.

The validity of the Proficiency Examination for Diagnostic Radiologic Technology was investigated, using 140 radiologic technologists who took both the written Proficiency Examination and a performance test. As an additional criterion measure of job proficiency, supervisors' assessments were obtained for 128 of the technologists. The resulting…

FORENSIC RADIOLOGY AND IMAGING FOR VETERINARY RADIOLOGISTS.

PubMed

Watson, Elizabeth; Heng, Hock Gan

2017-05-01

Imaging studies are often of evidentiary value in medicolegal investigations involving animals and the role of the veterinary radiologist is to interpret those images for courts as an expert or opinion witness. With progressing interest in prosecuting animal crimes and strengthening of penalties for crimes against animals, the participation of veterinary radiologists in medicolegal investigations is expected to increase. Veterinary radiologists who are aware of radiographic and imaging signs that result in animal suffering, abuse, or neglect; knowledgeable in ways radiology and imaging may support cause of death determinations; conversant in postmortem imaging; comfortable discussing mechanisms and timing of blunt or sharp force and projectile trauma in imaging; and prepared to identify mimics of abuse can assist court participants in understanding imaging evidence. The goal of this commentary review is to familiarize veterinary radiologists with the forensic radiology and imaging literature and with the advantages and disadvantages of various imaging modalities utilized in forensic investigations. Another goal is to provide background information for future research studies in veterinary forensic radiology and imaging. © 2017 American College of Veterinary Radiology.

Independent Verification Survey of the Clean Coral Storage Pile at the Johnston Atoll Plutonium-Contaminated Soil Remediation Project

DOE Office of Scientific and Technical Information (OSTI.GOV)

Wilson-Nichols, M.J.

2000-12-07

The Oak Ridge National Laboratory (ORNL) Environmental Technology Section conducted an independent verification (IV) survey of the clean storage pile at the Johnston Atoll Plutonium Contaminated Soil Remediation Project (JAPCSRP) from January 18-25, 1999. The goal of the JAPCSRP is to restore a 24-acre area that was contaminated with plutonium oxide particles during nuclear testing in the 1960s. The selected remedy was a soil sorting operation that combined radiological measurements and mining processes to identify and sequester plutonium-contaminated soil. The soil sorter operated from about 1990 to 1998. The remaining clean soil is stored on-site for planned beneficial use onmore » Johnston Island. The clean storage pile currently consists of approximately 120,000 m{sup 3} of coral. ORNL conducted the survey according to a Sampling and Analysis Plan, which proposed to provide an IV of the clean pile by collecting a minimum number (99) of samples. The goal was to ascertain with 95% confidence whether 97% of the processed soil is less than or equal to the accepted guideline (500-Bq/kg or 13.5-pCi/g) total transuranic (TRU) activity. In previous IV tasks, ORNL has (1) evaluated and tested the soil sorter system software and hardware and (2) evaluated the quality control (QC) program used at the soil sorter plant. The IV has found that the soil sorter decontamination was effective and significantly reduced plutonium contamination in the soil processed at the JA site. The Field Command Defense Threat Reduction Agency currently plans to re-use soil from the clean pile as a cover to remaining contamination in portions of the radiological control area. Therefore, ORNL was requested to provide an IV. The survey team collected samples from 103 random locations within the top 4 ft of the clean storage pile. The samples were analyzed in the on-site radioanalytical counting laboratory with an American Nuclear Systems (ANS) field instrument used for the detection of low-energy radiation. Nine results exceeded the JA soil screening guideline for distributed contamination of 13.5 pCi/g for total TRUs, ranging from 13.7 to 125.9 pCi/g. Because of these results, the goal of showing with 95% confidence that 97% of the processed soil is less than or equal to 13.5 pCi/g-TRU activity cannot be met. The value of 13.5 pCi/g represents the 88th percentile rather than the 95th percentile in a nonparametric one-sided upper 90% confidence limit. Therefore, at the 95% confidence level, 88% of the clean pile is projected to be below the 13.5-pCi/g goal. The Multi-Agency Radiation Survey and Site Investigation Manual recommends use of a nonparametric statistical ''Sign Test'' to demonstrate compliance with release criteria for TRU. Although this survey was not designed to use the sign test, the data herein would demonstrate that the median (50%) of the clean storage pile is below the l3.5-pCi/g derived concentration guideline level. In other words, with the caveat that additional investigation of elevated concentrations was not performed, the data pass the sign test at the 13.5-pCi/g level. Additionally, the lateral extent of the pile was gridded, and 10% of the grid blocks was scanned with field instruments for the detection of low-energy radiation coupled to ratemeter/scalers to screen for the presence of hot particles. No hot particles were detected in the top 1 cm of the grid blocks surveyed.« less

Sump bay fever: inhalational fever associated with a biologically contaminated water aerosol.

PubMed Central

Anderson, K; McSharry, C P; Clark, C; Clark, C J; Barclay, G R; Morris, G P

1996-01-01

OBJECTIVE: To investigate the clinical, serological, and environmental features of a work related inhalational fever associated with exposure to an aerosol generated from a biologically contaminated 130,000 gallon water pool in a building used for testing scientific equipment. METHOD: Cross sectional survey of all exposed subjects (n = 83) by symptom questionnaire, clinical examination, spirometry, and serology for antibody to Pseudomonads, pool water extract, and endotoxin. In symptomatic patients diffusion capacity was measured, and chest radiology was performed if this was abnormal. Serial peak flow was recorded in those subjects with wheeze. Bacterial and fungal air sampling was performed before and during operation of the water pool pump mechanism. Endotoxin was measured in the trapped waters and in the pumps. Serum cotinine was measured as an objective indicator of smoking. RESULTS: Of the 20 symptomatic subjects, fever was most common in those with the highest exposure (chi 2 42.7, P < 0.001) in the sump bay when the water was (torrentially) recirculated by the water pumps. Symptoms occurred late in the working day only on days when the water pumps were used, and were independent of the serum cotinine. Pulmonary function was normal in most subjects (spirometry was normal in 79/83, diffusion capacity was low in five subjects, chest radiology was normal). Peak flow recording did not suggest a work relation. The bacterial content of the aerosol rose from 6 to > 10,000 colony forming units per cubic metre (cfu/m3) (predominantly environmental Pseudomonads) when the pumps were operating. High endotoxin concentrations were measured in the waters and oil sumps in the pumps. Low concentrations of antibody to the organisms isolated were detected (apart from two subjects with high antibody) but there was no relation to exposure or the presence of symptoms and similar antibody was found in the serum samples from a non-exposed population. The fever symptoms settled completely with the simple expedient of changing the water and cleaning the pumps. CONCLUSION: Given the results of our study, the development of inhalational fever in this unique environment and clearly restricted cohort was closely related to the degree of exposure to contaminated aerosol and mainly occurred in the absence of distinct serological abnormality and independent of cigarette smoking. PMID:8777446

Environmental health program activities

NASA Technical Reports Server (NTRS)

Bergtholdt, C. P.

1969-01-01

Activities reported include studies on toxic air contaminants, excessive noise, poor lighting, food sanitation, water pollution, and exposure to nonionizing radiation as health hazards. Formulations for a radiological health manual provide guidance to personnel in the procurement and safe handling of radiation producing equipment and Apollo mission planning. A literature search and development of a water analysis laboratory are outlined to obtain information regarding microbiological problems involving potable water, waste management, and personal hygiene.

Chemical, Biological, and Radiological (CBR) Contamination Survivability, Small Items of Equipment

DTIC Science & Technology

2012-06-22

thickness (number of coats), paint condition, and surface cleanliness (mud, grease, and other). j. Pretest (baseline) and posttest (30 days after...survivability testing of small items of mission-essential (ME) Army materiel. Small items, for example , include personal gear, small arms, radios...their effects. An example would be the age of the paint on the surface (aged, new, etc.). f. The only current mechanism for converting agent mass

Chemical, Biological, and Radiological (CBR) Contamination Survivability: Large Item Interiors

DTIC Science & Technology

2012-06-22

materials of construction, paint type, and surface condition ( pretest and posttest ), including cleanliness (mud, grease, etc.). Photographs should be...35 g. Pretest and posttest ME functional performance characteristics (when measured) used as the measure of the SUT’s mission performance before and...materials and their finishes will be reported in a form that can be compared with pretest and posttest hardness functional performance data. 6.2 Chemical

Radiological results for samples collected on paired glass- and cellulose-fiber filters at the Sandia complex, Tonopah Test Range, Nevada

DOE Office of Scientific and Technical Information (OSTI.GOV)

Mizell, Steve A.; Shadel, Craig A.

Airborne particulates are collected at U.S. Department of Energy sites that exhibit radiological contamination on the soil surface to help assess the potential for wind to transport radionuclides from the contamination sites. Collecting these samples was originally accomplished by drawing air through a cellulose-fiber filter. These filters were replaced with glass-fiber filters in March 2011. Airborne particulates were collected side by side on the two filter materials between May 2013 and May 2014. Comparisons of the sample mass and the radioactivity determinations for the side-by-side samples were undertaken to determine if the change in the filter medium produced significant results.more » The differences in the results obtained using the two filter types were assessed visually by evaluating the time series and correlation plots and statistically by conducting a nonparametric matched-pair sign test. Generally, the glass-fiber filters collect larger samples of particulates and produce higher radioactivity values for the gross alpha, gross beta, and gamma spectroscopy analyses. However, the correlation between the radioanalytical results for the glass-fiber filters and the cellulose-fiber filters was not strong enough to generate a linear regression function to estimate the glass-fiber filter sample results from the cellulose-fiber filter sample results.« less

An aerial radiological survey of Maralinga and EMU, South Australia

DOE Office of Scientific and Technical Information (OSTI.GOV)

Tipton, W J; Berry, H A; Fritzsche, A E

An aerial radiological survey was conducted over the former British nuclear test ranges at Maralinga and Emu in South Australia from May through July 1987. The survey covered an area of approximately 1,550 square kilometers which included the nine major trial sites, where a nuclear yield occurred, and all the minor trial sites, where physics experiments were conducted. Flight lines were flown at an altitude of 30 meters with line spacings of 50, 100, and 200 meters depending on the area and whether man-made contamination was present. Results of the aerial survey were processed for americium-241 (used to determine plutoniummore » contamination), cesium-137, cobalt-60, and uranium-238. The aerial survey also detected the presence of europium-152, a soil activation product, in the immediate vicinity of the major trial ground zeros. Ground measurements were also made at approximately 120 locations using a high-resolution germanium detector to provide supplemental data for the aerial survey. This survey was conducted as part of a series of studies being conducted over a two to three-year timeframe to obtain information from which options and associated costs can be formulated about the decontamination and possible rehabilitation of the former nuclear test sites.« less

RADIOLOGICAL SURVEY STATION DEVELOPMENT FOR THE PIT DISASSEMBLY AND CONVERSION PROJECT

DOE Office of Scientific and Technical Information (OSTI.GOV)

Dalmaso, M.; Gibbs, K.; Gregory, D.

2011-05-22

The Savannah River National Laboratory (SRNL) has developed prototype equipment to demonstrate remote surveying of Inner and Outer DOE Standard 3013 containers for fixed and transferable contamination in accordance with DOE Standard 3013 and 10 CFR 835 Appendix B. When fully developed the equipment will be part of a larger suite of equipment used to package material in accordance with DOE Standard 3013 at the Pit Disassembly and Conversion Project slated for installation at the Savannah River Site. The prototype system consists of a small six-axis industrial robot with an end effector consisting of a force sensor, vacuum gripper andmore » a three fingered pneumatic gripper. The work cell also contains two alpha survey instruments, swipes, swipe dispenser, and other ancillary equipment. An external controller interfaces with the robot controller, survey instruments and other ancillary equipment to control the overall process. SRNL is developing automated equipment for the Pit Disassembly and Conversion (PDC) Project that is slated for the Savannah River Site (SRS). The equipment being developed is automated packaging equipment for packaging plutonium bearing materials in accordance with DOE-STD-3013-2004. The subject of this paper is the development of a prototype Radiological Survey Station (RSS). Other automated equipment being developed for the PDC includes the Bagless transfer System, Outer Can Welder, Gantry Robot System (GRS) and Leak Test Station. The purpose of the RSS is to perform a frisk and swipe of the DOE Standard 3013 Container (either inner can or outer can) to check for fixed and transferable contamination. This is required to verify that the contamination levels are within the limits specified in DOE-STD-3013-2004 and 10 CFR 835, Appendix D. The surface contamination limit for the 3013 Outer Can (OC) is 500 dpm/100 cm2 (total) and 20 dpm/100 cm2 (transferable). This paper will concentrate on the RSS developments for the 3013 OC but the system for the 3013 Inner Can (IC) is nearly identical.« less

Data Sharing Report Characterization of Isotope Row Facilities Oak Ridge National Laboratory Oak Ridge TN

DOE Office of Scientific and Technical Information (OSTI.GOV)

Weaver, Phyllis C.

The U.S. Department of Energy (DOE) Oak Ridge Office of Environmental Management (EM-OR) requested that Oak Ridge Associated Universities (ORAU), working under the Oak Ridge Institute for Science and Education (ORISE) contract, provide technical and independent waste management planning support using funds provided by the American Recovery and Reinvestment Act (ARRA). Specifically, DOE EM-OR requested ORAU to plan and implement a survey approach, focused on characterizing the Isotope Row Facilities located at the Oak Ridge National Laboratory (ORNL) for future determination of an appropriate disposition pathway for building debris and systems, should the buildings be demolished. The characterization effort wasmore » designed to identify and quantify radiological and chemical contamination associated with building structures and process systems. The Isotope Row Facilities discussed in this report include Bldgs. 3030, 3031, 3032, 3033, 3033A, 3034, 3036, 3093, and 3118, and are located in the northeast quadrant of the main ORNL campus area, between Hillside and Central Avenues. Construction of the isotope production facilities was initiated in the late 1940s, with the exception of Bldgs. 3033A and 3118, which were enclosed in the early 1960s. The Isotope Row facilities were intended for the purpose of light industrial use for the processing, assemblage, and storage of radionuclides used for a variety of applications (ORNL 1952 and ORAU 2013). The Isotope Row Facilities provided laboratory and support services as part of the Isotopes Production and Distribution Program until 1989 when DOE mandated their shutdown (ORNL 1990). These facilities performed diverse research and developmental experiments in support of isotopes production. As a result of the many years of operations, various projects, and final cessation of operations, production was followed by inclusion into the surveillance and maintenance (S&M) project for eventual decontamination and decommissioning (D&D). The process for D&D and final dismantlement of facilities requires that the known contaminants of concern (COCs) be evaluated and quantified and to identify and quantify any additional contaminants in order to satisfy the waste acceptance criteria requirements for the desired disposal pathway. Known facility contaminants include, but are not limited to, asbestos-containing material (ACM), radiological contaminants, and chemical contaminants including polychlorinated biphenyls (PCBs) and metals.« less

Development of emergency response tools for accidental radiological contamination of French coastal areas.

PubMed

Duffa, Céline; Bailly du Bois, Pascal; Caillaud, Matthieu; Charmasson, Sabine; Couvez, Céline; Didier, Damien; Dumas, Franck; Fievet, Bruno; Morillon, Mehdi; Renaud, Philippe; Thébault, Hervé

2016-01-01

The Fukushima nuclear accident resulted in the largest ever accidental release of artificial radionuclides in coastal waters. This accident has shown the importance of marine assessment capabilities for emergency response and the need to develop tools for adequately predicting the evolution and potential impact of radioactive releases to the marine environment. The French Institute for Radiological Protection and Nuclear Safety (IRSN) equips its emergency response centre with operational tools to assist experts and decision makers in the event of accidental atmospheric releases and contamination of the terrestrial environment. The on-going project aims to develop tools for the management of marine contamination events in French coastal areas. This should allow us to evaluate and anticipate post-accident conditions, including potential contamination sites, contamination levels and potential consequences. In order to achieve this goal, two complementary tools are developed: site-specific marine data sheets and a dedicated simulation tool (STERNE, Simulation du Transport et du transfert d'Eléments Radioactifs dans l'environNEment marin). Marine data sheets are used to summarize the marine environment characteristics of the various sites considered, and to identify vulnerable areas requiring implementation of population protection measures, such as aquaculture areas, beaches or industrial water intakes, as well as areas of major ecological interest. Local climatological data (dominant sea currents as a function of meteorological or tidal conditions) serving as the basis for an initial environmental sampling strategy is provided whenever possible, along with a list of possible local contacts for operational management purposes. The STERNE simulation tool is designed to predict radionuclide dispersion and contamination in seawater and marine species by incorporating spatio-temporal data. 3D hydrodynamic forecasts are used as input data. Direct discharge points or atmospheric deposition source terms can be taken into account. STERNE calculates Eulerian radionuclide dispersion using advection and diffusion equations established offline from hydrodynamic calculations. A radioecological model based on dynamic transfer equations is implemented to evaluate activity concentrations in aquatic organisms. Essential radioecological parameters (concentration factors and single or multicomponent biological half-lives) have been compiled for main radionuclides and generic marine species (fish, molluscs, crustaceans and algae). Dispersion and transfer calculations are performed simultaneously on a 3D grid. Results can be plotted on maps, with possible tracking of spatio-temporal evolution. Post-processing and visualization can then be performed. Copyright © 2015 Elsevier Ltd. All rights reserved.

[A case report: anomaly of the fourth branchial pouch with recurring cervical abscesses. Cauterization with trichloroacetic acid closed the fistula opening and cured the patient].

PubMed

Stenquist, Monika; Juhlin, Claes; Aström, Gunnar; Friberg, Ulla

2003-04-24

A fourth branchial pouch sinus is a rare congenital anomaly, which in a 13-year-old girl presented clinically as recurrent deep cervical abscesses. The location of the majority of these anomalies is the left side of the neck (90%). Radiological and endoscopic investigations verified the diagnosis. The internal orifice located at the apex of the pyriform sinus could facilitate contamination by infectious pharyngeal secretions and lead to abscess recurrence. Traditionally, the recommended treatment is radical surgery. It can, however, be technically difficult to excise the whole fistula tract. In this patient we used a non-invasive treatment modality; chemocauterization with 40% trichloroacetic acid (TCA). After three treatments the fistula was closed. To date (month no. 15) there has been no abscess recurrence. TCA chemocauterization seems to be a safe first-line treatment for patients with pyriform sinus fistulas.

Middlesex FUSRAP Site - A Path to Site-Wide Closure - 13416

DOE Office of Scientific and Technical Information (OSTI.GOV)

Miller, David M.; Edge, Helen

2013-07-01

The road-map to obtaining closure of the Middlesex Sampling Plant FUSRAP site in Middlesex, New Jersey (NJ) has required a multi-faceted approach, following the CERCLA Process. Since 1998, the US ACE, ECC, and other contractors have completed much of the work required for regulatory acceptance of site closure with unrestricted use. To date, three buildings have been decontaminated, demolished, and disposed of. Two interim storage piles have been removed and disposed of, followed by the additional removal and disposal of over 87,000 tons of radiologically and chemically-impacted subsurface soils by the summer of 2008. The US ACE received a determinationmore » from the EPA for the soils Operable Unit, (OU)-1, in September 2010 that the remedial excavations were acceptable, and meet the criteria for unrestricted use as required by the 2004 Record of Decision (ROD) for OU-1. Following the completion of OU-1, the project delivery team performed additional field investigation of the final Operable Unit for Middlesex, OU-2, Groundwater. As of December 2012, the project delivery team has completed a Supplemental Remedial Investigation, which will be followed with a streamlined Feasibility Study, Proposed Plan, and ROD. Several years of historical groundwater data was available from previous investigations and the FUSRAP Environmental Surveillance Program. Historical data indicated sporadic detections of Volatile Organic Compounds (VOCs), primarily trichloroethylene (TCE), carbon tetrachloride (CT), and methyl tert-butyl ether (MTBE), with no apparent trend or pattern indicating extent or source of the VOC impact. In 2008, the project delivery team initiated efforts to re-assess the Conceptual Site Model (CSM) for groundwater. The bedrock was re-evaluated as a leaky multi-unit aquifer, and a plan was developed for additional investigations for adequate bedrock characterization and delineation of groundwater contaminated primarily by CT, TCE, and tetrachloroethene (PCE). The investigation was designed to accumulate multiple lines of evidence to determine the source and to delineate the extent of contamination, as required to complete the CERCLA Process and gain regulatory acceptance. Investigative techniques included in-well vertical flow tracing, borehole geophysics and packer testing of temporary test holes to characterize contamination in the bedrock fractures beneath the site, and to delineate likely source areas. (authors)« less

SUDOQU: a new dose model to derive criteria for surface contamination of non-food (consumer) goods, containers and conveyances.

PubMed

van Dillen, Teun

2015-04-01

The Fukushima nuclear accident (Japan, 11 March 2011) revealed the need for well-founded criteria for surface contamination and associated screening levels related to the import of non-food (consumer) goods, containers and conveyances. The only available European-harmonised criteria are those laid down in the IAEA transport regulations, but these criteria date back from the early 1960s and only apply to the safe transport of radioactive materials. The main problem is that a generic dose-assessment model for consumer products is missing. Therefore, RIVM (National Institute for Public Health and the Environment) developed a new methodology entitled SUDOQU (SUrface DOse QUantification) to calculate the annual effective dose for both consumers and non-radiological workers, addressing issues of removability of surface contamination. The methodology can be used to derive criteria and screening levels for surface contamination and could serve as a useful tool for policy-makers and radiation-protection specialists. © The Author 2014. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

First annual report on the Biological Monitoring and Abatement Program at Oak Ridge National Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

Loar, J. M.; Adams, S. M.; Blaylock, B. G.

1992-08-01

As a condition of the National Pollutant Discharge Elimination System (NPDES) permit issued to Oak Ridge National Laboratory (ORNL) on April 1, 1986, a Biological Monitoring and Abatement Program (BMAP) was developed for White Oak Creek (WOC); selected tributaries of WOC, including Fifth Creek, First Creek, Melton Branch, and Northwest Tributary; and the Clinch River. BMAP consists of seven major tasks that address both radiological and nonradiological contaminants in the aquatic and terrestrial environs on-site and the aquatic environs off-site. These tasks are (1) toxicity monitoring; (2) bioaccumulation monitoring of nonradiological contaminants in aquatic biota; (3) biological indicator studies; (4)more » instream ecological monitoring; (5) assessment of contaminants in the terrestrial environment; (6) radioecology of WOC and White Oak Lake (WOL); and (7) contaminant transport, distribution, and fate in the WOC embayment-Clinch River-Watts Bar Reservoir system. This document, the first of a series of annual reports presenting the results of BMAP, describes studies that were conducted from March through December 1986.« less

Final report of the decontamination and decommissioning of Building 34 at the Grand Junction Projects Office Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Widdop, M.R.

1996-08-01

The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7 acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the Grand Junction Projects Office Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, was also the remedialmore » action contractor. Building 34 was radiologically contaminated and the building was demolished in 1996. The soil area within the footprint of the building was analyzed and found to be not contaminated. The area can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual closeout report for each contaminated GJPO building.« less

Final report of the decontamination and decommissioning of Building 44 at the Grand Junction Projects Office Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Widdop, M.R.

1996-07-01

The U.S. Department of Energy (DOE) Junction Projects Office (GJPO) occupies a 61.7 acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the Grand Junction Projects Office Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, is also the remedial actionmore » contractor. Building 44 was radiologically contaminated and the building was demolished in 1994. The soil area within the footprint of the building was not contaminated; it complies with the identified standards and the area can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.« less

Final report of the decontamination and decommissioning of Building 18 at the Grand Junction Projects Office Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Widdop, M.R.

1996-08-01

The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, also is the remedial action contractor. The soilmore » beneath Building 18 was found to be radiologically contaminated; the building was not contaminated. The soil was remediated in accordance with identified standards. Building 18 and the underlying soil can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.« less

The Spanish Protocol for radiological surveillance of metal recycling: a collaboration of government and industry.

PubMed

Cadierno, Juan Pedro García; Renedo, J I Serrano; Lopez, E Gil

2006-11-01

The presence of radioactive materials in scrap metal has been detected relatively often in recent years. As a result of an accidental melting of a 137Cs source in a Spanish steel mill (Acerinox) in 1998, the national authorities, the involved private companies, and the main trade unions drafted a protocol for prevention of and responding to such events ("Spanish Protocol"). The Protocol was signed in 1999. The number of subscribing companies is 90. The Protocol is a voluntary agreement defining the radiological surveillance of scrap metal and its products and the duties and rights of the signatories. From the effective date of the Protocol to December 2004, 461 pieces of ferric scrap were detected including sources of radiation and contaminated metal. Four melting incidents have happened in different companies.

Nuclear Rocket Test Facility Decommissioning Including Controlled Explosive Demolition of a Neutron-Activated Shield Wall

DOE Office of Scientific and Technical Information (OSTI.GOV)

Michael Kruzic

2007-09-01

Located in Area 25 of the Nevada Test Site, the Test Cell A Facility was used in the 1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program. The facility was decontaminated and decommissioned (D&D) in 2005 using the Streamlined Approach For Environmental Restoration (SAFER) process, under the Federal Facilities Agreement and Consent Order (FFACO). Utilities and process piping were verified void of contents, hazardous materials were removed, concrete with removable contamination decontaminated, large sections mechanically demolished, and the remaining five-foot, five-inch thick radiologically-activated reinforced concrete shield wall demolished using open-air controlled explosive demolitionmore » (CED). CED of the shield wall was closely monitored and resulted in no radiological exposure or atmospheric release.« less

File format for normalizing radiological concentration exposure rate and dose rate data for the effects of radioactive decay and weathering processes

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kraus, Terrence D.

2017-04-01

This report specifies the electronic file format that was agreed upon to be used as the file format for normalized radiological data produced by the software tool developed under this TI project. The NA-84 Technology Integration (TI) Program project (SNL17-CM-635, Normalizing Radiological Data for Analysis and Integration into Models) investigators held a teleconference on December 7, 2017 to discuss the tasks to be completed under the TI program project. During this teleconference, the TI project investigators determined that the comma-separated values (CSV) file format is the most suitable file format for the normalized radiological data that will be outputted frommore » the normalizing tool developed under this TI project. The CSV file format was selected because it provides the requisite flexibility to manage different types of radiological data (i.e., activity concentration, exposure rate, dose rate) from other sources [e.g., Radiological Assessment and Monitoring System (RAMS), Aerial Measuring System (AMS), Monitoring and Sampling). The CSV file format also is suitable for the file format of the normalized radiological data because this normalized data can then be ingested by other software [e.g., RAMS, Visual Sampling Plan (VSP)] used by the NA-84’s Consequence Management Program.« less

Technical support for the EPA cleanup rule on radioactively contaminated sites

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hull, H.B.; Newman, A.; Wolbarst, A.B.

1995-12-31

The U.S. Environmental Protection Agency (EPA) is developing a radiation site cleanup regulation for the protection of the public from radionuclide contamination at sites that are to be cleaned up and released for public use. The regulation will apply to sites under the control of Federal agencies, and to sites licensed by the Nuclear Regulatory Commission (NRC) or NRC Agreement States. The agency is therefore conducting a comprehensive technical analysis aimed at developing information that will be used to support the rule. This presentation describes the regulation and the approach developed to determine how radiological health impacts and volumes ofmore » soil requiring remediation vary as functions of the possible cleanup dose or risk level.« less

Detection of microbial contamination during human islet isolation.

PubMed

Kin, Tatsuya; Rosichuk, Shawn; Shapiro, A M James; Lakey, Jonathan R T

2007-01-01

Current good manufacturing practice (cGMP) islet processing facilities provide an ultraclean environment for the safe production of clinical grade islets for transplantation into immunosuppressed diabetic recipients. The objective of this study was to monitor the rate of microbial contamination in islet products after implementation of good manufacturing practice conditions. Fluid samples for microbial contamination were collected at the following steps: from the pancreas transport solution upon arrival of the organ (n=157), after surface decontamination of the pancreas with antiseptic agents (n=89), from islet supernatant at the end of the isolation (n=104), and from islet supernatant as a final transplantable product after culture (n=53). Bacterial, fungal, and mycoplasma cultures were conducted for 2, 2, and 3 weeks, respectively. Microbial contamination was detected in 31% of transport solution. The contamination was not associated with the presence of the duodenum during the preservation, cold ischemia time, or procurement team (local vs. distant). Surface decontamination of the pancreas resulted in clearance of 92% of the microbial contamination. Six preparations at the end of the isolation revealed microbial growth. All were de novo contamination during the processing. Fifty-three preparations that met our release criteria in terms of product sterility were transplanted into type 1 diabetic patients. In two instances, positive culture of the islet preparation was reported after transplantation had occurred. No patient showed any clinical findings suggestive of infection or any radiological abnormalities suggestive of abscess; a single dose of antibiotic coverage was given routinely to recipients prior to islet infusion. Although transport solution carries a high risk of microbial contamination, most contaminants become undetectable during islet processing. Microbial contamination in final products is rare, but de novo contamination still occurs during processing even under cGMP conditions.

Detection of Microbial Contamination during Human Islet Isolation.

PubMed

Kin, Tatsuya; Rosichuk, Shawn; Shapiro, A M James; Lakey, Jonathan R T

2007-01-01

Current good manufacturing practice (cGMP) islet processing facilities provide an ultraclean environment for the safe production of clinical grade islets for transplantation into immunosuppressed diabetic recipients. The objective of this study was to monitor the rate of microbial contamination in islet products after implementation of good manufacturing practice conditions. Fluid samples for microbial contamination were collected at the following steps: from the pancreas transport solution upon arrival of the organ (n = 157), after surface decontamination of the pancreas with antiseptic agents (n = 89), from islet supernatant at the end of the isolation (n = 104), and from islet supernatant as a final transplantable product after culture (n = 53). Bacterial, fungal, and mycoplasma cultures were conducted for 2, 2, and 3 weeks, respectively. Microbial contamination was detected in 31% of transport solution. The contamination was not associated with the presence of the duodenum during the preservation, cold ischemia time, or procurement team (local vs. distant). Surface decontamination of the pancreas resulted in clearance of 92% of the microbial contamination. Six preparations at the end of the isolation revealed microbial growth. All were de novo contamination during the processing. Fifty-three preparations that met our release criteria in terms of product sterility were transplanted into type 1 diabetic patients. In two instances, positive culture of the islet preparation was reported after transplantation had occurred. No patient showed any clinical findings suggestive of infection or any radiological abnormalities suggestive of abscess; a single dose of antibiotic coverage was given routinely to recipients prior to islet infusion. Although transport solution carries a high risk of microbial contamination, most contaminants become undetectable during islet processing. Microbial contamination in final products is rare, but de novo contamination still occurs during processing even under cGMP conditions.

Updating Dosimetry for Emergency Response Dose Projections.

PubMed

DeCair, Sara

2016-02-01

In 2013, the U.S. Environmental Protection Agency (EPA) proposed an update to the 1992 Protective Action Guides (PAG) Manual. The PAG Manual provides guidance to state and local officials planning for radiological emergencies. EPA requested public comment on the proposed revisions, while making them available for interim use by officials faced with an emergency situation. Developed with interagency partners, EPA's proposal incorporates newer dosimetric methods, identifies tools and guidelines developed since the current document was issued, and extends the scope of the PAGs to all significant radiological incidents, including radiological dispersal devices or improvised nuclear devices. In order to best serve the emergency management community, scientific policy direction had to be set on how to use International Commission on Radiological Protection Publication 60 age groups in dose assessment when implementing emergency guidelines. Certain guidelines that lend themselves to different PAGs for different subpopulations are the PAGs for potassium iodide (KI), food, and water. These guidelines provide age-specific recommendations because of the radiosensitivity of the thyroid and young children with respect to ingestion and inhalation doses in particular. Taking protective actions like using KI, avoiding certain foods or using alternative sources of drinking water can be relatively simple to implement by the parents of young children. Clear public messages can convey which age groups should take which action, unlike how an evacuation or relocation order should apply to entire households or neighborhoods. New in the PAG Manual is planning guidance for the late phase of an incident, after the situation is stabilized and efforts turn toward recovery. Because the late phase can take years to complete, decision makers are faced with managing public exposures in areas not fully remediated. The proposal includes quick-reference operational guidelines to inform re-entry to the contaminated zone. Broad guidance on approaches to wide-area cleanup and cleanup goals is also provided. EPA adapted the cleanup process from the 2008 U.S. Department of Homeland Security (DHS) Planning Guidance for Protection and Recovery Following Radiological Dispersal Device (RDD) and Improvised Nuclear Device (IND) Incidents, and the final PAG Manual will supersede that DHS guidance. Waste management guidance is also provided. Recognizing that an incident could result in radioactive waste volumes that severely strain or exceed available resources and capacity, officials may consider alternatives for disposal of waste that is relatively lightly contaminated. Waste management, including treatment, staging, and interim and long-term storage, must be an integral part of recovery.

Oil as a Weapon of the 21st Century: Energy Security and the U.S. Pivot to Asia-Pacific

DTIC Science & Technology

2016-03-01

11 Compared to hydrocarbons, nuclear power offers a carbon-free power generation source, but carries the risk of radiological contamination . With...South Korea, Australia, New Zealand, Philippines, Thailand, Vietnam, Indonesia, Malaysia , Singapore, Australia, Bangladesh, and Burma.88,89 Enhancing...engagement between the countries comprising CTF 151 has resulted in several documented instances where Canadian and British forces gave food and water

General practitioners’ views on radiology reports of plain radiography for back pain

PubMed Central

Espeland, Ansgar; Baerheim, Anders

2007-01-01

Objective To identify and describe general practitioners’ (GPs’) views on radiology reports, using plain radiography for back pain as the case. Design Qualitative study with three focus-group interviews analysed using Giorgi's method as modified by Malterud. Setting Southern Norway. Subjects Five female and eight male GPs aged 32–57 years who had practised for 3–15 years and were from 11 different practices. Main outcome measures Descriptions of GPs’ views. Results GPs wanted radiology reports to indicate more clearly the meaning of radiological terminology, the likelihood of disease, the clinical relevance of the findings, and/or the need for further investigations. GPs stated that good referral information leads to better reports. Conclusion These results can help to improve communication between radiologists and GPs. The issues identified in this study could be further investigated in studies that can quantify GPs’ satisfaction with radiology reports in relation to characteristics of the GP, the radiologist, and the referral information. PMID:17354154

Comprehensive Health Care Economics Curriculum and Training in Radiology Residency.

PubMed

Keiper, Mark; Donovan, Timothy; DeVries, Matthew

2018-06-01

To investigate the ability to successfully develop and institute a comprehensive health care economics skills curriculum in radiology residency training utilizing didactic lectures, case scenario exercises, and residency miniretreats. A comprehensive health care economics skills curriculum was developed to significantly expand upon the basic ACGME radiology residency milestone System-Based Practice, SBP2: Health Care Economics requirements and include additional education in business and contract negotiation, radiology sales and marketing, and governmental and private payers' influence in the practice of radiology. A health care economics curriculum for radiology residents incorporating three phases of education was developed and implemented. Phase 1 of the curriculum constituted basic education through didactic lectures covering System-Based Practice, SBP2: Health Care Economics requirements. Phase 2 constituted further, more advanced didactic lectures on radiology sales and marketing techniques as well as government and private insurers' role in the business of radiology. Phase 3 applied knowledge attained from the initial two phases to real-life case scenario exercises and radiology department business miniretreats with the remainder of the radiology department. A health care economics skills curriculum in radiology residency is attainable and essential in the education of future radiology residents in the ever-changing climate of health care economics. Institution of more comprehensive programs will likely maximize the long-term success of radiology as a specialty by identifying and educating future leaders in the field of radiology. Copyright © 2018 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Concrete shaver. Innovative technology summary report

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1998-12-01

The US Department of Energy (DOE) is in the process of decontamination and decommissioning (D and D) for many of its nuclear facilities throughout the United States. These facilities must be dismantled and the demolition waste sized into manageable pieces for handling and disposal. The facilities undergoing D and D are typically chemically and/or radiologically contaminated. To facilitate this work, DOE requires a tool capable of removing the surface of radiologically contaminated concrete floors. Operating requirements for the tool include simple and economical operation, the capability of operating in ambient temperatures from 3 C to 40 C (37 F tomore » 104 F), and the ability to be easily decontaminated. The tool also must be safe for workers. The Marcrist Industries Limited concrete shaver is an electrically driven, self-propelled concrete and coating removal system. This technology consists of a 25-cm (10-in.)-wide diamond impregnated shaving drum powered by an electric motor and contains a vacuum port for dust extraction. The concrete shaver is ideal for use on open, flat, floor areas. The shaver may also be used on slightly curved surfaces. This shaver is self-propelled and produces a smooth, even surface with little vibration. The concrete shaver is an attractive alternative to traditional pneumatic scabbling tools, which were considered the baseline in this demonstration. The use of this tool reduces worker fatigue (compared to the baseline) due to lower vibration. The shaver is more than five times faster than the five-piston pneumatic scabbler at removing contamination from concrete. Because of this increased productivity, the shaver is 50% less costly to operate than baseline technologies. The DOE has successfully demonstrated the concrete shaver for decontaminating floors for free-release surveys prior to demolition work.« less

Addendum to the Closure Report for Corrective Action Unit 326: Areas 6 and 27 Release Sites, Nevada Test Site, Nevada, Revision 1

DOE Office of Scientific and Technical Information (OSTI.GOV)

Grant Evenson

This document constitutes an addendum to the Closure Report for Corrective Action Unit 326: Areas 6 and 27 Release Sites, Nevada Test Site, Nevada (Revision 1), December 2002 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada Test Site, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: • This page that refers the reader to the SIR document for additional information • Themore » cover, title, and signature pages of the SIR document • The NDEP approval letter • The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the UR for CAS 06-25-01, CP-1 Heating Oil Release. This UR was established as part of a Federal Facility Agreement and Consent Order (FFACO) corrective action and is based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since this UR was established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, this UR was reevaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the UR) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove the UR because contamination is not present at the site above the risk-based FALs. Requirements for inspecting and maintaining this UR will be canceled, and the postings and signage at this site will be removed. Fencing and posting may be present at this site that are unrelated to the FFACO UR such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at this site.« less

Addendum to the Closure Report for Corrective Action Unit 403: Second Gas Station, Tonopah Test Range, Nevada, Revision 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Grant Evenson

This document constitutes an addendum to the Closure Report for Corrective Action Unit 403: Second Gas Station, Tonopah Test Range, Nevada, September 1998 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada Test Site, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: • This page that refers the reader to the SIR document for additional information • The cover, title, and signature pagesmore » of the SIR document • The NDEP approval letter • The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the UR for CAS 03-02-004-0360, Underground Storage Tanks. This UR was established as part of a Federal Facility Agreement and Consent Order (FFACO) corrective action and is based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since this UR was established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, this UR was reevaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the UR) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove the UR because contamination is not present at the site above the risk-based FALs. Requirements for inspecting and maintaining this UR will be canceled, and the postings and signage at this site will be removed. Fencing and posting may be present at this site that are unrelated to the FFACO UR such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at this site.« less

Addendum to the Closure Report for Corrective Action Unit 339: Area 12 Fleet Operations Steam Cleaning Discharge Area, Nevada Test Site, Revision 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Grant Evenson

This document constitutes an addendum to the Closure Report for CAU 339: Area 12 Fleet Operations Steam Cleaning Discharge Area Nevada Test Site, December 1997 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada Test Site, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: • This page that refers the reader to the SIR document for additional information • The cover, title, andmore » signature pages of the SIR document • The NDEP approval letter • The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the UR for CAS 12-19-01, A12 Fleet Ops Steam Cleaning Efflu. This UR was established as part of a Federal Facility Agreement and Consent Order (FFACO) corrective action and is based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since this UR was established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, this UR was reevaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the UR) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove the UR because contamination is not present at the site above the risk-based FALs. Requirements for inspecting and maintaining this UR will be canceled, and the postings and signage at this site will be removed. Fencing and posting may be present at this site that are unrelated to the FFACO UR such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at this site.« less

Addendum 2 to the Closure Report for Corrective Action Unit 358: Areas 18, 19, 20 Cellars/Mud Pits, Nevada Test Site, Nevada, Revison 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Grant Evenson

This document constitutes an addendum to the Closure Report for Corrective Action Unit 358: Areas 18, 19, 20 Cellars/Mud Pits, Nevada Test Site, Nevada, January 2004 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada Test Site, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: • This page that refers the reader to the SIR document for additional information • The cover, title,more » and signature pages of the SIR document • The NDEP approval letter • The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the UR for CAS 19-09-05, Mud Pit. This UR was established as part of a Federal Facility Agreement and Consent Order (FFACO) corrective action and is based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since this UR was established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, this UR was reevaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the UR) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove the UR because contamination is not present at the site above the risk-based FALs. Requirements for inspecting and maintaining this UR will be canceled, and the postings and signage at this site will be removed. Fencing and posting may be present at this site that are unrelated to the FFACO UR such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at this site.« less

[eLearning-radiology.com--sustainability for quality assurance].

PubMed

Ketelsen, D; Talanow, R; Uder, M; Grunewald, M

2009-04-01

The aim of the study was to analyze the availability of published radiological e-learning tools and to establish a solution for quality assurance. Substantial pubmed research was performed to identify radiological e-learning tools. 181 e-learning programs were selected. As examples two databases expanding their programs with external links, Compare (n = 435 external links) and TNT-Radiology (n = 1078 external links), were evaluated. A concept for quality assurance was developed by an international taskforce. At the time of assessment, 56.4 % (102 / 181) of the investigated e-learning tools were accessible at their original URL. A subgroup analysis of programs published 5 to 8 years ago showed significantly inferior availability to programs published 3 to 5 years ago (p < 0.01). The analysis of external links showed 49.2 % and 61.0 % accessible links for the programs Compare (published 2003) and TNT-Radiology (published 2006), respectively. As a consequence, the domain www.eLearning-radiology.com was developed by the taskforce and published online. This tool allows authors to present their programs and users to evaluate the e-learning tools depending on several criteria in order to remove inoperable links and to obtain information about the complexity and quality of the e-learning tools. More than 50 % of investigated radiological e-learning tools on the Internet were not accessible after a period of 5 to 8 years. As a consequence, an independent, international tool for quality assurance was designed and published online under www.eLearning-radiology.com .

DOE Office of Scientific and Technical Information (OSTI.GOV)

Cournoyer, Michael E; George, Gerald L; Dodge, Robert L

Programmatic operations at the Los Alamos National Laboratory Plutonium Facility (TA-55) involve working with various amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces, airborne contamination, and excursions of contaminants into the operator's breathing zone are prevented through the use of a variety of gloveboxes (the glovebox, coupled with an adequate negative pressure gradient, provides primary confinement). Radiation shielding is commonly used to protect the glovebox worker from unintentional direct and secondary radiation exposure, while working with plutonium-238 and plutonium-239. In these environments, low-energy photons, i.e., those less than 250 keY, are encountered.more » Shielding glove box gloves are traditionally composed of lead-based materials, but these are now considered hazardous waste. This has prompted the development of new, nonhazardous- shielding gJovebox gloves. No studies, however, have investigated the effectiveness of these new glovebox gloves. We examined both leaded and nonhazardous- shielding glovebox gloves and compared their attenuation effectiveness over the energy range of interest at TA-55. All measurements are referenced to lead sheets, allowing direct comparisons to the common industry standard of 0.1 mm lead equivalent material. The attenuation properties of both types of glovebox gloves vary with energy, making it difficult for manufacturers to claim lead equivalency across the entire energy range used at TA-55. The positions of materials' photon energy absorption edges, which are particularly important to improved attenuation performance, depending upon the choice of radiation energy range, are discussed. This effort contributes to the Los Alamos National Laboratory Continuous Improvement Program by improving the efficiency, cost effectiveness, and formality of glovebox operations.« less

Abandoned Rayrock uranium mill tailings in the Northwest Territories: Environmental conditions and radiological impact

DOE Office of Scientific and Technical Information (OSTI.GOV)

Veska, E.; Eaton, R.S.

Field and laboratory investigations were undertaken of the environment surrounding abandoned U mill tailings at Rayrock, Northwest Territories, Canada, to examine the extent of 226Ra and U contamination. Samples of ground water, surface water, and unconsolidated geological material from the Rayrock area were collected for chemical and radiochemical analyses. Results indicated that the surface waters contained levels of 226Ra as high as 20 Bq L-1, 210Pb as high as 1.1 Bq L-1, and ground water U as high as 2800 micrograms L-1. Lower levels of 226Ra, 210Pb, and U, 3.6 Bq L-1, 0.5 Bq L-1, and 4 micrograms L-1, respectively,more » were found in a small lake adjacent to the tailings area. Analysis of tailings and soil in the immediate vicinity indicates that the radionuclides and U are mobilized and can move within the tailings. Some of the mobilized radionuclides will be bound by the surrounding peat. The remainder may move to Lake Alpha in ground water. Surface water flow also transports some contaminants both in the water of Alpha Creek and by washing tailings into Lake Alpha. The potential annual external and internal dose equivalents to a hypothetical resident were calculated based on exposure from the abandoned U mill tailings, drinking water, and fish caught in the lakes in the vicinity of the tailings. While Alpha Creek and Lake Alpha water showed evidence of contamination, the rest of the water system and the fish were at natural background levels of radioactivity.« less

High Efficiency Particulate Air (HEPA) Filter Generation, Characterization, and Disposal Experiences at the Oak Ridge National Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

Coffey, D. E.

2002-02-28

High Efficiency Particulate Air filtration is an essential component of the containment and ventilation systems supporting the research and development activities at the Oak Ridge National Laboratory. High Efficiency Particulate Air filters range in size from 7.6cm (3 inch) by 10.2 cm (4 inch) cylindrical shape filters to filter array assemblies up to 2.1 m (7 feet) high by 1.5 m (5 feet) wide. Spent filters are grouped by contaminates trapped in the filter media and become one of the components in the respective waste stream. Waste minimization and pollution prevention efforts are applied for both radiological and non-radiological applications.more » Radiological applications include laboratory hoods, glove boxes, and hot cells. High Efficiency Particulate Air filters also are generated from intake or pre-filtering applications, decontamination activities, and asbestos abatement applications. The disposal avenues include sanitary/industrial waste, Resource Conservation and Recovery Act and Toxic Substance Control Act, regulated waste, solid low-level waste, contact handled transuranic, and remote handled transuranic waste. This paper discusses characterization and operational experiences associated with the disposal of the spent filters across multiple applications.« less

Assessment of the radiological impact of oil refining industry.

PubMed

Bakr, W F

2010-03-01

The field of radiation protection and corresponding national and international regulations has evolved to ensure safety in the use of radioactive materials. Oil and gas production processing operations have been known to cause naturally occurring radioactive materials (NORMs) to accumulate at elevated concentrations as by-product waste streams. A comprehensive radiological study on the oil refining industry in Egypt was carried out to assess the radiological impact of this industry on the workers. Scales, sludge, water and crude oil samples were collected at each stage of the refining process. The activity concentration of (226)Ra, (232)Th and (40)K were determined using high-resolution gamma spectrometry. The average activity concentrations of the determined isotopes are lower than the IAEA exempt activity levels for NORM isotopes. Different exposure scenarios were studied. The average annual effective dose for workers due to direct exposure to gamma radiation and dust inhalation found to be 0.6 microSv and 3.2 mSv, respectively. Based on the ALARA principle, the results indicate that special care must be taken during cleaning operations in order to reduce the personnel's exposure due to maintenance as well as to avoid contamination of the environment. 2009 Elsevier Ltd. All rights reserved.

Structural Characterization of the 216-Z-9 Crib Prior to Decontamination and Demolition Using Robot Crawler and High Resolution Photography

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hopkins, A.; Sutter, C.; Klos, D.B.

2008-07-01

The Department of Energy, Richland Operations Office is preparing to conduct a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) removal action for the decontamination and demolition of the above-grade mining structures and equipment at the 216-Z-9 Crib. An investigation of the condition of the mining complex was initiated to determine constraints necessary for safely conducting the removal of the buildings. While crib headspace chemical analysis and nondestructive analysis of the interior of the buildings was completed to address radiological contamination concerns, the primary concern regarding the removal of the above-grade structures located on the crib cover involves determining themore » loading capacity and structural integrity of the crib cover slab. Additional concerns included headspace gases and radionuclide contamination. Until the structural analysis was completed, loading limits on the crib cover had been restricted. Photographic documentation revealed the loss of protective tiles and acid resistant coating from the underside of the cover raising a question of concrete stability. The investigation relied heavily on the use of high resolution photography with high intensity lighting for photographic documentation of the underside of the crib cover, followed by structural analysis of the documentation by a team of qualified engineers. Deployment of a robot crawler with attached camera and positioning of a fixed camera were integral to this structural characterization effort. Results of the photographic documentation were of sufficient quality to allow for bounding decisions to be made regarding the loading of the crib cover while performing the demolition of the mining structures (glovebox, excavator, bucket) and the associated buildings. The 216-Z-9 Crib, also known as the 216 Z-9 Recuplex CAW (CA column waste) Waste Disposal Cavern, the Z-9 Trench and the Z-9 Crib was constructed as an engineered trench with an open area beneath a concrete slab. The crib is located near the Plutonium Finishing Plant (PFP) facility, at the Hanford Nuclear Reservation in Eastern Washington State. The crib was used as a disposal site for effluent chemical and radiological wastes from the recovery of uranium and plutonium through extraction or RECUPLEX process, a method that recovered uranium and plutonium from liquid and solid wastes and scraps from other PFP processes. During its operating life, from 1955 through 1962, the Z-9 Crib received liquid wastes totaling approximately four million liters, or one million gallons. Analyses of the crib soil in seven locations to a depth of up to two meters (six feet) beneath the crib floor indicated that the plutonium content of the crib soil ranged from 50 to 150 kg (the highest concentration measured was 34.5 g/L of soil). While performing the structural evaluation of the crib cover, additional characterization information was obtained on the radiological and chemical conditions of the crib and structures. (authors)« less

Corrective Action Decision Document/Closure Report for Corrective Action Unit 367: Area 10 Sedan, Ess and Uncle Unit Craters Nevada National Security Site, Nevada, Revision 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Patrick Matthews

2011-06-01

Corrective Action Unit 367 comprises four corrective action sites (CASs): • 10-09-03, Mud Pit • 10-45-01, U-10h Crater (Sedan) • 10-45-02, Ess Crater Site • 10-45-03, Uncle Crater Site The purpose of this Corrective Action Decision Document/Closure Report is to provide justification and documentation of the corrective actions and site closure activities implemented at CAU 367. A corrective action of closure in place with use restrictions was completed at each of the three crater CASs (10-45-01, 10-45-02, and 10-45-03); corrective actions were not required at CAS 10-09-03. In addition, a limited soil removal corrective action was conducted at the locationmore » of a potential source material release. Based on completion of these correction actions, no additional corrective action is required at CAU 367, and site closure is considered complete. Corrective action investigation (CAI) activities were performed from February 2010 through March 2011, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 367: Area 10 Sedan, Ess and Uncle Unit Craters, Nevada Test Site, Nevada. The approach for the CAI was divided into two facets: investigation of the primary release of radionuclides, and investigation of non-test or other releases (e.g., migration in washes and potential source material). Based on the proximity of the Uncle, Ess, and Sedan craters, the impact of the Sedan test on the fallout deposited from the two earlier tests, and aerial radiological surveys, the CAU 367 investigation was designed to study the releases from the three crater CASs as one combined release (primary release). Corrective Action Site 10-09-03, Mud Pit, consists of two mud pits identified at CAU 367. The mud pits are considered non-test releases or other releases and were investigated independent of the three crater CASs. The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 367 dataset of investigation results was evaluated based on a data quality assessment. This assessment demonstrated the dataset is complete and acceptable for use in fulfilling the DQO data needs. Analytes detected during the CAI were evaluated against final action levels (FALs) established in this document. For the primary release, radiological doses exceeding the FAL of 25 millirem per year were not found to be present in the surface or shallow subsurface soil outside the default contamination boundary. However, it was assumed that radionuclides are present in subsurface media within each of the three craters (Sedan, Ess, and Uncle) due to prompt injection of radionuclides from the tests. Based on the assumption of radiological dose exceeding the FAL, corrective actions were undertaken that consisted of implementing a use restriction and posting warning signs at each crater CAS. These use restrictions were recorded in the FFACO database; the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Facility Information Management System; and the NNSA/NSO CAU/CAS files. With regard to other releases, no contaminants of concern were identified at the mud pits or any of the other release locations, with one exception. Potential source material in the form of lead was found at one location. A corrective action of clean closure was implemented at this location, and verification samples indicated that no further action is necessary. Therefore, NNSA/NSO provides the following recommendations: • A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 367. • Corrective Action Unit 367 should be promoted from Appendix III to Appendix IV of the FFACO.« less

Wide-area decontamination in an urban environment after radiological dispersion: A review and perspectives.

PubMed

Kaminski, Michael D; Lee, Sang Don; Magnuson, Matthew

2016-03-15

Nuclear or radiological terrorism in the form of uncontrolled radioactive contamination presents a unique challenge in the field of nuclear decontamination. Potential targets require an immediate decontamination response, or mitigation plan to limit the social and economic impact. To date, experience with urban decontamination of building materials - specifically hard, porous, external surfaces - is limited to nuclear weapon fallout and nuclear reactor accidents. Methods are lacking for performing wide-area decontamination in an urban environment so that in all release scenarios the area may be re-occupied without evaluation and/or restriction. Also lacking is experience in developing mitigation strategies, that is, methods of mitigating contamination and its resultant radiation dose in key areas during the immediate aftermath of an event and after lifesaving operations. To date, the tremendous strategy development effort primarily by the European community has focused on the recovery phase, which extends years beyond the release event. In this review, we summarize the methods and data collected over the past 70 years in the field of hard, external surface decontamination of radionuclide contaminations, with emphasis on methods suitable for response to radiological dispersal devices and their potentially unique physico-chemical characteristics. This review concludes that although a tremendous amount of work has been completed primarily by the European Community (EU) and the United Kingdom (UK), the few studies existing on each technique permit only very preliminary estimates of decontamination factors for various building materials and methods and extrapolation of those values for use in environments outside the EU and UK. This data shortage prevents us from developing an effective and detailed mitigation response plan and remediation effort. Perhaps most importantly, while the data available does include valuable information on the practical aspects of performing the various remediation methods including costs, coverage rates, manpower, pitfalls, etc., it lacks the details on lessons learned, best practices, and standard procedures, for instance, that would be required to develop a mitigation strategy. While the urban decontamination problem is difficult and there is much more research to do, the existing literature provides a framework for a response plan. Using this framework, in conjunction with computer modeling and relevant data collection, can lead to development of appropriate plans and exercises that would permit development of a mitigation and remediation response. Copyright © 2015 Elsevier B.V. All rights reserved.

Chernobyl post-accident management: the ETHOS project.

PubMed

Dubreuil, G H; Lochard, J; Girard, P; Guyonnet, J F; Le Cardinal, G; Lepicard, S; Livolsi, P; Monroy, M; Ollagnon, H; Pena-Vega, A; Pupin, V; Rigby, J; Rolevitch, I; Schneider, T

1999-10-01

ETHOS is a pilot research project supported by the radiation protection research program of the European Commission (DG XII). The project provides an alternative approach to the rehabilitation of living conditions in the contaminated territories of the CIS in the post-accident context of Chernobyl. Initiated at the beginning of 1996, this 3-y project is currently being implemented in the Republic of Belarus. The ETHOS project involves an interdisciplinary team of European researchers from the following institutions: the Centre d'etude sur l'Evaluation de la Protection dans le domaine Nucleaire CEPN (radiological protection, economics), the Institute National d'Agronomie de Paris-Grignon INAPG (agronomy, nature & life management), the Compiegne University of Technology (technological and industrial safety, social trust), and the Mutadis Research Group (sociology, social risk management), which is in charge of the scientific co-ordination of the project. The Belarussian partners in the ETHOS project include the Ministry of Emergencies of Belarus as well as the various local authorities involved with the implementation site. The ETHOS project relies on a strong involvement of the local population in the rehabilitation process. Its main goal is to create conditions for the inhabitants of the contaminated territories to reconstruct their overall quality of life. This reconstruction deals with all the day-to-day aspects that have been affected or threatened by the contamination. The project aims at creating a dynamic process whereby acceptable living conditions can be rebuilt. Radiological security is developed in the ETHOS project as part of a general improvement in the quality of life. The approach does not dissociate the social and the technical dimensions of post-accident management. This is so as to avoid radiological risk assessment and management being reduced purely to a problem for scientific experts, from which local people are excluded, and to take into consideration the problems of acceptability of decisions and the distrust of the population towards experts. These cannot be solved merely by a better communication strategy. This paper presents the main features of the methodological approach of the ETHOS project. It also explains how it is being implemented in the village of Olmany in the district of Stolyn (Brest region) in Belarus since March 1996, as well as its initial achievements.

Altitudinal characteristics of atmospheric deposition of aerosols in mountainous regions: Lessons from the Fukushima Daiichi Nuclear Power Station accident.

PubMed

Sanada, Yukihisa; Katata, Genki; Kaneyasu, Naoki; Nakanishi, Chika; Urabe, Yoshimi; Nishizawa, Yukiyasu

2018-03-15

To understand the formation process of radiologically contaminated areas in eastern Japan caused by the Fukushima Daiichi Nuclear Power Station (FDNPS) accident, the deposition mechanisms over complex topography are the key factors to be investigated. To characterize the atmospheric deposition processes of radionuclides over complex mountainous topography, we investigated the altitudinal distributions of the radiocesium deposited during the accident. In five selected areas, altitudinal characteristics of the air dose rates observed using airborne surveys were analyzed. To examine the deposition mechanisms, we supplementarily used vertical profiles of radiocesium deposition in each area calculated in the latest atmospheric dispersion model. In southern Iwate, the vertical profile of the observed air dose rate was uniform regardless of altitude. In western Tochigi, the areas with the highest levels of contamination were characteristically distributed in the middle of the mountains, while in southern Fukushima, the areas with the highest contamination levels were enhanced near the summits of mountains. In central Fukushima, high air dose rates were limited to the bottoms of basin-like valley. In the region northwest of FDNPS, the air dose rate was the highest at the bottom of valley topography and decreased gradually with altitude. The simulation results showed that calculated wet deposition and observed vertical profiles of total deposition were similar in areas of southern Iwate and northwest of FDNPS qualitatively, suggesting that the dominant deposition mechanism was wet deposition. In contrast, the atmospheric dispersion model failed to reproduce either the timing of precipitation events or vertical profiles of radiocesium deposition in three other areas. Although it was difficult to elucidate the deposition mechanisms in these areas due to uncertainties of the present model results, potential mechanisms such as cloud water deposition were still proposed based on circumstantial evidences of limited meteorological data during the early stage of the accident. Copyright © 2017 Elsevier B.V. All rights reserved.

Remediation of Centre Pier, Port Hope, Ontario: Historical, Logistical, Regulatory and Technical Challenges - 13118

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ferguson Jones, Andrea; Case, Glenn; Lawrence, Dave

Centre Pier is a 3.9 ha property owned by the Commissioners of the Port Hope Harbour in the Municipality of Port Hope, Ontario, Canada. It is centrally located on the Port Hope waterfront and is bounded on the west by the Port Hope Harbour, on the east by the Ganaraska River, on the south by Lake Ontario, and on the north by a railway corridor. The property is currently leased by the Commissioners of the Port Hope Harbour to the Cameco Corporation which owns the four onsite building that are used as warehouse space for their uranium conversion facility locatedmore » on the western side of the Harbour. Remediation of this site forms part of the Port Hope Project being undertaken by Atomic Energy of Canada Limited (AECL) and Public Works and Government Services Canada (PWGSC) as part of the Port Hope Area Initiative (PHAI). Soil impacts include radiological, metals and petroleum hydrocarbons resulting from long term historical industrial use. Radiological impacts in soil extend across most of the site primarily within the upper metre of fill. Metals-contaminated soil is present across the entire site in the underlying fill material. The metals-contaminated fill extends to a maximum depth of 2.0 m below grade at the north end of the site which is underlain by peat. However, the metals-contaminated soil could extend to the top of the bedrock on the remainder of the site. Based on the elevation of the bedrock in the adjacent river and Harbour Basin, the metals-contaminated soil may extend to a depth of 5.6 m or 6.5 m below existing grade. Petroleum-contaminated soil is present on the southeast side of the site, where a storage tank farm was previously located. Challenges include: - The complex history of the site both relating to site use and Pier construction. Pier development began in the 1800's and was undertaken by many different entities. Modifications and repairs were made over the years resulting in several different types of Pier walls and fill that must be considered during remediation. A wide variety of industrial activity on the Pier including extensive foundry operations as well as the industrial nature of the fill used to construct the Pier has resulted in extensive contamination distribution. The Pier structure will require reinforcement to permit both the remediation of the Pier and the adjacent Harbour and remediation techniques will need to be well suited to minimize disruption of wall structures as well as being able to deal with fill ranging from ash to boulders. - Multiple stakeholders are responsible for building demolition, remediation of radiological impacts, remediation of industrial impacts and the use of the site as a staging area for Harbour sediment remediation. The successful remediation of the Centre Pier will require careful negotiation and planning for the various remediation activities noted above. - The depth of contamination on the Pier would result in the complete removal of the Pier if all contamination were to be excavated. Therefore, a Risk Assessment will be conducted to determine the appropriate means for in situ risk management for materials to be left in place below a proposed depth of 1.5 m below current grade. With the concurrence of the property owners and Provincial regulators, the Risk Assessment will be undertaken in accordance with the Provincial requirements that will ensure adequate protection of the environment and future users of the site. - The end use of the Pier has yet to be confirmed by the Municipality. (authors)« less

Corrective Action Decision Document/Closure Report for Corrective Action Unit 372: Area 20 Cabriolet/Palanquin Unit Craters, Nevada National Security Site, Nevada, Revision 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Matthews, Patrick and Sloop, Christy

2011-04-01

This Corrective Action Decision Document (CADD)/Closure Report (CR) has been prepared for Corrective Action Unit (CAU) 372, Area 20 Cabriolet/Palanquin Unit Craters, located within Areas 18 and 20 at the Nevada National Security Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order (FFACO). Corrective Action Unit 372 comprises four corrective action sites (CASs): • 18-45-02, Little Feller I Surface Crater • 18-45-03, Little Feller II Surface Crater • 20-23-01, U-20k Contamination Area • 20-45-01, U-20L Crater (Cabriolet) The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation that no further corrective action ismore » needed for CAU 372 based on the implementation of the corrective action of closure in place with administrative controls at all CASs. Corrective action investigation (CAI) activities were performed from November 9, 2009, through December 10, 2010, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 372: Area 20 Cabriolet/Palanquin Unit Craters. The approach for the CAI was divided into two facets: investigation of the primary release of radionuclides and investigation of other releases (migration in washes and chemical releases). The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 372 dataset of investigation results was evaluated based on a data quality assessment. This assessment demonstrated the dataset is acceptable for use in fulfilling the DQO data needs. Investigation results were evaluated against final action levels (FALs) established in this document. A radiological dose FAL was established of 25 millirem per year based on the Remote Work Area exposure scenario (336 hours of annual exposure). Radiological doses exceeding the FAL were found to be present at all four CASs. It is assumed that radionuclide levels present within the Little Feller I and Cabriolet high contamination areas and within the craters at Palanquin and Cabriolet exceed the FAL. It is also assumed that potential source material in the form of lead bricks at Little Feller I and lead-acid batteries at Palanquin and Cabriolet exceed the FAL. Therefore, corrective actions were undertaken that consist of removing potential source material, where present, and implementing a use restriction and posting warning signs at each CAS. These use restrictions were recorded in the FFACO database; the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Facility Information Management System; and the NNSA/NSO CAU/CAS files. Therefore, NNSA/NSO provides the following recommendations: • No further corrective actions are necessary for CAU 372. • A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 372. • Corrective Action Unit 372 should be moved from Appendix III to Appendix IV of the FFACO.« less

Radiation dose from common radiological investigations and cumulative exposure in children with cystic fibrosis: an observational study from a single UK centre

PubMed Central

Ward, Rebecca; Carroll, William D; Cunningham, Paula; Ho, Sheng-Ang; Jones, Mary; Lenney, Warren; Thompson, David

2017-01-01

Objectives Cumulative radiation exposure is associated with increased risk of malignancy. This is important in cystic fibrosis (CF) as frequent imaging is required to monitor disease progression and diagnose complications. Previous estimates of cumulative radiation are outdated as the imaging was performed on older equipment likely to deliver higher radiation. Our objectives were to determine the radiation dose delivered to children during common radiological investigations using modern equipment and to identify the number of such investigations performed in a cohort of children with CF to calculate their cumulative radiation exposure. Design, setting and participants Data including age at investigation and radiation exposure measured as estimated effective dose (EED) were collected on 2827 radiological studies performed on children at one UK paediatric centre. These were combined with the details of all radiological investigations performed on 65 children with CF attending the same centre to enable calculation of each child’s cumulative radiation exposure. Results The mean EED for the common radiological investigations varied according to age. The range was 0.01–0.02 mSv for chest X-rays, 0.03–0.11 mSv for abdominal X-rays, 0.57–1.69 mSv for CT chest, 2.9–3.9 mSv for abdominal and pelvic CT, 0.20–0.21 mSv for sinus CT and 0.15–0.52 mSv for fluoroscopy-guided procedures. The mean EED was three to five times higher for helical compared with axial chest CT scans. The mean annual cumulative EED for our cohort of children with CF was 0.15 mSv/year with an estimated cumulative paediatric lifetime EED (0–18 years) of 3.5 mSv. Conclusions This study provides up-to-date estimations of the radiation exposure when using common radiological investigations. These doses and the estimates of cumulative radiation exposure in children with CF are lower than previously reported. This reflects the reduced EED associated with modern equipment and the use of age-specific scanning protocols. PMID:28827272

Results of the radiological survey at the ALCOA Research Laboratory, 600 Freeport Road, New Kensington, Pennsylvania (ANK001)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Foley, R.D.; Brown, K.S.

1992-10-01

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the ALCOA Research Laboratory, 600 Freeport Road, New Kensington, Pennsylvania. The survey was performed on November 12, 1991. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, principally [sup 238]U, as a result of work done for the Manhattan Engineer District in 1944. The survey included measurement of direct alpha and beta-gamma levels in the northeast comer of the basement of Building 29, and the collection of a debris sample frommore » a floor drain for radionuclide analysis. The survey area was used for experimental canning of uranium slugs prior to production activities at the former New Kensington Works nearby.« less

RESRAD model presentation

DOE Office of Scientific and Technical Information (OSTI.GOV)

Yu, C.; Faillace, E.; Chen, S.Y.

RESRAD was one of the multimedia models selected by the US Nuclear Regulatory Commission (NRC) to include in its workshop on radiation dose modeling and demonstration of compliance with the radiological criteria for license termination. This paper is a summary of the presentation made at the workshop and focuses on the 10 questions the NRC distributed to all participants prior to the workshop. The code selection criteria, which were solicited by the NRC, for demonstrating compliance with the license termination rule are also included. Among the RESRAD family of codes, RESRAD and RESRAD-BUILD are designed for evaluating radiological contamination inmore » soils and in buildings. Many documents have been published to support the use of these codes. This paper focuses on these two codes. The pathways considered, the databases and parameters used, quality control and quality assurance, benchmarking, verification and validation of these codes, and capabilities as well as limitations of these codes are discussed in detail.« less

Radiation and cataract.

PubMed

Rehani, Madan M; Vano, Eliseo; Ciraj-Bjelac, Olivera; Kleiman, Norman J

2011-09-01

When this paper was about to go to press, the International Commission on Radiological Protection released a statement recommending a change in the threshold dose for the eye lens and dose limits for eye for occupationally exposed persons. It is clear that the earlier published threshold for radiation cataract is no longer valid. Epidemiological studies among Chernobyl clean-up workers, A bomb survivors, astronauts, residents of contaminated buildings, radiological technicians and recent surveys of staff in interventional rooms indicate that there is an increased incidence of lens opacities at doses below 1 Gy. Nevertheless, eye lens dosimetry is at a primitive stage and needs to be developed further. Despite uncertainties concerning dose threshold and dosimetry, it is possible to significantly reduce the risk of radiation cataract through the use of appropriate eye protection. By increasing awareness among those at risk and better adoption and increased usage of protective measures, radiation cataract can become preventable despite lowering of dose limits.

Proposed method to calculate FRMAC intervention levels for the assessment of radiologically contaminated food and comparison of the proposed method to the U.S. FDA's method to calculate derived intervention levels

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kraus, Terrence D.; Hunt, Brian D.

This report reviews the method recommended by the U.S. Food and Drug Administration for calculating Derived Intervention Levels (DILs) and identifies potential improvements to the DIL calculation method to support more accurate ingestion pathway analyses and protective action decisions. Further, this report proposes an alternate method for use by the Federal Emergency Radiological Assessment Center (FRMAC) to calculate FRMAC Intervention Levels (FILs). The default approach of the FRMAC during an emergency response is to use the FDA recommended methods. However, FRMAC recommends implementing the FIL method because we believe it to be more technically accurate. FRMAC will only implement themore » FIL method when approved by the FDA representative on the Federal Advisory Team for Environment, Food, and Health.« less

Radiological survey of the Norfolk Naval Station, the Norfolk Naval Shipyard, and Newport News Shipbuilding. Final report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Sensintaffar, E.L.; Blanchard, R.L.

1988-09-01

The report presents results of the survey conducted by EERF personnel to assess levels of environmental radioactivity resulting from maintenance and operation of nuclear-powered warships at the Norfolk Naval Station, Norfolk Naval Shipyard and Newport News Shipbuilding. The purpose of the survey was to determine if activities related to nuclear-powered warships resulted in release of radionuclides which may contribute to significant population exposure or contamination of the environment.

DOE Office of Scientific and Technical Information (OSTI.GOV)

None, None

Operations of Sandia National Laboratories, Nevada (SNL/NV) at the Tonopah Test Range (TTR) resulted in no planned point radiological releases during 1996. Other releases from SNL/NV included diffuse transuranic sources consisting of the three Clean Slate sites. Air emissions from these sources result from wind resuspension of near-surface transuranic contaminated soil particulates. The total area of contamination has been estimated to exceed 20 million square meters. Soil contamination was documented in an aerial survey program in 1977 (EG&G 1979). Surface contamination levels were generally found to be below 400 pCi/g of combined plutonium-238, plutonium-239, plutonium-240, and americium-241 (i.e., transuranic) activity.more » Hot spot areas contain up to 43,000 pCi/g of transuranic activity. Recent measurements confirm the presence of significant levels of transuranic activity in the surface soil. An annual diffuse source term of 0.39 Ci of transuranic material was calculated for the cumulative release from all three Clean Slate sites. A maximally exposed individual dose of 1.1 mrem/yr at the TTR airport area was estimated based on the 1996 diffuse source release amounts and site-specific meteorological data. A population dose of 0.86 person-rem/yr was calculated for the local residents. Both dose values were attributable to inhalation of transuranic contaminated dust.« less

Application of the Commission's recommendations: the 2013-2017 Committee 4 programme of work.

PubMed

Lochard, J

2015-06-01

Committee 4 of the International Commission on Radiological Protection (ICRP) is responsible for developing principles, recommendations, and guidance on the protection of people against radiation exposure, and to consider their practical application in all exposure situations. Currently, the Committee's efforts are focused on the completion of a series of future ICRP publications on the implementation of its 2007 Recommendations to the various existing exposure situations. A report on protection against radon exposure was published recently (ICRP Publication 126), and two documents on protection against cosmic radiation in aviation, and naturally occurring radioactive material are under development. The programme of work for the forthcoming 2013-2017 period comprises the update of ICRP Publication 109 on protection of people in emergency exposure situations, and the update of ICRP Publication 111 on protection of people living in long-term contaminated areas after a nuclear accident, as well as the development of a future ICRP publication on the ethics of radiological protection. It also includes the preparation of task groups on the application of the Commission's recommendations for contaminated sites from past activities and for surface and near-surface disposal of radioactive waste. Another important task for Committee 4 will be to develop a reflection on the tolerability of risk from radiation. © The International Society for Prosthetics and Orthotics Reprints and permissions: sagepub.co.uk/journalsPermissions.nav.

Data analysis and review of radiology services at Glasgow 2014 Commonwealth Games.

PubMed

Bethapudi, Sarath; Ritchie, David; Bongale, Santosh; Gordon, Jonny; MacLean, John; Mendl, Liz

2015-10-01

Medical services at the Glasgow 2014 Commonwealth Games (CWG) were provided though a purpose-built medical polyclinic, which had a fully equipped radiology department along with other services, set up within the main Games Village. Data analysis of radiology services offered at CWG has not been published before. Imaging services within the polyclinic, Athletes Village, Glasgow 2014 CWG. The aim of the paper is to analyse data on radiological investigations and assess the demand and distribution of workload on imaging services at CWG 2014. Data on radiology investigations at the CWG 2014 was retrieved from the Carestream picture archiving and communication system (PACS) and Pharmasys (CWG official centralised electronic database system) and analysed. Six hundred ninety-seven diagnostic and interventional procedures were performed. Of these 37.9% were magnetic resonance imaging (MRI) scans, 22% were diagnostic ultrasound (US) examinations, 33.1% were radiographs, 4.3% were computed tomography (CT) scans and 2.7% were imaging-guided interventional procedures. 88% of imaging was performed on athletes and the remainder were performed on team officials and workforce. Demand on radiology services gradually picked up through the pre-competition period and peaked half way through the CWG. Radiology played a vital role in the successful provision of medical services at the Glasgow 2014 CWG. High demand on imaging services can be expected at major international sporting events and therefore pre-event planning is vital. Having back-up facilities in case of technical failure should be given due importance when planning radiology services at future CWG events.

An outbreak of extrinsic alveolitis at a car engine plant.

PubMed

Dawkins, Paul; Robertson, Alastair; Robertson, Wendy; Moore, Vicky; Reynolds, John; Langman, Gerald; Robinson, Edward; Harris-Roberts, Joanne; Crook, Brian; Burge, Sherwood

2006-12-01

Twelve workers from a car engine-manufacturing plant presented with extrinsic allergic alveolitis (EAA), with heterogeneous clinical, radiological and pathological findings. They were exposed to metalworking fluids (MWF) that cooled, lubricated and cleaned the machines. They were characterized by history, examination, lung function testing, radiology, bronchoscopic lavage, lung biopsy and serology. Sera were tested for precipitins to a crude extract of used MWF and to reference cultures of bacteria suspected to be implicated. All were males and none were current smokers. All had dyspnoea, many had weight loss and cough, but only half had influenza-like symptoms. Only half had auscultatory crackles. Five had peak flow variability, four with an occupational component. There was overall restrictive spirometry, decreased lung volumes and reduced gas transfers. Ten had radiological evidence of interstitial lung disease. Seven (of eight) had lymphocytosis on bronchial lavage, including the two with inconclusive radiology. Seven (of 11) had lung biopsies showing inflammatory infiltrates, two with fibrosis and one with granulomas. Three (of 11) had strong positive precipitins to an extract of the used MWF from the plant. Molecular biological analysis of the MWF revealed Acinetobacter and Ochrobactrum. Precipitins to Acinetobacter were detected in seven of 11 workers tested (and four of 11 control workers). Precipitins to Ochrobactrum were detected in three of 11 workers tested (and three of 11 control workers). This is the largest series reported in Europe of EAA due to an aerosol of microbiologically contaminated MWF in heavy manufacturing industry.

Preliminary radiological safety assessment for decommissioning of thoria dissolver of the ²³³U pilot plant, Trombay.

PubMed

Priya, S; Srinivasan, P; Gopalakrishnan, R K

2012-01-01

The thoria dissolver, used for separation of (233)U from reactor-irradiated thorium metal and thorium oxide rods, is no longer operational. It was decided to carry out assessment of the radiological status of the dissolver cell for planning of the future decommissioning/dismantling operations. The dissolver interiors are expected to be contaminated with the dissolution remains of irradiated thorium oxide rods in addition to some of the partially dissolved thoria pellets. Hence, (220)Rn, a daughter product of (228)Th is of major radiological concern. Airborne activity of thoron daughters (212)Pb (Th-B) and (212)Bi (Th-C) was estimated by air sampling followed by high-resolution gamma spectrometry of filter papers. By measuring the full-energy peaks counts in the energy windows of (212)Pb, (212)Bi and (208)Tl, concentrations of thoron progeny in the sampled air were estimated by applying the respective intrinsic peak efficiency factors and suitable correction factors for the equilibration effects of (212)Pb and (212)Bi in the filter paper during the delay between sampling and counting. Then the thoron working level (TWL) was evaluated using the International Commission on Radiological Protection (ICRP) methodology. Finally, the potential effective dose to the workers, due to inhalation of thoron and its progeny during dismantling operations was assessed by using dose conversion factors recommended by ICRP. Analysis of filter papers showed a maximum airborne thoron progeny concentration of 30 TWLs inside the dissolver.

Environmental risk management for radiological accidents: integrating risk assessment and decision analysis for remediation at different spatial scales.

PubMed

Yatsalo, Boris; Sullivan, Terrence; Didenko, Vladimir; Linkov, Igor

2011-07-01

The consequences of the Tohuku earthquake and subsequent tsunami in March 2011 caused a loss of power at the Fukushima Daiichi nuclear power plant, in Japan, and led to the release of radioactive materials into the environment. Although the full extent of the contamination is not currently known, the highly complex nature of the environmental contamination (radionuclides in water, soil, and agricultural produce) typical of nuclear accidents requires a detailed geospatial analysis of information with the ability to extrapolate across different scales with applications to risk assessment models and decision making support. This article briefly summarizes the approach used to inform risk-based land management and remediation decision making after the Chernobyl, Soviet Ukraine, accident in 1986. Copyright © 2011 SETAC.

RESRAD for Radiological Risk Assessment. Comparison with EPA CERCLA Tools - PRG and DCC Calculators

DOE Office of Scientific and Technical Information (OSTI.GOV)

Yu, C.; Cheng, J. -J.; Kamboj, S.

The purpose of this report is two-fold. First, the risk assessment methodology for both RESRAD and the EPA’s tools is reviewed. This includes a review of the EPA’s justification for 2 using a dose-to-risk conversion factor to reduce the dose-based protective ARAR from 15 to 12 mrem/yr. Second, the models and parameters used in RESRAD and the EPA PRG and DCC Calculators are compared in detail, and the results are summarized and discussed. Although there are suites of software tools in the RESRAD family of codes and the EPA Calculators, the scope of this report is limited to the RESRADmore » (onsite) code for soil contamination and the EPA’s PRG and DCC Calculators also for soil contamination.« less

Evidence Theory Based Uncertainty Quantification in Radiological Risk due to Accidental Release of Radioactivity from a Nuclear Power Plant

NASA Astrophysics Data System (ADS)

Ingale, S. V.; Datta, D.

2010-10-01

Consequence of the accidental release of radioactivity from a nuclear power plant is assessed in terms of exposure or dose to the members of the public. Assessment of risk is routed through this dose computation. Dose computation basically depends on the basic dose assessment model and exposure pathways. One of the exposure pathways is the ingestion of contaminated food. The aim of the present paper is to compute the uncertainty associated with the risk to the members of the public due to the ingestion of contaminated food. The governing parameters of the ingestion dose assessment model being imprecise, we have approached evidence theory to compute the bound of the risk. The uncertainty is addressed by the belief and plausibility fuzzy measures.

Status Update on the NCRP Scientific Committee SC 5-1 Report: Decision Making for Late-Phase Recovery from Nuclear or Radiological Incidents - 13450

DOE Office of Scientific and Technical Information (OSTI.GOV)

Chen, S.Y.

2013-07-01

In August 2008, the U.S. Department of Homeland Security (DHS) issued its final Protective Action Guide (PAG) for radiological dispersal device (RDD) and improvised nuclear device (IND) incidents. This document specifies protective actions for public health during the early and intermediate phases and cleanup guidance for the late phase of RDD or IND incidents, and it discusses approaches to implementing the necessary actions. However, while the PAG provides specific guidance for the early and intermediate phases, it prescribes no equivalent guidance for the late-phase cleanup actions. Instead, the PAG offers a general description of a complex process using a site-specificmore » optimization approach. This approach does not predetermine cleanup levels but approaches the problem from the factors that would bear on the final agreed-on cleanup levels. Based on this approach, the decision-making process involves multifaceted considerations including public health, the environment, and the economy, as well as socio-political factors. In an effort to fully define the process and approach to be used in optimizing late-phase recovery and site restoration following an RDD or IND incident, DHS has tasked the NCRP with preparing a comprehensive report addressing all aspects of the optimization process. Preparation of the NCRP report is a three-year (2010-2013) project assigned to a scientific committee, the Scientific Committee (SC) 5-1; the report was initially titled, Approach to Optimizing Decision Making for Late- Phase Recovery from Nuclear or Radiological Terrorism Incidents. Members of SC 5-1 represent a broad range of expertise, including homeland security, health physics, risk and decision analysis, economics, environmental remediation and radioactive waste management, and communication. In the wake of the Fukushima nuclear accident of 2011, and guided by a recent process led by the White House through a Principal Level Exercise (PLE), the optimization approach has since been expanded to include off-site contamination from major nuclear power plant accidents as well as other nuclear or radiological incidents. The expanded application under the current guidance has thus led to a broadened scope of the report, which is reflected in its new title, Decision Making for Late-Phase Recovery from Nuclear or Radiological Incidents. The NCRP report, which is due for publication in 2013, will substantiate the current DHS guidance by clarifying and elaborating on the processes required for the development and implementation of procedures for optimizing decision making for late-phase recovery, enabling the establishment of cleanup goals on a site-specific basis. The report will contain a series of topics addressing important issues related to the long-term recovery from nuclear or radiological incidents. Special topics relevant to supporting the optimization of the decision-making process will include cost-benefit analysis, radioactive waste management, risk communication, stakeholder interaction, risk assessment, and decontamination approaches and techniques. The committee also evaluated past nuclear and radiological incidents for their relevance to the report, including the emerging issues associated with the Fukushima nuclear accident. Thus, due to the commonality of the late-phase issues (such as the potential widespread contamination following an event), the majority of the information pertaining to the response in the late-phase decision-making period, including site-specific optimization framework and approach, could be used or adapted for use in case of similar situations that are not due to terrorism, such as those that would be caused by major nuclear facility accidents or radiological incidents. To ensure that the report and the NCRP recommendations are current and relevant to the effective implementation of federal guidance, SC 5-1 has actively coordinated with the agencies of interest and other relevant stakeholders throughout the duration of the project. The resulting report will be an important resource to guide those involved in late-phase recovery efforts following a nuclear or radiological incident. (authors)« less

Impact assessment of ionizing radiation on human and non-human biota from the vicinity of a near-surface radioactive waste repository.

PubMed

Nedveckaite, T; Gudelis, A; Vives i Batlle, J

2013-05-01

This work describes the radiological assessment of the near-surface Maisiagala radioactive waste repository (Lithuania) over the period 2005-2012, with focus on water pathways and special emphasis on tritium. The study includes an assessment of the effect of post-closure upgrading, the durability of which is greater than 30 years. Both human and terrestrial non-human biota are considered, with local low-intensity forestry and small farms being the area of concern. The radiological exposure was evaluated using the RESRAD-OFFSITE, RESRAD-BIOTA and ERICA codes in combination with long-term data from a dedicated environmental monitoring programme. All measurements were performed at the Lithuanian Institute of Physics as part of this project. It is determined that, after repository upgrading, radiological exposure to humans are significantly lower than the human dose constraint of 0.2 mSv/year valid in the Republic of Lithuania. Likewise, for non-human biota, dose rates are below the ERICA/PROTECT screening levels. The potential annual effective inhalation dose that could be incurred by the highest-exposed human individual (which is due to tritiated water vapour airborne release over the most exposed area) does not exceed 0.1 μSv. Tritium-labelled drinking water appears to be the main pathway for human impact, representing about 83 % of the exposure. Annual committed effective dose (CED) values for members of the public consuming birch sap as medical practice are calculated to be several orders of magnitude below the CEDs for the same location associated with drinking of well water. The data presented here indicate that upper soil-layer samples may not provide a good indication of potential exposure to terrestrial deep-rooted trees, as demonstrated by an investigation of stratified (3)H in soil moisture, expressed on a wet soil mass basis, in an area with subsurface contamination.

Defining the diagnostic algorithm in pancreatic cancer.

PubMed

Horwhat, John David; Gress, Frank G

2004-07-01

Most patients with pancreatic cancer present with a mass on radiologic studies, however, not every pancreatic mass is cancer. Since radiological studies alone are insufficient to establish the diagnosis of a pancreatic mass and patient management depends on a definitive diagnosis; confirmatory cytology or histology is usually required. As a minimally invasive procedure, EUS and EUS FNA avoid the risk of cutaneous or peritoneal contamination that may occur with CT or US-guided investigations and is less invasive than surgical interventions. As a result, EUS FNA of pancreatic masses is becoming the standard for obtaining cytological diagnosis. This chapter presents an EUS-based diagnostic algorithm for the evaluation of pancreatic lesions and is based upon a review of the pertinent literature in the field of pancreatic endosonography that has been the most influential in helping to guide this evolving field. Realizing there is much overlap among the EUS characteristics of various pancreatic lesions, for the sake of simplicity we have structured our discussion in broad terms of solid versus cystic lesions and discuss various pancreatic lesions within this framework. The additional contributors to this round table discussion have been asked to provide a more dedicated, focused discussion of the various subcategories of pancreatic lesions in greater detail than we could hope to achieve here. We provide this final contribution to the round table as a means of bringing the discussion back to the big picture of pancreatic lesions, rather than trying to hone in on the fine details of any one subclass.

Diagnosis of cystocele--the correlation between clinical and radiological evaluation.

PubMed

Altman, Daniel; Mellgren, Anders; Kierkegaard, Jonas; Zetterström, Jan; Falconer, Christian; López, Annika

2004-01-01

In patients with genital prolapse involving several compartments simultaneously, radiologic investigation can be used to complement the clinical assessment. Contrast medium in the urinary bladder enables visualization of the bladder base at cystodefecoperitoneography (CDP). The aim of the present study was to evaluate the correlation between clinical examination using the Pelvic Organ Prolapse Quantification system (POP-Q) and CDP. Thirty-three women underwent clinical assessment and CDP. Statistical analysis using Pearson's correlation coefficient ( r) demonstrated a wide variability between the current definition of cystocele at CDP and POP-Q ( r=0.67). An attempt to provide an alternative definition of cystocele at CDP had a similar outcome ( r=0.63). The present study demonstrates a moderate correlation between clinical and radiologic findings in patients with anterior vaginal wall prolapse. It does not support the use of bladder contrast at radiologic investigation in the routine preoperative assessment of patients with genital prolapse.

Experimental Fuels Facility Re-categorization Based on Facility Segmentation

DOE Office of Scientific and Technical Information (OSTI.GOV)

Reiss, Troy P.; Andrus, Jason

The Experimental Fuels Facility (EFF) (MFC-794) at the Materials and Fuels Complex (MFC) located on the Idaho National Laboratory (INL) Site was originally constructed to provide controlled-access, indoor storage for radiological contaminated equipment. Use of the facility was expanded to provide a controlled environment for repairing contaminated equipment and characterizing, repackaging, and treating waste. The EFF facility is also used for research and development services, including fuel fabrication. EFF was originally categorized as a LTHC-3 radiological facility based on facility operations and facility radiological inventories. Newly planned program activities identified the need to receive quantities of fissionable materials in excessmore » of the single parameter subcritical limit in ANSI/ANS-8.1, “Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors” (identified as “criticality list” quantities in DOE-STD-1027-92, “Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports,” Attachment 1, Table A.1). Since the proposed inventory of fissionable materials inside EFF may be greater than the single parameter sub-critical limit of 700 g of U-235 equivalent, the initial re-categorization is Hazard Category (HC) 2 based upon a potential criticality hazard. This paper details the facility hazard categorization performed for the EFF. The categorization was necessary to determine (a) the need for further safety analysis in accordance with LWP-10802, “INL Facility Categorization,” and (b) compliance with 10 Code of Federal Regulations (CFR) 830, Subpart B, “Safety Basis Requirements.” Based on the segmentation argument presented in this paper, the final hazard categorization for the facility is LTHC-3. Department of Energy Idaho (DOE-ID) approval of the final hazard categorization determined by this hazard assessment document (HAD) was required per the DOE-ID Supplemental Guidance for DOE-STD-1027-92 based on the proposed downgrade of the initial facility categorization of Hazard Category 2.« less

Evaluation of mammography equipment performance, dose and image quality in five Latin American countries

NASA Astrophysics Data System (ADS)

Brandan, M.-E.; Ruiz-Trejo, C.; Caspani, C. E. M.; Fleitas, I.; de-la-Mora, R.; Miranda, A. A.; Plazas, M.-C.; Betancourt, C.-M.; Borras, C.

2001-10-01

Under the auspices of PAHO/WHO, a multicentric investigation is carried out in five Latin American countries. Its aim is to correlate quality indicators of radiology services with the accuracy of the radiological interpretation as determined by a panel of radiology experts. We present preliminary results from mammographic imaging facilities. Evaluation of the equipment performance and dose measurements in 21 mammographic units show that, on the average, 75% of the units comply with recommendations issued by various organizations. An independent evaluation of the quality of the clinical images show strong variations among the different radiological services.

Evaluation and implementation of a soil blending application

DOE Office of Scientific and Technical Information (OSTI.GOV)

Honerlah, H.; Sendra, D.; Zafran, A.

2007-07-01

With the Nuclear Regulatory Commission (NRC) issuing guidance on the 'Use of Intentional Mixing of Contaminated Soil' (SECY-04-0035) dated 1 March 2004, an opportunity to blend higher level radiologically contaminated soils with that of lower activity from the Colonie Formerly Utilized Sites Remedial Action Program (FUSRAP) site became available. Shaw Environmental, under contract with United States Army Corps of Engineers (USACE) to remediate the Colonie site, was tasked to blend soils of higher radioactivity (> 6.29 Bq/g or 170 pCi/g) concentration with soils of lower radioactivity concentration (< 6.29 Bq/g or 170 pCi/g). A mass balance formula approach was usedmore » to determine the proper soil blending ratio. This blending process enabled soils to meet the Waste Acceptance Criteria (WAC) of a specific disposal facility. All blended waste streams were treated to stabilize lead, removing the hazardous waste code D008, and to meet appropriate Resource Conservation Recovery Act (RCRA) requirements and land disposal restrictions. The initial blending on-site was conducted with a 2,485 m{sup 3} (3,250 yd{sup 3}) stockpile of higher concentration soils being blended with lower concentration soils. The lower concentration soils were excavated, staged and sampled into 191 m{sup 3} (250 yd{sup 3}) stockpiles. The ratio for this blending was based on the average radiological concentration of the large stockpile being blended and average concentrations of the individual 191 m{sup 3} (250 yd{sup 3}) piles of lower radiological concentration using a mass balance approach. Once a new 191 m{sup 3} (250 yd{sup 3}) stockpile was created with blended soils it was sampled to insure it met the WAC of Facility A. After the large stockpile had been successfully blended and additional in-situ soils of higher concentration were excavated, they were blended using a similar mass balance approach. For the newly excavated soils, each of the individual piles radiological concentrations was used to determine the specific blending ratio. The blending process took place to lower the disposal costs for the project. By sending the soils to Facility A (RCRA part C permitted) vs. Facility B (Part 61 NRC licensed), a cost savings of over 1.56 million dollars was realized. Prior to commencing the blending of soils, USACE coordinated discussions with appropriate state and federal governmental organizations. (authors)« less

Independent Verification Survey of the Clean Coral Storage Pile at the Johnston Atoll Plutonium Contaminated Soil Remediation Project

DOE Office of Scientific and Technical Information (OSTI.GOV)

Wilson-Nichols, M.J.; Egidi, P.V.; Roemer, E.K.

2000-09-01

f I The Oak Ridge National Laboratory (ORNL) Environmental Technology Section conducted an independent verification (IV) survey of the clean storage pile at the Johnston Atoll Plutonium Contaminated Soil Remediation Project (JAPCSRP) from January 18-25, 1999. The goal of the JAPCSRP is to restore a 24-acre area that was contaminated with plutonium oxide particles during nuclear testing in the 1960s. The selected remedy was a soil sorting operation that combined radiological measurements and mining processes to identify and sequester plutonium-contaminated soil. The soil sorter operated from about 1990 to 1998. The remaining clean soil is stored on-site for planned beneficialmore » use on Johnston Island. The clean storage pile currently consists of approximately 120,000 m3 of coral. ORNL conducted the survey according to a Sampling and Analysis Plan, which proposed to provide an IV of the clean pile by collecting a minimum number (99) of samples. The goal was to ascertain wi th 95% confidence whether 97% of the processed soil is less than or equal to the accepted guideline (500-Bq/kg or 13.5-pCi/g) total transuranic (TRU) activity.« less

The development of radioactive sample surrogates for training and exercises

DOE Office of Scientific and Technical Information (OSTI.GOV)

Martha Finck; Bevin Brush; Dick Jansen

2012-03-01

The development of radioactive sample surrogates for training and exercises Source term information is required for to reconstruct a device used in a dispersed radiological dispersal device. Simulating a radioactive environment to train and exercise sampling and sample characterization methods with suitable sample materials is a continued challenge. The Idaho National Laboratory has developed and permitted a Radioactive Response Training Range (RRTR), an 800 acre test range that is approved for open air dispersal of activated KBr, for training first responders in the entry and exit from radioactively contaminated areas, and testing protocols for environmental sampling and field characterization. Membersmore » from the Department of Defense, Law Enforcement, and the Department of Energy participated in the first contamination exercise that was conducted at the RRTR in the July 2011. The range was contaminated using a short lived radioactive Br-82 isotope (activated KBr). Soil samples contaminated with KBr (dispersed as a solution) and glass particles containing activated potassium bromide that emulated dispersed radioactive materials (such as ceramic-based sealed source materials) were collected to assess environmental sampling and characterization techniques. This presentation summarizes the performance of a radioactive materials surrogate for use as a training aide for nuclear forensics.« less

Disclosing neuroimaging incidental findings: a qualitative thematic analysis of health literacy challenges.

PubMed

Rancher, Caitlin E; Shoemaker, Jody M; Petree, Linda E; Holdsworth, Mark; Phillips, John P; Helitzer, Deborah L

2016-10-11

Returning neuroimaging incidental findings (IF) may create a challenge to research participants' health literacy skills as they must interpret and make appropriate healthcare decisions based on complex radiology jargon. Disclosing IF can therefore present difficulties for participants, research institutions and the healthcare system. The purpose of this study was to identify the extent of the health literacy challenges encountered when returning neuroimaging IF. We report on findings from a retrospective survey and focus group sessions with major stakeholders involved in disclosing IF. We surveyed participants who had received a radiology report from a research study and conducted focus groups with participants, parents of child participants, Institutional Review Board (IRB) members, investigators and physicians. Qualitative thematic analyses were conducted using standard group-coding procedures and descriptive summaries of health literacy scores and radiology report outcomes are examined. Although participants reported high health literacy skills (m = 87.3 on a scale of 1-100), 67 % did not seek medical care when recommended to do so; and many participants in the focus groups disclosed they could not understand the findings described in their report. Despite their lack of understanding, participants desire to have information about their radiology results, and the investigators feel ethically inclined to return findings. The language in clinically useful radiology reports can create a challenge for participants' health literacy skills and has the potential to negatively impact the healthcare system and investigators conducting imaging research. Radiology reports need accompanying resources that explain findings in lay language, which can help reduce the challenge caused by the need to communicate incidental findings.

Investigating the Relationship of Sociodemographic and Personality Factors to Faculty Perceptions and Motivations Regarding the Use of Online Instruction in Radiologic and Imaging Sciences

ERIC Educational Resources Information Center

Washington, Angela E.

2012-01-01

The purpose of this quantitative correlational study was to investigate the relationship of sociodemographic and personality traits to faculty perceptions and motivations regarding the use of online instruction in radiologic and imaging sciences. A faculty perception and motivations survey of online instruction was administered online in order to…

Addendum to the Closure Report for Corrective Action Unit 214: Bunkers and Storage Areas Nevada Test Site, Nevada, Revision 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Lynn Kidman

This document constitutes an addendum to the September 2006, Closure Report for Corrective Action Unit 214: Bunkers and Storage Areas as described in the document Recommendations and Justifications for Modifications for Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Federal Facility Agreement and Consent Order (UR Modification document) dated February 2008. The UR Modification document was approved by NDEP on February 26, 2008. The approval of the UR Modification document constituted approval of each of the recommended UR modifications. In conformance with the UR Modification document, this addendum consists of: • Thismore » cover page that refers the reader to the UR Modification document for additional information • The cover and signature pages of the UR Modification document • The NDEP approval letter • The corresponding section of the UR Modification document This addendum provides the documentation justifying the cancellation of the URs for: • CAS 25-23-01, Contaminated Materials • CAS 25-23-19, Radioactive Material Storage These URs were established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and were based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996; as amended August 2006). Since these URs were established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, these URs were re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006c). This re-evaluation consisted of comparing the original data (used to define the need for the URs) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove these URs because contamination is not present at these sites above the risk-based FALs. Requirements for inspecting and maintaining these URs will be canceled, and the postings and signage at each site will be removed. Fencing and posting may be present at these sites that are unrelated to the FFACO URs such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004f). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at these sites.« less

Wide Area Recovery and Resiliency Program (WARRP) Decon-13 Subject Matter Expert Meeting

DTIC Science & Technology

2012-08-14

Japan, Chernobyl , Goiania Waste Screening Workshop August 14, 2012 Edward A. Tupin Center for Radiological Emergency Response Radiation Protection...Total release -10% - 20% of releases from Chernobyl (37 PBq = 1,000,000 Curies) L~:lCl.~== ~ Wide Ar£>a Contamination ~ MEXT data as of S£>pt£>mber...and longer-tenn interim storage - disposal likely will take more time 2 1 On April 26, 1986, Unit 4 of the Chernobyl Nuclear Power Plant suffered

Characterization report for Building 301 Hot Cell Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1998-07-01

During the period from October, 1997, through March, 1998, ANL-E Health Physics conducted a pre-D and D characterization of Building 301, referred to as the Hot Cell Facility. While primary emphasis was placed on radiological evaluation, the presence of non-nuclear hazardous and toxic material was also included in the scope of the characterization. This is one of the early buildings on the ANL-E site, and was heavily used in the 1950`s and 1960`s for various nuclear reaction and reactor design studies. Some degree of cleanup and contamination fixation was done in the 1970`s, so that the building could be usedmore » with a minimum of risk of personnel contamination. Work records are largely nonexistent for the early history of the building, so that any assumptions about extent and type of contamination had to be kept very open in the survey planning process. The primary contaminant was found to be painted-over Cs-137 embedded in the concrete floors, although a variety of other nuclides consistent with the work said to have been performed were found in smaller quantities. Due to leaks and drips through the floor, a relatively modest amount of soil contamination was found in the service trench under the building, not penetrating deeply. Two contaminated, disconnected drain lines leaving the building could not be traced by site records, and remain a problem for remediation. The D and D Characterization Plan was fulfilled.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Haudebourg, Raphael; Fichet, Pascal; Goutelard, Florence

The detection (location and quantification) of nuclear facilities to be dismantled possible contamination with low-range particles emitters ({sup 3}H, other low-energy β emitters, a emitters) remains a tedious and expensive task. Indeed, usual remote counters show a too low sensitivity to these non-penetrating radiations, while conventional wipe tests are irrelevant for fixed radioactivity evaluation. The only method to accurately measure activity levels consists in sampling and running advanced laboratory analyses (spectroscopy, liquid scintillation counting, pyrolysis...). Such measurements generally induce sample preparation, waste production (destructive analyses, solvents), nuclear material transportation, long durations, and significant labor mobilization. Therefore, the search for themore » limitation of their number and cost easily conflicts with the necessity to perform a dense screening for sampling (to maximize the representativeness of the samples), in installations of thousands of square meters (floors, wells, ceilings), plus furniture, pipes, and other wastes. To overcome this contradiction, Digital Autoradiography (D. A.) was re-routed from bio molecular research to radiological mapping of nuclear installations under dismantling and to waste and sample analysis. After in-situ exposure to the possibly-contaminated areas to investigate, commercial reusable radiosensitive phosphor screens (of a few 100 cm{sup 2}) were scanned in the proper laboratory device and sharp quantitative images of the radioactivity could be obtained. The implementation of geostatistical tools in the data processing software enabled the exhaustive characterization of concrete floors at a rate of 2 weeks / 100 m{sup 2}, at lowest costs. Various samples such as drilled cores, or tank and wood pieces, were also successfully evaluated with this method, for decisive results. Thanks to the accurate location of potential contamination spots, this approach ensures relevant and representative sampling for further laboratory analyses and should be inserted in the range of common tools used in dismantling. (authors)« less

Tuberculosis in Newborns: The Lessons of the “Lübeck Disaster” (1929–1933)

PubMed Central

Fox, Gregory J.; Orlova, Marianna; Schurr, Erwin

2016-01-01

In an accident later known as the Lübeck disaster, 251 neonates were orally given three doses of the new Bacille Calmette–Guérin (BCG) antituberculosis (TB) vaccine contaminated with Mycobacterium tuberculosis. A total of 173 infants developed clinical or radiological signs of TB but survived the infection, while 72 died from TB. While some blamed the accident on BCG itself by postulating reversion to full virulence, such a possibility was conclusively disproven. Rather, by combining clinical, microbiological, and epidemiological data, the chief public health investigator Dr. A. Moegling concluded that the BCG vaccine had been contaminated with variable amounts of fully virulent M. tuberculosis. Here, we summarize the conclusions drawn by Moegling and point out three lessons that can be learned. First, while mortality was high (approximately 29%), the majority of neonates inoculated with M. tuberculosis eventually overcame TB disease. This shows the high constitutional resistance of humans to the bacillus. Second, four semiquantitative levels of contamination were deduced by Moegling from the available data. While at low levels of M. tuberculosis there was a large spread of clinical phenotypes reflecting a good degree of innate resistance to TB, at the highest dose, the majority of neonates were highly susceptible to TB. This shows the dominating role of dose for innate resistance to TB. Third, two infants inoculated with the lowest dose nevertheless died of TB, and their median time from inoculation to death was substantially shorter than for those who died after inoculation with higher doses. This suggests that infants who developed disease after low dose inoculation are those who are most susceptible to the disease. We discuss some implications of these lessons for current study of genetic susceptibility to TB. PMID:26794678

Microbial flora on cell-phones in an orthopedic surgery room before and after decontamination.

PubMed

Murgier, J; Coste, J-F; Cavaignac, E; Bayle-Iniguez, X; Chiron, P; Bonnevialle, P; Laffosse, J-M

2016-12-01

Cell-phones are the typical kind of object brought into the operating room from outside by hospital staff. A great effort is made to reduce the level of potentially contaminating bacteria in the operating room, and introducing these devices may run counter to good practice. The study hypothesis was that cell-phones are colonized by several strains of bacteria and may constitute a source of nosocomial contamination. The main study objective was to screen for bacterial colonies on the surfaces of cell-phones introduced in an orthopedic surgery room. The secondary objective was to assess the efficacy of decontamination. Samples were taken from the cell-phones of hospital staff (surgeons, anaesthetists, nurses, radiology operators, and external medical representatives) entering the operating room of the university hospital center orthopedic surgery department, Toulouse (France). Sampling used Count Tact ® contact gel, without wiping the phone down in advance. Both sides of the phone were sampled, before and after decontamination with a pad imbibed with 0.25% Surfanios ® Premium disinfectant. A nasal sample was also taken to investigate the correlation between Staphylococcus aureus in the nasal cavities and on the cell-phone. Fifty-two cell-phones were sampled. Before decontamination, the mean number of colony-forming units (CFU) was 258 per phone (range, 0-1,664). After decontamination, it was 127 (range, 0-800) (P=0.0001). Forty-nine cell-phones bore CFUs before decontamination (94%), and 39 after (75%) (P=0.02). Cell-phones are CFU carriers and may thus lead to contamination. Guidelines should be drawn up to encourage cleaning phones regularly and to reduce levels of use within the operating room. Copyright © 2016 Elsevier Masson SAS. All rights reserved.

Summary of the proceedings of the International Forum 2017: "Position of interventional radiology within radiology".

PubMed

2018-04-01

The International Forum is held once a year by the ESR and its international radiological partner societies with the aim to address and discuss selected topics of global relevance in radiology. In 2017, the issue of the position of interventional radiology (IR) within radiology was analysed. IR is expanding because of the increased patient demand for minimally invasive therapies performed under imaging guidance, and its success in improving patient outcomes, reducing in-hospital stays, reducing morbidity and mortality of treatment in many organs and organ-systems. Despite the many successes of IR, public awareness about it is quite low. IR requires specific training and, in most countries, the majority of interventional radiologists do not dedicate their time completely to IR but perform diagnostic radiology investigations as well. Turf battles in IR are common in many countries. To preserve and keep IR within radiology, it is necessary to focus more on direct and longitudinal patient care. Having beds dedicated to IR within radiology departments is very important to increase clinical involvement of interventional radiologists. IR procedures fit perfectly within "value-based healthcare", but the metrics have to be developed. • IR should stay a prominent subspecialty within radiology. • Dedicated IR training pathways are mandatory. • Measures to increase recruitment of young doctors to IR and to increase public awareness of IR are needed. • Beds dedicated to IR within radiology departments are important in order to increase clinical involvement of interventional radiologists.

Hidden flexion injury of the cervical spine.

PubMed

Webb, J K; Broughton, R B; McSweeney, T; Park, W M

1976-08-01

This paper describes seven patients who developed late vertebral deformity after flexion injuries of the cervical spine. In four the clinical and radiological features were subtle and because the patients walked into an emergency department the severity of the injury was not initially appreciated. Certain specific clinical and radiological features of flexion injury are described and emphasis is placed on the importance of correct management. A radiological tetrad is described which should alert the surgeon to the possibility of damage to the posterior interspinous complex of the cervical spine and so lead to further radiological investigations. Despite the frequency of flexion injuries the alarming complications described in this paper are rare.

OPEN AIR DEMOLITION OF FACILITIES HIGHLY CONTAMINATED WITH PLUTONIUM

DOE Office of Scientific and Technical Information (OSTI.GOV)

LLOYD, E.R.

2007-05-31

The demolition of highly contaminated plutonium buildings usually is a long and expensive process that involves decontaminating the building to near free- release standards and then using conventional methods to remove the structure. It doesn't, however, have to be that way. Fluor has torn down buildings highly contaminated with plutonium without excessive decontamination. By removing the select source term and fixing the remaining contamination on the walls, ceilings, floors, and equipment surfaces; open-air demolition is not only feasible, but it can be done cheaper, better (safer), and faster. Open-air demolition techniques were used to demolish two highly contaminated buildings tomore » slab-on-grade. These facilities on the Department of Energy's Hanford Site were located in, or very near, compounds of operating nuclear facilities that housed hundreds of people working on a daily basis. To keep the facilities operating and the personnel safe, the projects had to be creative in demolishing the structures. Several key techniques were used to control contamination and keep it within the confines of the demolition area: spraying fixatives before demolition; applying fixative and misting with a fine spray of water as the buildings were being taken down; and demolishing the buildings in a controlled and methodical manner. In addition, detailed air-dispersion modeling was done to establish necessary building and meteorological conditions and to confirm the adequacy of the proposed methods. Both demolition projects were accomplished without any spread of contamination outside the modest buffer areas established for contamination control. Furthermore, personnel exposure to radiological and physical hazards was significantly reduced by using heavy equipment rather than ''hands on'' techniques.« less

A national survey exploring UK trainees' perceptions, core training experience, and decisions to pursue advanced training in breast radiology.

PubMed

Lowes, S; Bydder, M; Sinnatamby, R

2017-11-01

To investigate UK radiology trainees' perceptions of breast radiology and the factors that influenced their decision whether or not to choose breast radiology as an area of special interest. An online survey was compiled and distributed to all UK specialty trainees in clinical radiology via the Royal College of Radiologists Junior Radiologists' Forum (JRF) regional representatives. There were 275 respondents, representing 22% of all UK radiology trainees. Responses were received from all regions. A significant factor identified in influencing whether or not trainees decide to pursue advanced training in breast radiology is the timing and quality of their initial core training experience. Specific positive aspects of breast radiology that were repeatedly identified included the high level of patient contact and frequent use of interventional procedures. Recurring negative aspects of breast radiology included isolation from general radiology and finding the subject matter boring. Breast radiology faces a significant workforce shortfall that is predicted to worsen in the coming years. There has never been a greater need to recruit specialty trainees into this field, and action is urgently needed to help ensure the sustainability of breast services and drive further improvements to patient care. The findings from this survey should be regarded as a challenge to all breast radiologists to engage with trainees from an early stage in their training and to enthuse them with the many positive aspects of a career in breast radiology. Copyright © 2017 The Royal College of Radiologists. Published by Elsevier Ltd. All rights reserved.

Local, Regional and National Responses for Medical Management of a Radiological/Nuclear Incident

PubMed Central

Dainiak, Nicholas; Skudlarska, Beata; Albanese, Joseph

2013-01-01

Radiological and nuclear devices may be used by terrorists or may be the source of accidental exposure. A tiered approach has been recommended for response to a terrorist event wherein local, regional, state and federal assets become involved sequentially, as the magnitude in severity of the incident increases. State-wide hospital plans have been developed and published for Connecticut, New York and California. These plans address delineation of responsibilities of various categories of health professionals, protection of healthcare providers, identification and classification of individuals who might have been exposed to and/or contaminated by radiation and, in the case of Connecticut response plan, early management of victims. Regional response programs such as the New England Regional Health Compact (consisting of 6 member states) have been developed to manage consequences of radiation injury. The Department of Homeland Security is ultimately responsible for managing both health consequences and the crisis. Multiple US national response assets may be called upon for use in radiological incidents. These include agencies and programs that have been developed by the Department of Energy, the Environmental Protection Agency and the Department of Defense. Coordination of national, regional and state assets with local response efforts is necessary to provide a timely and efficient response. PMID:23447742

Local, regional and national responses for medical management of a radiological/nuclear incident.

PubMed

Dainiak, Nicholas; Skudlarska, Beata; Albanese, Joseph

2013-01-01

Radiological and nuclear devices may be used by terrorists or may be the source of accidental exposure. A tiered approach has been recommended for response to a terrorist event wherein local, regional, state and federal assets become involved sequentially, as the magnitude in severity of the incident increases. State-wide hospital plans have been developed and published for Connecticut, New York and California. These plans address delineation of responsibilities of various categories of health professionals, protection of healthcare providers, identification and classification of individuals who might have been exposed to and/or contaminated by radiation and, in the case of Connecticut response plan, early management of victims. Regional response programs such as the New England Regional Health Compact (consisting of 6 member states) have been developed to manage consequences of radiation injury. The Department of Homeland Security is ultimately responsible for managing both health consequences and the crisis. Multiple US national response assets may be called upon for use in radiological incidents. These include agencies and programs that have been developed by the Department of Energy, the Environmental Protection Agency and the Department of Defense. Coordination of national, regional and state assets with local response efforts is necessary to provide a timely and efficient response.

The recommendations of ICRP Publication 111 in the light of the ICRP dialogue initiative in Fukushima.

PubMed

Lochard, J

2016-12-01

Publication 111, published by the International Commission on Radiological Protection (ICRP) in 2009, provided the first recommendations for dealing with the long-term recovery phase after a nuclear accident. Its focus is on the protection of people living in long-term contaminated areas after a nuclear accident, drawing on the experience of the Belarus population, Cumbrian sheep farmers in the UK, and Sami reindeer herders in Norway affected by the fallout from Chernobyl. The ICRP dialogue initiative in Fukushima confirmed what had been identified after Chernobyl, namely the very strong concern for health, particularly that of children, loss of control over everyday life, apprehension about the future, disintegration of family life and of the social and economic fabric, and the threat to the autonomy and dignity of affected people. Through their testimonies and reflections, the participants of the 12 dialogue meetings shed light on this complex situation. The ICRP dialogue initiative also confirmed that the wellbeing of the affected people is at stake, and radiological protection must focus on rehabilitation of their living conditions. The challenge is to incorporate the important clarifications resulting from the ICRP dialogue initiative into the updated version of Publication 111 that is currently in development. This paper does not necessarily reflect the views of the International Commission on Radiological Protection.

MARSAME Radiological Release Report for Archaeological Artifacts Excavated from Area L

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ruedig, Elizabeth; Whicker, Jeffrey Jay; Gillis, Jessica Mcdonnel

In 1991 Los Alamos National Laboratory’s (LANL’s) cultural resources team excavated archaeological site LA 4618 located at Technical Area 54, within Material Disposal Area L (MDA L). MDA L received non-radioactive chemical waste from the early 1960s until 1985. Further development of the MDA required excavation of several cultural sites under National Historic Preservation Act requirements; artifacts from these sites have been subsequently stored at LANL. The LANL cultural resources group would now like to release these artifacts to the Museum of Indian Arts and Culture in Santa Fe for curation. The history of disposal at Area L suggests thatmore » the artifact pool is unlikely to be chemically contaminated and LANL staff washed each artifact at least once following excavation. Thus, it is unlikely that the artifacts present a chemical hazard. LANL’s Environmental Stewardship group (EPC-ES) has evaluated the radiological survey results for the Area L artifact pool and found that the items described in this report meet the criteria for unrestricted radiological release under Department of Energy (DOE) Order 458.1 Radiation Protection of the Public and the Environment and are candidates for release without restriction from LANL control. This conclusion is based on the known history of MDA L and on radiation survey data.« less

Accumulation of Radioactive Cesium Released from Fukushima Daiichi Nuclear Power Plant in Terrestrial Cyanobacteria Nostoc commune

PubMed Central

Sasaki, Hideaki; Shirato, Susumu; Tahara, Tomoya; Sato, Kenji; Takenaka, Hiroyuki

2013-01-01

The Fukushima Daiichi Nuclear Power Plant accident released large amounts of radioactive substances into the environment and contaminated the soil of Tohoku and Kanto districts in Japan. Removal of radioactive material from the environment is an urgent problem, and soil purification using plants is being considered. In this study, we investigated the ability of 12 seed plant species and a cyanobacterium to accumulate radioactive material. The plants did not accumulate radioactive material at high levels, but high accumulation was observed in the terrestrial cyanobacterium Nostoc commune. In Nihonmatsu City, Fukushima Prefecture, N. commune accumulated 415,000 Bq/kg dry weight 134Cs and 607,000 Bq kg−1 dry weight 137Cs. The concentration of cesium in N. commune tended to be high in areas where soil radioactivity was high. A cultivation experiment confirmed that N. commune absorbed radioactive cesium from polluted soil. These data demonstrated that radiological absorption using N. commune might be suitable for decontaminating polluted soil. PMID:24256969

Underground Test Area Calendar Year 2014 Annual Sampling Analysis Report Nevada National Security Site, Nevada, Revision 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Farnham, Irene

2016-12-01

This report presents the analytical data for the 2014 fiscal year (FY) and calendar year (CY) (October 1, 2013, through December 31, 2014), and an evaluation of the data to ensure that the Sampling Plan’s objectives are met. In addition to samples collected and analyzed for the Sampling Plan, some NNSS wells are monitored by NNSA/NFO to demonstrate compliance with State-issued water discharge permits; with protection of groundwater from ongoing radiological waste disposal activities (compliance wells); and to demonstrate that the onsite drinking water supply is below SDWA maximum contaminant levels (MCLs) (public water system [PWS] wells). While not allmore » sampled locations are required by the Sampling Plan, these samples are relevant to its objectives and are therefore presented herein for completeness purposes. Special investigations that took place in 2014 that are relevant to the Sampling Plan are also presented. This is the first annual report released to support Sampling Plan implementation.« less

A proteomics assay to detect eight CBRN-relevant toxins in food.

PubMed

Gilquin, Benoit; Jaquinod, Michel; Louwagie, Mathilde; Kieffer-Jaquinod, Sylvie; Kraut, Alexandra; Ferro, Myriam; Becher, François; Brun, Virginie

2017-01-01

A proteomics assay was set up to analyze food substrates for eight toxins of the CBRN (chemical, biological, radiological and nuclear) threat, namely ricin, Clostridium perfringens epsilon toxin (ETX), Staphylococcus aureus enterotoxins (SEA, SEB and SED), shigatoxins from Shigella dysenteriae and entero-hemorragic Escherichia coli strains (STX1 and STX2) and Campylobacter jejuni cytolethal distending toxin (CDT). The assay developed was based on an antibody-free sample preparation followed by bottom-up LC-MS/MS analysis operated in targeted mode. Highly specific detection and absolute quantification were obtained using isotopically labeled proteins (PSAQ standards) spiked into the food matrix. The sensitivity of the assay for the eight toxins was lower than the oral LD50 which would likely be used in a criminal contamination of food supply. This assay should be useful in monitoring biological threats. In the public-health domain, it opens the way for multiplex investigation of food-borne toxins using targeted LC-MS/MS. © 2016 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Pu isotopes in soils collected downwind from Lop Nor: regional fallout vs. global fallout.

PubMed

Bu, Wenting; Ni, Youyi; Guo, Qiuju; Zheng, Jian; Uchida, Shigeo

2015-07-17

For the first time, soil core samples from the Jiuquan region have been analyzed for Pu isotopes for radioactive source identification and radiological assessment. The Jiuquan region is in downwind from the Lop Nor Chinese nuclear test (CNT) site. The high Pu inventories (13 to 546 Bq/m(2)) in most of the sampling locations revealed that this region was heterogeneously contaminated by the regional fallout Pu from the CNTs. The contributions of the CNTs to the total Pu in soils were estimated to be more than 40% in most cases. The (240)Pu/(239)Pu atom ratios in the soils ranged from 0.059 to 0.186 with an inventory-weighted average of 0.158, slightly lower than that of global fallout. This atom ratio could be considered as a mixed fingerprint of Pu from the CNTs. In addition, Pu in soils of Jiuquan region had a faster downward migration rate compared with other investigated places in China.

Pu isotopes in soils collected downwind from Lop Nor: regional fallout vs. global fallout

PubMed Central

Bu, Wenting; Ni, Youyi; Guo, Qiuju; Zheng, Jian; Uchida, Shigeo

2015-01-01

For the first time, soil core samples from the Jiuquan region have been analyzed for Pu isotopes for radioactive source identification and radiological assessment. The Jiuquan region is in downwind from the Lop Nor Chinese nuclear test (CNT) site. The high Pu inventories (13 to 546 Bq/m2) in most of the sampling locations revealed that this region was heterogeneously contaminated by the regional fallout Pu from the CNTs. The contributions of the CNTs to the total Pu in soils were estimated to be more than 40% in most cases. The 240Pu/239Pu atom ratios in the soils ranged from 0.059 to 0.186 with an inventory-weighted average of 0.158, slightly lower than that of global fallout. This atom ratio could be considered as a mixed fingerprint of Pu from the CNTs. In addition, Pu in soils of Jiuquan region had a faster downward migration rate compared with other investigated places in China. PMID:26184740

Environmenal analysis of the Bayo Canyon (TA-10) Site, Los Alamos, New Mexico

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ferenbaugh, R.W.; Buhl, T.E.; Stoker, A.K.

1982-05-01

The radiological survey of the old TA-10 site in Bayo Canyon found low levels of surface contamination in the vicinity of the firing sites and subsurface contamination in the old waste disposal area. The three alternatives proposed for the site are: (1) to take no action; (2) to restrict usage of the area of subsurface contamination to activities that cause no subsurface disturbance (minimal action); and (3) to remove the subsurface conamination to levels below the working criteria. Dose calculations indicate that doses from surface contamination for recreational users of the canyon, permanent residents, and construction workers and doses formore » workers involved in excavation of contaminated soil under the clean up alternative are only small percentages of applicable guidelines. No environmental impacts are associated with either the no-action or minimal action alternatives. The impact associated with the cleanup alternative is small, especially considering that the area already has been affected by the original TA-10 decommissioning action, but nevertheless, the preferred alternative is the minimal action alternative, where 0.6 hectare of land is restricted to surface activities. This leaves the rest of the canyon available for development with up to 400 homes. The restricted area can be used for a park, tennis courts, etc., and the /sup 90/Sr activity will decay to levels permitting unrestricted usage in about 160 y.« less

Flood and Fire Monitoring and Forecasting Within the Chornobyl Exclusion Zone

NASA Astrophysics Data System (ADS)

Los, Victor

2001-03-01

Taking into consideration that radioactivity from the contaminating elements of the Chernobyl Exclusion Zone (CEZ) amounts to a huge number, one of the most urgent tasks, at present, is the resolution of problems related to secondary radioactive contamination caused by floods and fires. These factors may lead to critical consequences. For instance, if radioactive contaminants migrate into the water system, namely into the Dnipro River, a threat arises to more than 20 million inhabitants of Ukraine. Additionally, fires in the CEZ potentially could cause contaminants to be dispersed into the air and to migrate in the atmosphere for long distances. The elements of information support system for administrative decision-making to respond to the appearances and consequences of forest fires and floods in contaminated areas of the CEZ have been developed. The system proposes: using Earth Remote Sensing (R/S) data for timely detection of forest fires; integration by Geographic Information System (GIS) of mathematical models for radionuclide migration by air in order to forecast radiological consequences of forest fires; forecasting and assessing flood consequences by means of spatial analysis of GIS and R/S; and development of a system for dissemination of information. This project was performed within the framework of USAID Cooperative Agreement #121-A-00-98-00615-00, dedicated to the establishment of the Ukrainian Land and Resource Management Center.

Evaluation of Stress and a Stress-Reduction Program Among Radiologic Technologists.

PubMed

Reingold, Lynn

2015-01-01

To investigate stress levels and causes of stress among radiologic technologists and determine whether an intervention could reduce stress in a selected radiologic technologist population. Demographic characteristics and data on preintervention stress sources and levels were collected through Internet-based questionnaires. A 6-week, self-administered, mindfulness-based stress-reduction program was conducted as a pilot intervention with 42 radiologic technologists from the Veterans Administration Medical Center. Data also were collected postintervention. Identified sources of stress were compared with findings from previous studies. Some radiologic technologists experienced improvement in their perceptions of stress after the intervention. Sources of stress for radiologic technologists were similar to those shown in earlier research, including inconsistent management, poor management communication, conflicting demands, long work hours, excessive workloads, lack of work breaks, and time pressures. The mindfulness-based stress-reduction program is an example of an inexpensive method that could improve personal well-being, reduce work errors, improve relationships in the workplace, and increase job satisfaction. More research is needed to determine the best type of intervention for stress reduction in a larger radiologic technologist population.

Fast Running Urban Dispersion Model for Radiological Dispersal Device (RDD) Releases: Model Description and Validation

DOE Office of Scientific and Technical Information (OSTI.GOV)

Gowardhan, Akshay; Neuscamman, Stephanie; Donetti, John

Aeolus is an efficient three-dimensional computational fluid dynamics code based on finite volume method developed for predicting transport and dispersion of contaminants in a complex urban area. It solves the time dependent incompressible Navier-Stokes equation on a regular Cartesian staggered grid using a fractional step method. It also solves a scalar transport equation for temperature and using the Boussinesq approximation. The model also includes a Lagrangian dispersion model for predicting the transport and dispersion of atmospheric contaminants. The model can be run in an efficient Reynolds Average Navier-Stokes (RANS) mode with a run time of several minutes, or a moremore » detailed Large Eddy Simulation (LES) mode with run time of hours for a typical simulation. This report describes the model components, including details on the physics models used in the code, as well as several model validation efforts. Aeolus wind and dispersion predictions are compared to field data from the Joint Urban Field Trials 2003 conducted in Oklahoma City (Allwine et al 2004) including both continuous and instantaneous releases. Newly implemented Aeolus capabilities include a decay chain model and an explosive Radiological Dispersal Device (RDD) source term; these capabilities are described. Aeolus predictions using the buoyant explosive RDD source are validated against two experimental data sets: the Green Field explosive cloud rise experiments conducted in Israel (Sharon et al 2012) and the Full-Scale RDD Field Trials conducted in Canada (Green et al 2016).« less

Radiation in Yolo County

NASA Astrophysics Data System (ADS)

Dickie, H.; Colwell, K.

2013-12-01

In today's post-nuclear age, there are many man-made sources of radioactivity, in addition to the natural background we expect from cosmic and terrestrial origins. While all atoms possess unstable isotopes, there are few that are abundant enough, energetic enough, and have long enough half-lives to pose a signicant risk of ionizing radiation exposure. We hypothesize a decreasing relative radiation measurement (in detected counts per minute [CPM]) at nine locations that might pose occupational or environmental hazard: 1. A supermarket produce aisle (living tissue has high concentration of 40K) 2. A hospital (medical imaging uses X-rays and radioactive dyes) 3. The electronics section of a superstore (high voltage electronics have the potential to produce ionizing radiation) 4. An electrical transformer (similar reasons) 5. An antique store (some ceramics and glazes use radioisotopes that are now outlawed) 6. A gasoline pump (processing and terrestrial isotope contamination might leave a radioactive residue) 7. A fertilized eld (phosphate rock contains uranium and thorium, in addition to potassium) 8. A house (hopefully mild background, but potential radon contamination) 9. A school (should be radiologically neutral) We tested the hypothesis by measuring 100 minutes of counts on a self-assembled MightyOhmTM Geiger counter at each location. Our results show that contrary to the hypothesized ordering, the house was the most radiologically active. We present possible explanations for the observed radiation levels, as well as possible sources of measurement error, possible consequences of prolonged exposure to the measured levels, and suggestions for decreasing exposure and environmental impact.

Dirty Bombs: A Discouraging Second Look

NASA Astrophysics Data System (ADS)

Loeb, Cheryl A.

2004-05-01

Dirty bombs, terrorist devices to spread intensely radioactive material with the intent to kill, sicken, or inflict economic damage, have been overestimated by some in the government and underestimated by many physicists. It is unlikely that a radiological dispersion device (RDD) will contaminate an area to such a level that brief exposures are lethal or even incapacitating. However, careful examination of the consequences of the accident in Goiânia, Brazil shows that it is highly likely that people in the contaminated region will inhale or ingest dusty or liquid radioactive material in sufficient quantities to cause acute radiation sickness, and in some cases enough to kill. Some forms of radiological attack could kill tens or hundreds of people and sicken hundreds or thousands. This paper provides a general overview of the nature and use of RDDs and examines readily available sources of large quantities of radioactive material, material which requires significantly greater protection than it is afforded today. Under many circumstances an RDD containing only a few curies of cesium-137, strontium-90, cobalt-60 or other industrial isotopes could force the razing of more buildings and inflict greater economic losses than did the September 11, 2002 attacks on the World Trade Center and the Pentagon. The National Defense University study proposes new policies for the federal government which would decrease the chances of an attack and reduce the cost in lives and money to the United States should one, nevertheless, occur.

Controversy in urinary tract infection management in children: a review of new data and subsequent changes in guidelines.

PubMed

Kari, Jameela Abdulaziz; Tullus, Kjell

2013-12-01

Controversy and lack of consensus have been encountered in the management of pediatric urinary tract infection (UTI), including its diagnosis, radiological investigations and the use of antibiotic therapy. In this review, we discuss the need for radiological investigations and the extent of their use as well as the need for prophylactic antibiotics in children with UTI and vesicoureteral reflux. Only a small proportion of children with first UTI and no history of antenatal renal abnormalities have clinically important malformations. Renal ultrasound should be performed in febrile infants and young children with UTI; a micturating cystourethrogram should not be performed routinely after the first febrile UTI. Long-term antibiotics appear to reduce the risk of recurrent symptomatic UTI in susceptible children, although the clinical benefit is marginal. Current recommendations encourage performing radiological investigations only in children at risk and discourage routine prophylactic antibiotic use.

The social media revolution.

PubMed

Dubose, Cheryl

2011-01-01

The growing popularity and use of social media tools such as Facebook, YouTube, Twitter, blogging, and wikis have led to a social media revolution. Given this widespread influence, it is important for educators, administrators, and technologists to understand the risks of using social media in the classroom and workplace. To investigate popular social media sites and their effect on radiologic technology education and business practices. A comprehensive search of literature was performed to examine social media and its applications in education, health care, and business. Social media use is on the rise, affecting all aspects of mainstream society. Leaders in the radiologic sciences should be familiar with social media and cognizant of its risks. Future studies regarding social media use in the radiologic sciences are necessary to determine its effect on the radiologic science community. ©2011 by the American Society of Radiologic Technologists.

Changing radiology resident education to meet today's and tomorrow's needs.

PubMed

Halsted, Mark J; Perry, Laurie; Racadio, John M; Medina, L Santiago; LeMaster, Thomas

2004-09-01

Radiology education has evolved significantly in the past several decades, but there is considerable room for improvement. While some improvements depend on the availability of new technology, others are low tech, requiring merely that we be aware of and apply findings in the education literature. We teachers of radiology could benefit from recent studies investigating the processes underlying adult learning to improve the methods we use to train residents and fellows, and to improve the way we teach our colleagues and even ourselves. In this review, adult learning and the expert learner are briefly discussed, as are the important elements of effective learning tools. The strengths and weaknesses of radiology education as it is commonly practiced today are explored. Specific suggestions for improving education in radiology using both low tech and high tech methods are then discussed.

Radionuclide Retention in Concrete Wasteforms

DOE Office of Scientific and Technical Information (OSTI.GOV)

Wellman, Dawn M.; Jansik, Danielle P.; Golovich, Elizabeth C.

2012-09-24

Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation); the mechanism of contaminant release; the significance of contaminant release pathways; how wasteform performance is affected by the full range of environmental conditions within the disposal facility; the process of wasteform aging under conditions that are representative of processes occurring in response to changing environmental conditions within the disposal facility; the effect of wasteform aging on chemical, physical, and radiological properties; and the associated impact on contaminant release. This knowledge will enable accurate predictionmore » of radionuclide fate when the wasteforms come in contact with groundwater. Data collected throughout the course of this work will be used to quantify the efficacy of concrete wasteforms, similar to those used in the disposal of LLW and MLLW, for the immobilization of key radionuclides (i.e., uranium, technetium, and iodine). Data collected will also be used to quantify the physical and chemical properties of the concrete affecting radionuclide retention.« less

Fourth report on the Oak Ridge National Laboratory Biological Monitoring and Abatement Program for White Oak Creek Watershed and the Clinch River

DOE Office of Scientific and Technical Information (OSTI.GOV)

Loar, J.M.

1994-04-01

In response to a condition of the National Pollutant Discharge Elimination System (NPDES) permit issued to Oak Ridge National Laboratory (ORNL) on April 1, 1986, a Biological Monitoring and Abatement Program (BMAP) was developed for White Oak Creek (WOC) and selected tributaries. BMAP currently consists of six major tasks that address both radiological and nonradiological contaminants in the aquatic and terrestrial environs on-site and the aquatic environs off-site. These tasks are (1) toxicity monitoring, (2) bioaccumulation monitoring of nonradiological contaminants in aquatic biota, (3) biological indicator studies, (4) instream ecological monitoring, (5) assessment of contaminants in the terrestrial environment, andmore » (6) radioecology of WOC and White Oak Lake. The ecological characterization of the WOC watershed will provide baseline data that can be used to document the ecological effects of the water pollution control program and the remedial action program. The long-term nature of BMAP ensures that the effectiveness of remedial measures will be properly evaluated.« less

Final report of the decontamination and decommissioning of Building 6 at the Grand Junction Projects Office Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Widdop, M.R.

1996-07-01

The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the domestic uranium procurement program funded by the U.S. Atomic Energy Commission. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, is also the remedial actionmore » contractor. Radiological contamination was identified in Building 6, and the building was demolished in 1992. The soil area within the footprint of the building has been remediated in accordance with the identified standards and the area can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.« less

Final report of the decontamination and decommissioning of Building 39 at the Grand Junction Projects Office Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Widdop, M.R.

1996-07-01

The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, is also the remedial action contractor. The soilmore » beneath Building 39 was radiologically contaminated and the building was demolished in 1992. The soil area within the footprint of the building has been remediated in accordance with the identified standards and the area can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.« less

US Department of Energy Grand Junction Projects Office Remedial Action Project, final report of the decontamination and decommissioning of Building 36 at the Grand Junction Projects Office Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Widdop, M.R.

1996-08-01

The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, also is the remedial action contractor. Building 36more » was found to be radiologically contaminated and was demolished in 1996. The soil beneath the building was remediated in accordance with identified standards and can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.« less

Final report of the decontamination and decommissioning of Building 1 at the Grand Junction Projects Office Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Widdop, M.R.

1996-08-01

The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, also is the remedial action contractor. Building 1more » was found to be radiologically contaminated and was demolished in 1996. The soil beneath and adjacent to the building was remediated in accordance with identified standards and can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.« less

Project 57 Air Monitoring Report: January 1 through December 31, 2016

DOE Office of Scientific and Technical Information (OSTI.GOV)

Mizell, Steve A.; Nikolich, George; Shadel, Craig

On April 24, 1957, the Atomic Energy Commission (AEC, now the Department of Energy [DOE]) conducted the Project 57 safety experiment in western Emigrant Valley northeast of the Nevada National Security Site (NNSS, formerly the Nevada Test Site) on lands withdrawn by the Department of Defense (DOD) for the Nevada Test and Training Range (NTTR). The test was undertaken to develop (1) a means of estimating plutonium distribution resulting from a non-nuclear detonation; (2) biomedical evaluation techniques for use in plutonium-laden environments; (3) methods of surface decontamination; and (4) instruments and field procedures for prompt estimation of alpha contamination (Shreve,more » 1958). Although the test did not result in the fission of nuclear materials, it did disseminate plutonium across the land surface. Following the experiment, the AEC fenced the contaminated area and returned control of the surrounding land to the DOD. Various radiological surveys were performed in the area and in 2007, the DOE expanded the demarked Contamination Area (CA) by posting signs 200 to 400 ft (60 to 120 m) outside of the original fence.« less

Addendum to the Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 452: Historical Underground Storage Tank Release Sites, Nevada Test Site, Nevada, Revision 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Grant Evenson

This document constitutes an addendum to the Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 452: Historical Underground Storage Tank Release Sites, Nevada Test Site, Nevada, April 1998 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada Test Site, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: • This page that refers the reader to the SIR document for additionalmore » information • The cover, title, and signature pages of the SIR document • The NDEP approval letter • The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the URs for CASs: • 25-25-09, Spill H940825C (from UST 25-3101-1) • 25-25-14, Spill H940314E (from UST 25-3102-3) • 25-25-15, Spill H941020E (from UST 25-3152-1) These URs were established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and were based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since these URs were established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, these URs were re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the URs) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove these URs because contamination is not present at these sites above the risk-based FALs. Requirements for inspecting and maintaining these URs will be canceled, and the postings and signage at each site will be removed. Fencing and posting may be present at these sites that are unrelated to the FFACO URs such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at these sites.« less

Addendum 2 to the Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 454: Historical Underground Storage Tank Release Sites, Nevada Test Site, Nevada, Revision 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Grant Evenson

This document constitutes an addendum to the Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 454: Historical Underground Storage Tank Release Sites, Nevada Test Site, Nevada, April 1998 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada Test Site, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: • This page that refers the reader to the SIR document for additionalmore » information • The cover, title, and signature pages of the SIR document • The NDEP approval letter • The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the URs for CASs: • 12-25-08, Spill H950524F (from UST 12-B-1) • 12-25-10, Spill H950919A (from UST 12-COMM-1) These URs were established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and were based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since these URs were established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, these URs were re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the URs) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove these URs because contamination is not present at these sites above the risk-based FALs. Requirements for inspecting and maintaining these URs will be canceled, and the postings and signage at each site will be removed. Fencing and posting may be present at these sites that are unrelated to the FFACO URs such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at these sites.« less

COMPARE/Radiology, an interactive Web-based radiology teaching program evaluation of user response.

PubMed

Wagner, Matthias; Heckemann, Rolf A; Nömayr, Anton; Greess, Holger; Bautz, Werner A; Grunewald, Markus

2005-06-01

The aim of this study is to assess user benefits of COMPARE/Radiology, a highly interactive World Wide Web-based training program for radiology, as perceived by its users. COMPARE/Radiology (http://www.idr.med.uni-erlangen.de/compare.htm), an interactive training program based on 244 teaching cases, was created by the authors and made publicly available on the Internet. An anonymous survey was conducted among users to investigate the composition of the program's user base and assess the acceptance of the training program. In parallel, Web access data were collected and analyzed using descriptive statistics. The group of responding users (n = 1370) consisted of 201 preclinical medical students (14.7%), 314 clinical medical students (22.9%), 359 residents in radiology (26.2%), and 205 users of other professions (14.9%). A majority of respondents (1230; 89%) rated the interactivity of COMPARE/Radiology as good or excellent. Many respondents use COMPARE/Radiology for self-study (971; 70%) and for teaching others (600; 43%). Web access statistics show an increase in number of site visits from 1248 in December 2002 to 4651 in April 2004. Users appreciate the benefits of COMPARE/Radiology. The interactive instructional design was rated positively by responding users. The popularity of the site is growing, evidenced by the number of network accesses during the observation period.

Cutting costs: the impact of price lists on the cost development at the emergency department.

PubMed

Schilling, Ulf Martin

2010-12-01

It was shown that physicians working at the Swedish emergency department (ED) are unaware of the costs for investigations performed. This study evaluated the possible impact of price lists on the overall laboratory and radiology costs at the ED of a Swedish university hospital. Price lists including the most common laboratory analyses and radiological investigations at the ED were created. The lists were distributed to all internal medicine physicians by e-mail and exposed above their working stations continually. No lists were provided for the orthopaedic control group. The average costs for laboratory and radiological investigations during the months of June and July 2007 and 2008 were calculated. Neither clinical nor admission procedures were changed. The physicians were blinded towards the study. Statistical analysis was performed using the Student's t-test. A total of 1442 orthopaedic and 1585 medical patients were attended to in 2007. In 2008, 1467 orthopaedic and 1637 medical patients required emergency service. The average costs per patient were 980.27 SKR (98€)/999.41 SKR (100€, +1.95%) for orthopaedic and 1081.36 SKR (108€)/877.3 SKR (88€, -18.8%) for medical patients. Laboratory costs decreased by 9% in orthopaedic and 21.4% in medical patients. Radiology costs changed +5.4% in orthopaedic and -20.59% in medical patients. The distribution and promotion of price lists as a tool at the ED to heighten cost awareness resulted in a major decrease in the investigation costs. A significant decrease in radiological costs could be observed. It can be concluded that price lists are an effective tool to cut costs in public healthcare.

BIOTIC INTEGRITY OF STREAMS IN THE SAVANNAH RIVER SITE INTEGRATOR OPERABLE UNITS, 1996 TO 2003

DOE Office of Scientific and Technical Information (OSTI.GOV)

Paller, M; Susan Dyer, S

2004-11-08

The Savannah River Site (SRS) has been divided into six Integrator Operable Units (IOUs) that correspond to the watersheds of the five major streams on the SRS (Upper Three Runs, Fourmile Branch, Pen Branch, Steel Creek, and Lower Three Runs) and the portions of the Savannah River and Savannah River Swamp associated with the SRS. The streams are the primary integrators within each IOU because they potentially receive, through surface or subsurface drainage, soluble contaminants from all waste sites within their watersheds. If these contaminants reach biologically significant levels, they would be expected to effect the numbers, types, and healthmore » of stream organisms. In this study, biological sampling was conducted within each IOU as a measure of the cumulative ecological effects of the waste sites within the IOUs. The use of information from biological sampling to assess environmental quality is often termed bioassessment. The IOU bioassessment program included 38 sites in SRS streams and nine sites in the Savannah River. Sampling was conducted in 1996 to 1998, 2000, and 2003. Four bioassessment methods were used to evaluate ecological conditions in the IOU streams: the Index of Biotic Integrity, the Fish Health Assessment Index, measurement of fish tissue contaminant levels, and two benthic macroinvertebrate indices. The Index of Biotic Integrity (IBI) is an EPA supported method based on comparison of ecologically important and sensitive fish assemblage variables between potentially disturbed and reference (i.e., undisturbed) sites. It is designed to assess the ability of a stream to support a self-sustaining biological community and ecological processes typical of undisturbed, natural conditions. Since many types of contaminants can bioaccumulate, fish tissue contaminant data were used to determine the types of chemicals fish were exposed to and their relative magnitudes among IOUs. The Fish Health Assessment Index (HAI) is an EPA supported method for assessing the health and condition of individual fish based on dissection and internal examination. It helped to determine whether contaminant concentrations were high enough to adversely affect the health of individual fish. The benthic macroinvertebrate multimetric index (HDMI), used in 1997 to 2000, is a method for assessing stream health based on macroinvertebrate data collected with Hester-Dendy artificial substrates. In 2003 it was replaced with the Multiple Habitat Sampling protocol, a SCDHEC method for collecting and analyzing benthic macroinvertebrate data from natural substrate. These two macroinvertebrate based methods were used in conjunction with the fish based IBI to provide a more comprehensive assessment of ecological conditions. Lastly, habitat data were collected from each stream to assist in determining whether ecological integrity was compromised by physical factors (e.g., erosion) or chemical factors (e.g., discharge of toxic materials). Fish from many SRS streams exhibited evidence of contamination as a result of current or former SRS operations. The most prevalent radiological contaminants were cesium-137 (highest in fish from Lower Three Runs followed by Steel Creek and Fourmile Branch), tritium (highest in fish from Fourmile Branch followed by Pen Branch, and the Savannah River swamp), and strontium (highest in fish from Fourmile Branch followed by Pen Branch). Radiological contaminants were also found in fish collected from the Savannah River near the mouths of contaminated SRS streams; however, contaminant levels were substantially lower than in fish from the streams themselves. Mercury levels were moderately elevated in fish from some streams, particularly Lower Three Runs, and in fish from the Savannah River. Despite the occurrence of contaminants, most SRS streams exhibited comparatively high biotic integrity (based on IBI, HDMI, and MHSP scores) and minimal levels of pathology among individual fish (e.g., presence of tumors or extreme thinness), indicating that contaminant levels were generally insufficient to cause significant ecological degradation.« less

Involving stakeholders in radiological protection decision making: recovery history and lessons from the people of Fukushima.

PubMed

Lazo, T

2016-12-01

Between September 2011 and August 2015, the International Commission on Radiological Protection (ICRP) organised a series of 12 stakeholder dialogue workshops with residents of Fukushima Prefecture. Discussions focused on recovery, addressing topics such as protection of children, management of contaminated food, monitoring, and self-help measures. The OECD Nuclear Energy Agency (NEA) supported, and the Committee on Radiation Protection and Public Health (CRPPH) Secretariat attended, all 12 meetings to listen directly to the concerns of affected individuals and draw lessons for CRPPH. To summarise the dialogue results, ICRP organised a final meeting in Date, Japan with the support of NEA and other organisations. The lessons from and utility of the dialogue meetings were praised by dialogue participants and sponsors, and ICRP agreed that some form of dialogue would continue, although with ICRP participation and support rather than leadership. This paper summarises the internationally relevant lessons learned by CRPPH from this important process.

Toxicity assessment of the water used for human consumption from the Cameron/Tuba City abandoned uranium mining area prior/after the combined electrochemical treatment/advanced oxidation.

PubMed

Gajski, Goran; Oreščanin, Višnja; Gerić, Marko; Kollar, Robert; Lovrenčić Mikelić, Ivanka; Garaj-Vrhovac, Vera

2015-01-01

The purpose of this work was detailed physicochemical, radiological, and toxicological characterization of the composite sample of water intended for human consumption in the Cameron/Tuba City abandoned uranium mining area before and after a combined electrochemical/advanced oxidation treatment. Toxicological characterization was conducted on human lymphocytes using a battery of bioassays. On the bases of the tested parameters, it could be concluded that water used for drinking from the tested water sources must be strictly forbidden for human and/or animal consumption since it is extremely cytogenotoxic, with high oxidative stress potential. A combined electrochemical treatment and posttreatment with ozone and UV light decreased the level of all physicochemical and radiological parameters below the regulated values. Consequently, the purified sample was neither cytotoxic nor genotoxic, indicating that the presented method could be used for the improvement of water quality from the sites highly contaminated with the mixture of heavy metals and radionuclides.

Radiologic characterization of the Mexican Hat, Utah, uranium mill tailings remedial action site: Appendix D, Addenda D1--D7

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ludlam, J.R.

1985-01-01

This radiologic characterization of the inactive uranium millsite at Mexican Hat, Utah, was conducted by Bendix Field Engineering Corporation foe the US Department of Energy (DOE), Grand Junction Project Office, in response to and in accord with a Statement of Work prepared by the DOE Uranium Mill tailings Remedial Action Project (UMTRAP) Technical Assistance Contractor, Jacobs Engineering Group, Inc. the objective of this project was to determine the horizontal and vertical extent of contamination that exceeds the US Environmental Protection Agency (EPA) standards at the Mexican Hat site. The data presented in this report are required for characterization of themore » areas adjacent to the Mexican Hat tailings piles and for the subsequent design of cleanup activities. Some on-pile sampling was required to determine the depth of the 15-pCi/g Ra-226 interface in an area where wind and water erosion has taken place.« less

Results of the radiological survey at the former ALCOA New Kensington Works, Pine and Ninth Streets, New Kensington, Pennsylvania (ANK002)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Foley, R.D.; Brown, K.S.

1992-10-01

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the former ALCOA New Kensington Works, Pine and Ninth Streets, New Kensington, Pennsylvania. The survey was performed on November 12, 1991. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, principally, as a result of work done for the Manhattan Engineer District in 1944. The survey included a gamma scan of three bays inside Building 18; measurement of direct alpha and beta-gamma levels in the same area; and collection of amore » dust sample for radionuclide analysis from the center of each bay. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines for uranium. The radionuclide distributions were not significantly different from typical background levels in the Pittsburgh, Pennsylvania area.« less

Field application of the Numobag as a portable disposable isolation unit and for treating chemical, radiological or biologically induced wounds.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Miller, Keith A.; Felton, Robert; Vaughan, Courtenay Thomas

2005-04-01

Numotech Inc. has developed the Numobag{trademark}, a disposable, lightweight, wound healing device which produces Topical Hyperbaric Oxygen Therapy (THOT). The Numobag{trademark} is cost effective and has been clinically validated to heal large skin lesions rapidly and has proven to arrest wound advancement from several insidious forms of biological attack including dermal anthrax, small pox, necrotizing fasciitis etc. The Numobag{trademark} can treat mass casualties wounded by chemical/radiological burns or damaging biological exposures. The Numobag{trademark} can be a frontline tool as an isolation unit, reducing cross-contamination and infection of medical personnel. The heightened oxygen content kills organisms on the skin and inmore » the wound, avoids expensive hospital trash disposal procedures, and helps the flesh heal. The Numobag{trademark} requires high purity oxygen. Numotech Inc. is teaming with Sandia National Laboratories and Spektr Conversion in Russia to develop a cost effective, portable, low power oxygen generator.« less

An overview on GSF activities at the Semipalatinsk Test Site, Kazakhstan.

PubMed

Semioshkina, Natalia; Voigt, Gabrielle

2006-02-01

The Semipalatinsk Test Site (STS) in Kazakhstan was one of the major sites used by the former USSR for testing nuclear weapons for more than 40 years. Since the early 1990s, agricultural activities have been re-established there by neighbouring collective and private farms. Therefore, it has become important to evaluate the radiological situation and the current and future risk to people living on and using the contaminated area. During the last eight years, GSF has participated in many international projects performed on the STS to evaluate the radiological situation. A large number of soil, vegetation and food samples has been collected and analysed. Internal dose is one of the main components of the total dose when deriving risk factors for a population living within the test site. Internal doses, based on food monitoring and whole body measurements, were calculated for adults and were in the range of 13-500 microSv/y due to radiocaesium and radiostrontium.

An In Situ Radiological Survey of Three Canyons at the Los Alamos National Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

R.J. Maurer

1999-06-01

An in situ radiological survey of Mortandad, Ten Site, and DP Canyons at the Los Alamos National Laboratory was conducted during August 19-30, 1996. The purpose of this survey was to measure the quantities of radionuclides that remain in the canyons from past laboratory operations. A total of 65 in situ measurements were conducted using high-resolution gamma radiation detectors at 1 meter above the ground. The measurements were obtained in the streambeds of the canyons beginning near the water-release points at the laboratories and extending to the ends of the canyons. Three man-made gamma-emitting radionuclides were detected in the canyons:more » americium-241 ({sup 241}Am), cesium-137 ({sup 137}Cs), and cobalt-60 ({sup 60}Co). Estimated contamination levels ranged from 13.3-290.4 picocuries per gram (pCi/g)for {sup 241}Am, 4.4-327.8 pCi/g for {sup 137}Cs, and 0.4-2.6 pCi/g for {sup 60}Co.« less

An Updated Comprehensive Risk Analysis for Radioisotopes Identified of High Risk to National Security in the Event of a Radiological Dispersion Device Scenario

NASA Astrophysics Data System (ADS)

Robinson, Alexandra R.

An updated global survey of radioisotope production and distribution was completed and subjected to a revised "down-selection methodology" to determine those radioisotopes that should be classified as potential national security risks based on availability and key physical characteristics that could be exploited in a hypothetical radiological dispersion device. The potential at-risk radioisotopes then were used in a modeling software suite known as Turbo FRMAC, developed by Sandia National Laboratories, to characterize plausible contamination maps known as Protective Action Guideline Zone Maps. This software also was used to calculate the whole body dose equivalent for exposed individuals based on various dispersion parameters and scenarios. Derived Response Levels then were determined for each radioisotope using: 1) target doses to members of the public provided by the U.S. EPA, and 2) occupational dose limits provided by the U.S. Nuclear Regulatory Commission. The limiting Derived Response Level for each radioisotope also was determined.

DOE Office of Scientific and Technical Information (OSTI.GOV)

NSTec Environmental Restoration

Homeland Security Presidential Directive HSPD-5 requires all federal departments and agencies to adopt a National Incident Management System (NIMS)/Incident Command System (ICS) and use it in their individual domestic incident management and emergency prevention, preparedness, response, recovery, and mitigation programs and activities, as well as in support of those actions taken to assist state and local entities. This system provides a consistent nationwide template to enable federal, state, local, and tribal governments, private-sector, and nongovernmental organizations to work together effectively and efficiently to prepare for, prevent, respond to, and recover from domestic incidents, regardless of cause, size, or complexity, includingmore » acts of catastrophic terrorism. This document identifies the operational concepts of the Federal Radiological Monitoring and Assessment Center's (FRMAC) implementation of the NIMS/ICS response structure under the National Response Plan (NRP). The construct identified here defines the basic response template to be tailored to the incident-specific response requirements. FRMAC's mission to facilitate interagency environmental data management, monitoring, sampling, analysis, and assessment and link this information to the planning and decision staff clearly places the FRMAC in the Planning Section. FRMAC is not a mitigating resource for radiological contamination but is present to conduct radiological impact assessment for public dose avoidance. Field monitoring is a fact-finding mission to support this effort directly. Decisions based on the assessed data will drive public protection and operational requirements. This organizational structure under NIMS is focused by the mission responsibilities and interface requirements following the premise to provide emergency responders with a flexible yet standardized structure for incident response activities. The coordination responsibilities outlined in the NRP are based on the NIMS/ICS construct and Unified Command (UC) for management of a domestic incident. The NRP Nuclear/Radiological Incident Annex (NUC) further provides requirements and protocols for coordinating federal government capabilities to respond to nuclear/radiological Incidents of National Significance (INS) and other radiological incidents. When a FRMAC is established, it operates under the parameters of NIMS as defined in the NRP. FRMAC and its operations have been modified to reflect NIMS/ICS concepts and principles and to facilitate working in a Unified Command structure. FRMAC is established at or near the scene of the incident to coordinate radiological monitoring and assessment and is established in coordination with the U.S. Department of Homeland Security (DHS); the coordinating agency; other federal agencies; and state, local, and tribal authorities. However, regardless of the coordinating agency designation, U.S. Department of Energy (DOE) coordinates radiological monitoring and assessment activities for the initial phases of the offsite federal incident response through the Radiological Assistance Program (RAP) and FRMAC assets. Monitoring and assessment data are managed by FRMAC in an accountable, secure, and retrievable format. Monitoring data interpretations, including exposure rate contours, dose projections, and any requested radiological assessments are to be provided to the DHS; to the coordinating agency; and to state, local, and tribal government agencies.« less

Radioactive waste management complex low-level waste radiological composite analysis

DOE Office of Scientific and Technical Information (OSTI.GOV)

McCarthy, J.M.; Becker, B.H.; Magnuson, S.O.

1998-05-01

The composite analysis estimates the projected cumulative impacts to future members of the public from the disposal of low-level radioactive waste (LLW) at the Idaho National Engineering and Environmental Laboratory (INEEL) Radioactive Waste Management Complex (RWMC) and all other sources of radioactive contamination at the INEEL that could interact with the LLW disposal facility to affect the radiological dose. Based upon the composite analysis evaluation, waste buried in the Subsurface Disposal Area (SDA) at the RWMC is the only source at the INEEL that will significantly interact with the LLW facility. The source term used in the composite analysis consistsmore » of all historical SDA subsurface disposals of radionuclides as well as the authorized LLW subsurface disposal inventory and projected LLW subsurface disposal inventory. Exposure scenarios evaluated in the composite analysis include all the all-pathways and groundwater protection scenarios. The projected dose of 58 mrem/yr exceeds the composite analysis guidance dose constraint of 30 mrem/yr; therefore, an options analysis was conducted to determine the feasibility of reducing the projected annual dose. Three options for creating such a reduction were considered: (1) lowering infiltration of precipitation through the waste by providing a better cover, (2) maintaining control over the RWMC and portions of the INEEL indefinitely, and (3) extending the period of institutional control beyond the 100 years assumed in the composite analysis. Of the three options investigated, maintaining control over the RWMC and a small part of the present INEEL appears to be feasible and cost effective.« less

Savannah River Site Footprint Reduction Results under the American Recovery and Reinvestment Act - 13302

DOE Office of Scientific and Technical Information (OSTI.GOV)

Flora, Mary; Adams, Angelia; Pope, Robert

2013-07-01

The Savannah River Site (SRS) is an 802 square-kilometer United States Department of Energy (US DOE) nuclear facility located along the Savannah River near Aiken, South Carolina, managed and operated by Savannah River Nuclear Solutions. Construction of SRS began in the early 1950's to enhance the nation's nuclear weapons capability. Nuclear weapons material production began in the early 1950's, eventually utilizing five production reactors constructed to support the national defense mission. Past operations have resulted in releases of hazardous constituents and substances to soil and groundwater, resulting in 515 waste sites with contamination exceeding regulatory thresholds. More than 1,000 facilitiesmore » were constructed onsite with approximately 300 of them considered radiological, nuclear or industrial in nature. In 2003, SRS entered into a Memorandum of Agreement with its regulators to accelerate the cleanup using an Area Completion strategy. The strategy was designed to focus cleanup efforts on the 14 large industrial areas of the site to realize efficiencies of scale in the characterization, assessment, and remediation activities. This strategy focuses on addressing the contaminated surface units and the vadose zone and addressing groundwater plumes subsequently. This approach streamlines characterization and remediation efforts as well as the required regulatory documentation, while enhancing the ability to make large-scale cleanup decisions. In February 2009, Congress approved the American Reinvestment and Recovery Act (ARRA) to create jobs and promote economic recovery. At SRS, ARRA funding was established in part to accelerate the completion of environmental remediation and facility deactivation and decommissioning (D and D). By late 2012, SRS achieved 85 percent footprint reduction utilizing ARRA funding by accelerating and coupling waste unit remediation with D and D of remnant facilities. Facility D and D activities were sequenced and permitted with waste unit remediation activities to streamline regulatory approval and execution. Achieving footprint reduction fulfills the Government's responsibility to address legacy contamination; allows earlier completion of legally enforceable compliance agreement milestones; and enables future potential reuse of DOE resources, including land and infrastructure for other missions. Over the last 3.5 years significant achievements were met that contributed to footprint reduction, including the closure of 41 waste units (including 20 miles of radiologically contaminated stream) and decommissioning of 30 facilities (including the precedent setting in situ closure of two former production reactors, the first in the DOE Complex). Other notable achievements included the removal of over 39,750 cubic meters of debris and 68,810 cubic meters of contaminated soils, including 9175 cubic meters of lead-contaminated soil from a former site small arms testing range and treatment of 1,262 cubic meters of tritium-laden soils and concrete using a thermal treatment system. (authors)« less

Diethylene-triamine-penta-acetate administration protocol for radiological emergency medicine in nuclear fuel reprocessing plants.

PubMed

Jin, Yutaka

2008-01-01

Inhalation therapy of diethylene-triamine-penta-acetate (DTPA) should be initiated immediately to workers who have significant incorporation of plutonium, americium or curium in the nuclear fuel reprocessing plant. A newly designed electric mesh nebulizer is a small battery-operated passive vibrating mesh device, in which vibrations in an ultrasonic horn are used to force drug solution through a mesh of micron-sized holes. This nebulizer enables DTPA administration at an early stage in the event of a radiation emergency from contamination from the above radioactive metals.

Quick-sealing design for radiological containment

DOEpatents

Rampolia, Donald S.; Speer, Elmer

1990-01-01

A quick-sealing assembly and method for forming an adhesive seal on opposite sides of a mechanical seal for a flexible containment bag of the type used for working with radioactively contaminated objects. The assembly includes an elongated mechanical fastener having opposing engaging members affixed at a predetermined distance from each of the elongated edges, with an adhesive layer formed between the mechanical fastener and the elongated edge such that upon engagement of the mechanical fastener and adhesive layers to opposing containment fabric, a neat triple hermetic seal is formed.

Quick-sealing design for radiological containment

DOEpatents

Rampolla, Donald S.; Speer, Elmer

1991-01-01

A quick-sealing assembly and method for forming an adhesive seal on opposite sides of a mechanical seal for a flexible containment bag of the type used for working with radioactively contaminated objects. The assembly includes an elongated mechanical fastener having opposing engaging members affixed at a predetermined distance from each of the elongated edges, with an adhesive layer formed between the mechanical fastener and the elongated edge such that upon engagement of the mechanical fastener and adhesive layers to opposing containment fabric, a neat triple hermetic seal is formed.

Classic versus millennial medical lab anatomy.

PubMed

Benninger, Brion; Matsler, Nik; Delamarter, Taylor

2014-10-01

This study investigated the integration, implementation, and use of cadaver dissection, hospital radiology modalities, surgical tools, and AV technology during a 12-week contemporary anatomy course suggesting a millennial laboratory. The teaching of anatomy has undergone the greatest fluctuation of any of the basic sciences during the past 100 years in order to make room for the meteoric rise in molecular sciences. Classically, anatomy consisted of a 2-year methodical, horizontal, anatomy course; anatomy has now morphed into a 12-week accelerated course in a vertical curriculum, at most institutions. Surface and radiological anatomy is the language for all clinicians regardless of specialty. The objective of this study was to investigate whether integration of full-body dissection anatomy and modern hospital technology, during the anatomy laboratory, could be accomplished in a 12-week anatomy course. Literature search was conducted on anatomy text, journals, and websites regarding contemporary hospital technology integrating multiple image mediums of 37 embalmed cadavers, surgical suite tools and technology, and audio/visual technology. Surgical and radiology professionals were contracted to teach during the anatomy laboratory. Literature search revealed no contemporary studies integrating full-body dissection with hospital technology and behavior. About 37 cadavers were successfully imaged with roentograms, CT, and MRI scans. Students were in favor of the dynamic laboratory consisting of multiple activity sessions occurring simultaneously. Objectively, examination scores proved to be a positive outcome and, subjectively, feedback from students was overwhelmingly positive. Despite the surging molecular based sciences consuming much of the curricula, full-body dissection anatomy is irreplaceable regarding both surface and architectural, radiological anatomy. Radiology should not be a small adjunct to understand full-body dissection, but rather, full-body dissection aids the understanding of radiology mediums. The millennial anatomy dissection laboratory should consist of, at least, 50% radiology integration during full-body dissection. This pilot study is an example of the most comprehensive integration of full-body dissection, radiology, and hospital technology. © 2014 Wiley Periodicals, Inc.

A Head and Neck Simulator for Radiology and Radiotherapy

NASA Astrophysics Data System (ADS)

Thompson, Larissa; Campos, Tarcísio P. R.

2013-06-01

Phantoms are suitable tools to simulate body tissues and organs in radiology and radiation therapy. This study presents the development of a physical head and neck phantom and its radiological response for simulating brain pathology. The following features on the phantom are addressed and compared to human data: mass density, chemical composition, anatomical shape, computerized tomography images and Hounsfield Units. Mass attenuation and kerma coefficients of the synthetic phantom and normal tissues, as well as their deviations, were also investigated. Radiological experiments were performed, including brain tumors and subarachnoid hemorrhage simulations. Computerized tomography images of such pathologies in phantom and human were obtained. The anthropometric dimensions of the phantom present anatomical conformation similar to a human head and neck. Elemental weight percentages of the equivalent tissues match the human ones. Hounsfield Unit values of the main developed structures are presented, approaching human data. Kerma and mass attenuation coefficients spectra from human and phantom are presented, demonstrating smaller deviations in the radiological X-ray spectral domain. In conclusion, the phantom presented suitable normal and pathological radiological responses relative to those observed in humans. It may improve radiological protocols and education in medical imaging.

Surface Cleaning Techniques: Ultra-Trace ICP-MS Sample Preparation and Assay of HDPE

DOE Office of Scientific and Technical Information (OSTI.GOV)

Overman, Nicole R.; Hoppe, Eric W.; Addleman, Raymond S.

2013-06-01

The world’s most sensitive radiation detection and assay systems depend upon ultra-low background (ULB) materials to reduce unwanted radiological backgrounds. Herein, we evaluate methods to clean HDPE, a material of interest to ULB systems and the means to provide rapid assay of surface and bulk contamination. ULB level material and ultra-trace level detection of actinide elements is difficult to attain, due to the introduction of contamination from sample preparation equipment such as pipette tips, sample vials, forceps, etc. and airborne particulate. To date, literature available on the cleaning of such polymeric materials and equipment for ULB applications and ultra-trace analysesmore » is limited. For these reasons, a study has been performed to identify an effective way to remove surface contamination from polymers in an effort to provide improved instrumental detection limits. Inductively Coupled Plasma Mass Spectroscopy (ICP-MS) was utilized to assess the effectiveness of a variety of leachate solutions for removal of inorganic uranium and thorium surface contamination from polymers, specifically high density polyethylene (HDPE). HDPE leaching procedures were tested to optimize contaminant removal of thorium and uranium. Calibration curves for thorium and uranium ranged from 15 ppq (fg/mL) to 1 ppt (pg/mL). Detection limits were calculated at 6 ppq for uranium and 7 ppq for thorium. Results showed the most effective leaching reagent to be clean 6 M nitric acid for 72 hour exposures. Contamination levels for uranium and thorium found in the leachate solutions were significant for ultralow level radiation detection applications.« less

An assessment of potential health impacts on Utrok Atoll from exposure to cesium-137 (137Cs) and plutonium

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hamilton, T

2007-07-24

Residual fallout contamination from the nuclear test program in the Marshall Islands is a concern to Marshall Islanders because of the potential health risks associated with exposure to residual fallout contamination in the environment. Scientists from Lawrence Livermore National Laboratory (LLNL) have been monitoring the amount of fallout radiation delivered to Utrok Atoll residents over the past 4 years. This briefing document gives an outline of our findings from the whole body counting and plutonium bioassay monitoring programs. Additional information can be found on the Marshall Islands web site (http://eed.lnl.gov/mi/). Cesium-137 is an important radioactive isotope produced in nuclear detonationsmore » and can be taken up from coral soils into locally grown food crop products that form an important part of the Marshallese diet. The Marshall Islands whole body counting program has clearly demonstrated that the majority of Utrok Atoll residents acquire a very small but measurable quantity of cesium-137 in their bodies (Hamilton et al., 2006; Hamilton et. al., 2007a; 2007b;). During 2006, a typical resident of Utrok Atoll received about 3 mrem of radiation from internally deposited cesium-137 (Hamilton et al., 2007a). The population-average dose contribution from cesium-137 is around 2% of the total radiation dose that people normally experience from naturally occurring radiation sources in the Marshall Islands and is thousands of times lower than the level where radiation exposure is known to produce measurable health effects. The existing dose estimates from the whole body counting and plutonium bioassay programs are also well below radiological protection standards for protection of the public as prescribed by U.S. regulators and international agencies including the Marshall Islands Nuclear Claim Tribunal (NCT). Similarly, the level of internally deposited plutonium found in Utrok Atoll residents is well within the range normally expected for people living in the Northern Hemisphere. In addition, the preliminary results of the bioassay program on Utrok Atoll (Hamilton et al., 2007b) provide clear evidence that residents of Utrok Atoll have never acquired a significant uptake of plutonium either through an acute exposure event or from long-term chronic exposure to plutonium in the environment. This information and data should provide a level of assurance to the Utrok Atoll population group and its leadership that the dose contribution from exposure to residual radioactive fallout contamination on Utrok Atoll is very low, and is not likely to have any discernible impact on human health. We also estimate that the dose contribution based on current radiological exposure conditions will not produce any additional cancer fatalities (or any other measurable health condition) above that normally expected to arise in a population group of similar size. The potential risks from any genetic illnesses caused by exposure to residual fallout contamination in the environment will be even lower still. In conclusion, the data and information developed from the radiological protection monitoring program on Utrok appear to support a consensus that it is safe to live on Utrok Atoll. The health risks from exposure to residual fallout contamination on the atoll are minimal when compared with other lifetime risks that people normally experience, and are very small when compared to the threshold where radiation health effects could be either medically diagnosed in an individual or epidemiologically discerned in a group of people.« less

Phased Demolition of an Occupied Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Brede, Lawrence M.; Lauterbach, Merl J.; Witt, Brandon W.

2008-01-15

The U.S. government constructed the K-1401 facility in the late 1940's as a support building for various projects supporting the uranium gaseous diffusion process. In 2004 the U.S. Department of Energy authorized Bechtel Jacobs Company, LLC (BJC) to decontaminate and demolish the facility. The K-1401 facility was used for a variety of industrial purposes supporting the gaseous diffusion process. Many different substances were used to support these processes over the years and as a result different parts of the facility were contaminated with fluorine, chlorine trifluoride, uranium and technetium radiological contamination, asbestos, and mercury. The total facility area is 46,015more » m{sup 2} (495,000 sf) including a 6,800 m{sup 2} basement (73,200 sf). In addition to the contamination areas in the facility, a large portion was leased to businesses for re-industrialization when the D and D activities began. The work scope associated with the facility included purging and steam cleaning the former fluorine and chlorine trifluoride systems, decontaminating loose radiologically contaminated and mercury spill areas, dismantling former radiological lines contaminated with uranium oxide compounds and technetium, abating all asbestos containing material, and demolishing the facility. These various situations contributed to the challenge of successfully conducting D and D tasks on the facility. In order to efficiently utilize the work force, demolition equipment, and waste hauling trucks the normal approach of decontaminating the facility of the hazardous materials, and then conducting demolition in series required a project schedule of five years, which is not cost effective. The entire project was planned with continuous demolition as the goal end state. As a result, the first activities, Phase 1, required to prepare sections for demolition, including steam cleaning fluorine and chlorine trifluoride process lines in basement and facility asbestos abatement, were conducted while the tenants who were leasing floor space in the facility moved out. Upon completion of this phase the facility was turned over to the demolition project and the most hazardous materials were removed from the facility. Phase 2 activities included removing the process gas lines from sections C/D/E while decontaminating and preparing sections A and B for demolition. Demolition preparation activities include removing transit siding and universal waste from the area. Phase 3 began with demolition activities in sections A and B1 while continuing process gas line removal from sections C/D/E, as well as conducting demolition preparation activities to these sections. Area B was split into two sections, allowing demolition activities to occur in section B1 while personnel could still access the upper floor in sections C, D, and E. Once demolition began in section B2, personnel entry was only authorized in the basement. This timeline initiated phase 4, and the project completed cleaning the process components from the basement while section B2 demolition began. The final phase, phase 5, began once the basement was cleared. Final demolition activities began on sections C, D, E, and the basement. This material will ship for disposal and is scheduled for completion during FY07. Because the project was able to successfully phase demolition activities, the total facility demolition schedule was reduced by half to 2-1/2 years. The project was able to move portions of the demolition schedule from working in series to working in parallel, allowing the job to deliver facility demolition debris to ship for disposal 'just in time' as the facility was demolished.« less

Radiological protection from radioactive waste management in existing exposure situations resulting from a nuclear accident.

PubMed

Sugiyama, Daisuke; Hattori, Takatoshi

2013-01-01

In environmental remediation after nuclear accidents, radioactive wastes have to be appropriately managed in existing exposure situations with contamination resulting from the emission of radionuclides by such accidents. In this paper, a framework of radiation protection from radioactive waste management in existing exposure situations for application to the practical and reasonable waste management in contaminated areas, referring to related ICRP recommendations was proposed. In the proposed concept, intermediate reference levels for waste management are adopted gradually according to the progress of the reduction in the existing ambient dose in the environment on the basis of the principles of justification and optimisation by taking into account the practicability of the management of radioactive waste and environmental remediation. It is essential to include the participation of relevant stakeholders living in existing exposure situations in the selection of reference levels for the existing ambient dose and waste management.

Radiological protection from radioactive waste management in existing exposure situations resulting from a nuclear accident

PubMed Central

Sugiyama, Daisuke; Hattori, Takatoshi

2013-01-01

In environmental remediation after nuclear accidents, radioactive wastes have to be appropriately managed in existing exposure situations with contamination resulting from the emission of radionuclides by such accidents. In this paper, a framework of radiation protection from radioactive waste management in existing exposure situations for application to the practical and reasonable waste management in contaminated areas, referring to related ICRP recommendations was proposed. In the proposed concept, intermediate reference levels for waste management are adopted gradually according to the progress of the reduction in the existing ambient dose in the environment on the basis of the principles of justification and optimisation by taking into account the practicability of the management of radioactive waste and environmental remediation. It is essential to include the participation of relevant stakeholders living in existing exposure situations in the selection of reference levels for the existing ambient dose and waste management. PMID:22719047

Corrective Action Decision Document/Corrective Action Plan for Corrective Action Unit 98: Frenchman Flat, Nevada National Security Site, Nevada, Revision 1

DOE Office of Scientific and Technical Information (OSTI.GOV)

Irene Farnham and Sam Marutzky

2011-07-01

This CADD/CAP follows the Corrective Action Investigation (CAI) stage, which results in development of a set of contaminant boundary forecasts produced from groundwater flow and contaminant transport modeling of the Frenchman Flat CAU. The Frenchman Flat CAU is located in the southeastern portion of the NNSS and comprises 10 underground nuclear tests. The tests were conducted between 1965 and 1971 and resulted in the release of radionuclides in the subsurface in the vicinity of the test cavities. Two important aspects of the corrective action process are presented within this CADD/CAP. The CADD portion describes the results of the Frenchman Flatmore » CAU data-collection and modeling activities completed during the CAI stage. The corrective action objectives and the actions recommended to meet the objectives are also described. The CAP portion describes the corrective action implementation plan. The CAP begins with the presentation of CAU regulatory boundary objectives and initial use restriction boundaries that are identified and negotiated by NNSA/NSO and the Nevada Division of Environmental Protection (NDEP). The CAP also presents the model evaluation process designed to build confidence that the flow and contaminant transport modeling results can be used for the regulatory decisions required for CAU closure. The first two stages of the strategy have been completed for the Frenchman Flat CAU. A value of information analysis and a CAIP were developed during the CAIP stage. During the CAI stage, a CAIP addendum was developed, and the activities proposed in the CAIP and addendum were completed. These activities included hydrogeologic investigation of the underground testing areas, aquifer testing, isotopic and geochemistry-based investigations, and integrated geophysical investigations. After these investigations, a groundwater flow and contaminant transport model was developed to forecast contaminant boundaries that enclose areas potentially exceeding the Safe Drinking Water Act radiological standards at any time within 1,000 years. An external peer review of the groundwater flow and contaminant transport model was completed, and the model was accepted by NDEP to allow advancement to the CADD/CAP stage. The CADD/CAP stage focuses on model evaluation to ensure that existing models provide adequate guidance for the regulatory decisions regarding monitoring and institutional controls. Data-collection activities are identified and implemented to address key uncertainties in the flow and contaminant transport models. During the CR stage, final use restriction boundaries and CAU regulatory boundaries are negotiated and established; a long-term closure monitoring program is developed and implemented; and the approaches and policies for institutional controls are initiated. The model evaluation process described in this plan consists of an iterative series of five steps designed to build confidence in the site conceptual model and model forecasts. These steps are designed to identify data-collection activities (Step 1), document the data-collection activities in the 0CADD/CAP (Step 2), and perform the activities (Step 3). The new data are then assessed; the model is refined, if necessary; the modeling results are evaluated; and a model evaluation report is prepared (Step 4). The assessments are made by the modeling team and presented to the pre-emptive review committee. The decision is made by the modeling team with the assistance of the pre-emptive review committee and concurrence of NNSA/NSO to continue data and model assessment/refinement, recommend additional data collection, or recommend advancing to the CR stage. A recommendation to advance to the CR stage is based on whether the model is considered to be sufficiently reliable for designing a monitoring system and developing effective institutional controls. The decision to advance to the CR stage or to return to step 1 of the process is then made by NDEP (Step 5).« less

Recent Improvement of Measurement Instrumentation to Supervise Nuclear Operations and to Contribute Input Data to 3D Simulation Code - 13289

DOE Office of Scientific and Technical Information (OSTI.GOV)

Mahe, Charly; Chabal, Caroline

2013-07-01

The CEA has developed many compact characterization tools to follow sensitive operations in a nuclear environment. Usually, these devices are made to carry out radiological inventories, to prepare nuclear interventions or to supervise some special operations. These in situ measurement techniques mainly take place at different stages of clean-up operations and decommissioning projects, but they are also in use to supervise sensitive operations when the nuclear plant is still operating. In addition to this, such tools are often associated with robots to access very highly radioactive areas, and thus can be used in accident situations. Last but not least, themore » radiological data collected can be entered in 3D calculation codes used to simulate the doses absorbed by workers in real time during operations in a nuclear environment. Faced with these ever-greater needs, nuclear measurement instrumentation always has to involve on-going improvement processes. Firstly, this paper will describe the latest developments and results obtained in both gamma and alpha imaging techniques. The gamma camera has been used by the CEA since the 1990's and several changes have made this device more sensitive, more compact and more competitive for nuclear plant operations. It is used to quickly identify hot spots, locating irradiating sources from 50 keV to 1500 keV. Several examples from a wide field of applications will be presented, together with the very latest developments. The alpha camera is a new camera used to see invisible alpha contamination on several kinds of surfaces. The latest results obtained allow real time supervision of a glove box cleaning operation (for {sup 241}Am contamination). The detection principle as well as the main trials and results obtained will be presented. Secondly, this paper will focus on in situ gamma spectrometry methods developed by the CEA with compact gamma spectrometry probes (CdZnTe, LaBr{sub 3}, NaI, etc.). The radiological data collected is used to quantify the activity of hot spots and can also then be entered in 3D models of nuclear plants to simulate intervention scenarios. Recent developments and results will be presented regarding this. Finally, thanks to a large amount of feedback, the interest of using complementary measurements will be discussed. In fact, the recent use of 3D simulation codes requires very accurate knowledge of nuclear plant radiological data. The use of coupled devices such as imaging devices, (gamma and alpha cameras), gamma spectrometry, dose rate mapping, collimated / un-collimated measurements and many other physical values gives an approach to the radiological knowledge of a process or plant with the lowest possible uncertainty. In line with this, the paper will conclude with the future developments and trials that could be assessed in that field of application. (authors)« less

Long-term fate of depleted uranium at Aberdeen and Yuma Proving Grounds: Human health and ecological risk assessments

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ebinger, M.H.; Beckman, R.J.; Myers, O.B.

1996-09-01

The purpose of this study was to evaluate the immediate and long-term consequences of depleted uranium (DU) in the environment at Aberdeen Proving Ground (APG) and Yuma Proving Ground (YPG) for the Test and Evaluation Command (TECOM) of the US Army. Specifically, we examined the potential for adverse radiological and toxicological effects to humans and ecosystems caused by exposure to DU at both installations. We developed contaminant transport models of aquatic and terrestrial ecosystems at APG and terrestrial ecosystems at YPG to assess potential adverse effects from DU exposure. Sensitivity and uncertainty analyses of the initial models showed the portionsmore » of the models that most influenced predicted DU concentrations, and the results of the sensitivity analyses were fundamental tools in designing field sampling campaigns at both installations. Results of uranium (U) isotope analyses of field samples provided data to evaluate the source of U in the environment and the toxicological and radiological doses to different ecosystem components and to humans. Probabilistic doses were estimated from the field data, and DU was identified in several components of the food chain at APG and YPG. Dose estimates from APG data indicated that U or DU uptake was insufficient to cause adverse toxicological or radiological effects. Dose estimates from YPG data indicated that U or DU uptake is insufficient to cause radiological effects in ecosystem components or in humans, but toxicological effects in small mammals (e.g., kangaroo rats and pocket mice) may occur from U or DU ingestion. The results of this study were used to modify environmental radiation monitoring plans at APG and YPG to ensure collection of adequate data for ongoing ecological and human health risk assessments.« less

Radiation protection challenges in the management of radioactive waste from high-energy accelerators.

PubMed

Ulrici, Luisa; Algoet, Yvon; Bruno, Luca; Magistris, Matteo

2015-04-01

The European Laboratory for Particle Physics (CERN) has operated high-energy accelerators for fundamental physics research for nearly 60 y. The side-product of this activity is the radioactive waste, which is mainly generated as a result of preventive and corrective maintenance, upgrading activities and the dismantling of experiments or accelerator facilities. Prior to treatment and disposal, it is common practice to temporarily store radioactive waste on CERN's premises and it is a legal requirement that these storage facilities are safe and secure. Waste treatment typically includes sorting, segregation, volume and size reduction and packaging, which will depend on the type of component, its chemical composition, residual activity and possible surface contamination. At CERN, these activities are performed in a dedicated waste treatment centre under the supervision of the Radiation Protection Group. This paper gives an overview of the radiation protection challenges in the conception of a temporary storage and treatment centre for radioactive waste in an accelerator facility, based on the experience gained at CERN. The CERN approach consists of the classification of waste items into 'families' with similar radiological and physical-chemical properties. This classification allows the use of specific, family-dependent techniques for radiological characterisation and treatment, which are simultaneously efficient and compliant with best practices in radiation protection. The storage was planned on the basis of radiological and other possible hazards such as toxicity, pollution and fire load. Examples are given of technical choices for the treatment and radiological characterisation of selected waste families, which could be of interest to other accelerator facilities. © The Author 2014. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Shades of Grey: An Exploration of the Student Learning Experience in Diagnostic Imaging Education

ERIC Educational Resources Information Center

Linaker, Kathleen Linda

2012-01-01

Diagnostic radiology education is a specialty within healthcare education and encompasses education at both the undergraduate and resident level. There is little research regarding what constitutes effective radiology education. The broad purpose of this study was to investigate through the student perspective how chiropractic students learned…

Generalized "Satisfaction of Search": Adverse Influences on Dual-Target Search Accuracy

ERIC Educational Resources Information Center

Fleck, Mathias S.; Samei, Ehsan; Mitroff, Stephen R.

2010-01-01

The successful detection of a target in a radiological search can reduce the detectability of a second target, a phenomenon termed "satisfaction of search" (SOS). Given the potential consequences, here we investigate the generality of SOS with the goal of simultaneously informing radiology, cognitive psychology, and nonmedical searches such as…

1988 Hanford riverbank springs characterization report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Dirkes, R.L.

1990-12-01

This reports presents the results of a special study undertaken to characterize the riverbank springs (i.e., ground-water seepage) entering the Columbia River along the Hanford Site. Radiological and nonradiological analyses were performed. River water samples were also analyzed from upstream and downstream of the Site as well as from the immediate vicinity of the springs. In addition, irrigation return water and spring water entering the river along the shoreline opposite Hanford were analyzed. Hanford-origin contaminants were detected in spring water entering the Columbia River along the Hanford Site. The type and concentrations of contaminants in the spring water were similarmore » to those known to exist in the ground water near the river. The location and extent of the contaminated discharges compared favorably with recent ground-water reports and predictions. Spring discharge volumes remain very small relative to the flow of the Columbia. Downstream river sampling demonstrates the impact of ground-water discharges to be minimal, and negligible in most cases. Radionuclide concentrations were below US Department of Energy Derived Concentration Guides (DCGs) with the exception {sup 90}Sr near the 100-N Area. Tritium, while below the DCG, was detected at concentrations above the US Environmental Protection Agency drinking water standards in several springs. All other radionuclide concentrations were below drinking water standards. Nonradiological contaminants were generally undetectable in the spring water. River water contaminant concentrations, outside of the immediate discharge zones, were below drinking water standards in all cases. 19 refs., 5 figs., 12 tabs.« less

Microbiology for Radiologists: How to Minimize Infection Transmission in the Radiology Department.

PubMed

Mirza, Sobia K; Tragon, Tyson R; Fukui, Melanie B; Hartman, Matthew S; Hartman, Amy L

2015-01-01

The implementation of standardized infection control and prevention practices is increasingly relevant as modern radiology practice evolves into its more clinical role. Current Centers for Disease Control and Prevention, National Institutes of Health, and World Health Organization guidelines for the proper use of personal protective equipment, decontamination of reusable medical equipment, and appropriate management of bloodborne pathogen exposures will be reviewed. Standard precautions apply to all patients at all times and are the mainstay of infection control. Proper hand hygiene includes washing hands with soap and water when exposed to certain infectious particles, such as Clostridium difficile spores, which are not inactivated by alcohol-based hand rubs. The appropriate use of personal protective equipment in accordance with recommendations from the Centers for Disease Control and Prevention includes wearing a surgical mask during lumbar puncture. Because radiologists may perform lumbar punctures for patients with prion disease, it is important to appreciate that incineration is the most effective method of inactivating prion proteins. However, there is currently no consensus recommendation on the decontamination of prion-contaminated reusable items associated with lumbar puncture, and institutional policies should be consulted for directed management. In the event of a needlestick injury, radiology staff must be able to quickly provide appropriate initial management and seek medical attention, including laboratory testing for bloodborne pathogens. ©RSNA, 2015.

Combination of radiological and gray level co-occurrence matrix textural features used to distinguish solitary pulmonary nodules by computed tomography.

PubMed

Wu, Haifeng; Sun, Tao; Wang, Jingjing; Li, Xia; Wang, Wei; Huo, Da; Lv, Pingxin; He, Wen; Wang, Keyang; Guo, Xiuhua

2013-08-01

The objective of this study was to investigate the method of the combination of radiological and textural features for the differentiation of malignant from benign solitary pulmonary nodules by computed tomography. Features including 13 gray level co-occurrence matrix textural features and 12 radiological features were extracted from 2,117 CT slices, which came from 202 (116 malignant and 86 benign) patients. Lasso-type regularization to a nonlinear regression model was applied to select predictive features and a BP artificial neural network was used to build the diagnostic model. Eight radiological and two textural features were obtained after the Lasso-type regularization procedure. Twelve radiological features alone could reach an area under the ROC curve (AUC) of 0.84 in differentiating between malignant and benign lesions. The 10 selected characters improved the AUC to 0.91. The evaluation results showed that the method of selecting radiological and textural features appears to yield more effective in the distinction of malignant from benign solitary pulmonary nodules by computed tomography.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Detilleux, Michel; Centner, Baudouin

The paper describes different methodologies and tools developed in-house by Tractebel Engineering to facilitate the engineering works to be carried out especially in the frame of decommissioning projects. Three examples of tools with their corresponding results are presented: - The LLWAA-DECOM code, a software developed for the radiological characterization of contaminated systems and equipment. The code constitutes a specific module of more general software that was originally developed to characterize radioactive waste streams in order to be able to declare the radiological inventory of critical nuclides, in particular difficult-to-measure radionuclides, to the Authorities. In the case of LLWAA-DECOM, deposited activitiesmore » inside contaminated equipment (piping, tanks, heat exchangers...) and scaling factors between nuclides, at any given time of the decommissioning time schedule, are calculated on the basis of physical characteristics of the systems and of operational parameters of the nuclear power plant. This methodology was applied to assess decommissioning costs of Belgian NPPs, to characterize the primary system of Trino NPP in Italy, to characterize the equipment of miscellaneous circuits of Ignalina NPP and of Kozloduy unit 1 and, to calculate remaining dose rates around equipment in the frame of the preparation of decommissioning activities; - The VISIMODELLER tool, a user friendly CAD interface developed to ease the introduction of lay-out areas in a software named VISIPLAN. VISIPLAN is a 3D dose rate assessment tool for ALARA work planning, developed by the Belgian Nuclear Research Centre SCK.CEN. Both softwares were used for projects such as the steam generators replacements in Belgian NPPs or the preparation of the decommissioning of units 1 and 2 of Kozloduy NPP; - The DBS software, a software developed to manage the different kinds of activities that are part of the general time schedule of a decommissioning project. For each activity, when relevant, algorithms allow to estimate, on the basis of local inputs, radiological exposures of the operators (collective and individual doses), production of primary, secondary and tertiary waste and their characterization, production of conditioned waste, release of effluents,... and enable the calculation and the presentation (histograms) of the global results for all activities together. An example of application in the frame of the Ignalina decommissioning project is given. (authors)« less

The Northern Marshall Islands Radiological Survey: data and dose assessments.

PubMed

Robison, W L; Noshkin, V E; Conrado, C L; Eagle, R J; Brunk, J L; Jokela, T A; Mount, M E; Phillips, W A; Stoker, A C; Stuart, M L; Wong, K M

1997-07-01

Fallout from atmospheric nuclear tests, especially from those conducted at the Pacific Proving Grounds between 1946 and 1958, contaminated areas of the Northern Marshall Islands. A radiological survey at some Northern Marshall Islands was conducted from September through November 1978 to evaluate the extent of residual radioactive contamination. The atolls included in the Northern Marshall Islands Radiological Survey (NMIRS) were Likiep, Ailuk, Utirik, Wotho, Ujelang, Taka, Rongelap, Rongerik, Bikar, Ailinginae, and Mejit and Jemo Islands. The original test sites, Bikini and Enewetak Atolls, were also visited on the survey. An aerial survey was conducted to determine the external gamma exposure rate. Terrestrial (soil, food crops, animals, and native vegetation), cistern and well water samples, and marine (sediment, seawater, fish and clams) samples were collected to evaluate radionuclide concentrations in the atoll environment. Samples were processed and analyzed for 137Cs, 90Sr, 239+240Pu and 241Am. The dose from the ingestion pathway was calculated using the radionuclide concentration data and a diet model for local food, marine, and water consumption. The ingestion pathway contributes 70% to 90% of the estimated dose. Approximately 95% of the dose is from 137Cs. 90Sr is the second most significant radionuclide via ingestion. External gamma exposure from 137Cs accounts for about 10% to 30% of the dose. 239+240Pu and 241Am are the major contributors to dose via the inhalation pathway; however, inhalation accounts for only about 1% of the total estimated dose, based on surface soil levels and resuspension studies. All doses are computed for concentrations decay corrected to 1996. The maximum annual effective dose from manmade radionuclides at these atolls ranges from .02 mSv y(-1) to 2.1 mSv y(-1). The background dose in the Marshall Islands is estimated to be 2.4 mSv y(-1). The combined dose from both background and bomb related radionuclides ranges from slightly over 2.4 mSv y(-1) to 4.5 mSv y(-1). The 50-y integral dose ranges from 0.5 to 65 mSv.

A garage sale bargain: A leaking 2.2 GBq {sup 226}Ra source, Phase 1 - the incident

DOE Office of Scientific and Technical Information (OSTI.GOV)

Freeman, B.; Andrews, M.; Hogan, A.

1996-06-01

In March 1995, a private citizen living in Bristol, Tennessee, went to a local garage sale and purchased a box containing old medical equipment and paraphernalia for $10.00. The man put the box in the trunk of his car where it remained for several weeks. He then took the box into his home where he examined all of the items, including a small wooden box with a metal sleeve. After significant effort, he managed to remove the inner box which bore the word {open_quotes}radium.{close_quotes} Unsure of what this meant, he called his son-in-law who understood that radium was a radioactivemore » material and called the Tennessee Division of Radiological Health (TDRH). The TDRH investigation quickly located and isolated the source and determined that the contamination was spread throughout the man`s home and yard. Exposure rate readings as high as 160 mR h{sup -1} were found along with removable contamination as high as 3,000,000 dpm/100 cm{sup 2}. Over the next several days, the TDRH organized a voluntary effort for the medical evaluation of the man and his wife, the removal of the source, and the decontamination of the home, yard, car, etc. The two following papers will describe these aspects of this incident. On 26 May 1995, the remediation was completed, ending this unusual, but not unique, radiation incident.« less

Seasonal variations of natural radionuclides, minor and trace elements in lake sediments and water in a lignite mining area of North-Western Greece.

PubMed

Noli, Fotini; Tsamos, Panagiotis

2018-05-01

The radiological and chemical pollution of a cluster of four lakes in a lignite mining area of North-Western Greece was investigated using a variety of analytical techniques. Alpha spectrometry was applied to measure the activity concentrations of the uranium radioisotopes (U-234, U-235, and U-238) in waters. The mass activities of U-238, Th-232, and K-40 in sediments were measured by high-resolution gamma spectrometry. Furthermore, the determination of the minor and trace elements was carried out by instrumental neutron activation analysis (INAA) in both water and sediments samples, respectively. Pollution levels were also evaluated by calculating enrichment factors (EFs), contamination factors (CFs) and pollution load index (PLI). The data were discussed taking into account several parameters such as the distance from the pollution source, temperature, and location and showed that the environmental impact in this region could not be considered as negligible. The deviation of the isotopic ratio of U-234/U-238 from the equilibrium value indicated waters with intensive dissolution of uranium. The activity values in both waters and sediments found to be low in cool periods and increased in warm periods. Moreover, the concentrations of the elements U, Zn, and Fe were raised in water samples indicating possible pollution as well as the CFs and PLI denoted accumulation in the sediments and moderate to severe contamination for Zn and Cr in some cases.

Uncited Research Articles in Popular United States General Radiology Journals.

PubMed

Rosenkrantz, Andrew B; Chung, Ryan; Duszak, Richard

2018-05-03

This study aimed to characterize articles in popular general radiology journals that go uncited for a decade after publication. Using the Web of Science database, we identified annual citation counts for 13,459 articles published in Radiology, American Journal of Roentgenology, and Academic Radiology between 1997 and 2006. From this article cohort, we then identified all original research articles that accrued zero citations within a decade of publication. A concurrent equal-sized cohort of most cited articles was created. Numerous characteristics of the uncited and most cited articles were identified and compared. Only 47 uncited articles went uncited for a decade after publication. When compared to the 47 most cited articles over that same window, the uncited articles were significantly (P < .05) less likely to have a clinical focus, include a nonradiologist author and authors from multiple institutions and multiple nations, report research funding support and statistically significant findings, and include punctuation marks in their titles. Compared to the most cited articles, uncited articles also had significantly (P < .05) fewer authors, abstract words, manuscript words, references, tables, figure parts, and pages, as well as smaller subject sample sizes. Of articles published in popular general radiology journals, only a very small number of original research investigations remained uncited a decade after publication. Given that citations reflect the impact of radiology research, this observation suggests that journals are appropriately selecting meaningful work. Investigators seeking to avoid futile publication might consider their research initiatives in light of these characteristics. Copyright © 2018 The Association of University Radiologists. Published by Elsevier Inc. All rights reserved.

[Study of 12 epidemical cases of legionnaire's disease occurred in Meurthe-et-Moselle (France) between July and August 2004].

PubMed

Duhoux, F; Thomas, L; Bevilacqua, S; Lion, C; Hartemann, P; Piquet, E; Rabaud, C; May, T

2005-01-01

To describe epidemiological, clinical, biological, radiological data and therapeutic features of legionnaire's disease during an outbreak occurring in Meurthe-et-Moselle between July-August 2004. 12 cases were recorded including 11 men, 6 smokers, 4 alcoholo-nicotinic, 3 diabetics, 3 with hemopathy, 1 with corticotherapy; in one case no risks factors were found; mean age was 68.5 years [minimum=48; maximum=96]. Nine cases had sudden symptoms. Nine cases had a fever up to 40 degrees C, 9 with dyspnoea, 7 with cough, 7 with a relative bradycardia, 3 with diarrhoea, 3 felt faint, 3 with confusion. Radiology: unilateral unilobe localisation in 10 cases. Biological data: cytolysis in 8 cases, CRP >300 mg/l in 8. The diagnosis confirmed with urinary antigen of Legionella pneumophila serogroup 1 (UrAgLp1) in 12 cases. In 2 cases, UrAgLp1 appeared negative between 3rd and 10th day after the beginning of a treatment although UrAgLp1 was positive before the treatment. In all cases, the first serology realised during first days following occurrence the first symptoms remained negative. Two serology of control in four were positive. One search of L. pneumophila serogroup 1 in sputum was positive in 7. Bitherapy was used in 7 cases with preferential association: fluoroquinolone+rifampicin. Two patients died. Origin of the contamination remains unknown. Culture of Legionella is essential, in epidemic context, to compare clinical and environmental Legionella and to locate the origin of contamination.

Corrective Action Investigation Plan for Corrective Action Unit 568: Area 3 Plutonium Dispersion Sites Nevada National Security Site, Nevada, Revision 0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Matthews, Patrick

2014-01-01

CAU 568 is a grouping of sites where there has been a suspected release of contamination associated with nuclear testing. This document describes the planned investigation of CAU 568, which comprises the following corrective action sites (CASs): • 03-23-17, S-3I Contamination Area • 03-23-19, T-3U Contamination Area • 03-23-20, Otero Contamination Area • 03-23-22, Platypus Contamination Area • 03-23-23, San Juan Contamination Area • 03-23-26, Shrew/Wolverine Contamination Area These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained bymore » conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the investigation report.« less

New paleoradiological investigations of ancient human remains from North West Lombardy archaeological excavations.

PubMed

Licata, Marta; Borgo, Melania; Armocida, Giuseppe; Nicosia, Luca; Ferioli, Elena

2016-03-01

Since its birth in 1895, radiology has been used to study ancient mummies. The purpose of this article is to present paleoradiological investigations conducted on several medieval human remains in Varese province. Anthropological (generic identification) and paleopathological analyses were carried out with the support of diagnostic imaging (X-ray and CT scans). Human remains were discovered during excavations of medieval archaeological sites in northwest Lombardy. Classical physical anthropological methods were used for the macroscopic identification of the human remains. X-ray and CT scans were performed on the same scanner (16-layer Hitachi Eclos 16 X-ray equipment). Results Radiological analysis permitted investigating (1) the sex, (2) age of death, (3) type of trauma, (4) therapeutic interventions and (5) osteomas in ancient human remains. In particular, X-ray and CT examinations showed dimorphic facial traits on the mummified skull, and the same radiological approaches allowed determining the age at death from a mummified lower limb. CT analyses allow investigating different types of traumatic lesions in skulls and postcranial skeleton portions and reconstructing the gait and functional outcomes of a fractured femur. Moreover, one case of possible Gardner’s syndrome (GS) was postulated from observing multiple osteomas in an ancient skull. Among the medical tests available to the clinician, radiology is the most appropriate first-line procedure for a diagnostic approach to ancient human remains because it can be performed without causing any significant damage to the specimen.

Radiological Instrumentation Assessment for King County Wastewater Treatment Division

DOE Office of Scientific and Technical Information (OSTI.GOV)

Strom, Daniel J.; McConn, Ronald J.; Brodzinski, Ronald L.

2005-05-19

The King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into its combined sanitary and storm sewer system. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include "dirty bombs" that are not nuclear detonations but are explosives designed to spread radioactive material. Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. Volume 2 of PNNL-15163 assesses the radiological instrumentation needs for detection ofmore » radiological or nuclear terrorism, in support of decisions to treat contaminated wastewater or to bypass the West Point Treatment Plant (WPTP), and in support of radiation protection of the workforce, the public, and the infrastructure of the WPTP. Fixed radiation detection instrumentation should be deployed in a defense-in-depth system that provides 1) early warning of significant radioactive material on the way to the WPTP, including identification of the radionuclide(s) and estimates of the soluble concentrations, with a floating detector located in the wet well at the Interbay Pump Station and telemetered via the internet to all authorized locations; 2) monitoring at strategic locations within the plant, including 2a) the pipe beyond the hydraulic ram in the bar screen room; 2b) above the collection funnels in the fine grit facility; 2c) in the sampling tank in the raw sewage pump room; and 2d) downstream of the concentration facilities that produce 6% blended and concentrated biosolids. Engineering challenges exist for these applications. It is necessary to deploy both ultra-sensitive detectors to provide early warning and identification and detectors capable of functioning in high-dose rate environments that are likely under some scenarios, capable of functioning from 10 microrems per hour (background) up to 1000 rems per hour. Software supporting fixed spectroscopic detectors is needed to provide prompt, reliable, and simple interpretations of spectroscopic outputs that are of use to operators and decision-makers. Software to provide scientists and homeland security personnel with sufficient technical detail for identification, quantification, waste management decisions, and for the inevitable forensic and attribution needs must be developed. Computational modeling using MCNP software has demonstrated that useful detection capabilities can be deployed. In particular, any of the isotopes examined can be detected at levels between 0.01 and 0.1 μCi per gallon. General purpose instruments that can be used to determine the nature and extent of radioactive contamination and measure radiation levels for purposes of protecting personnel and members of the public should be available. One or more portable radioisotope identifiers (RIIDs) should be available to WTD personnel. Small, portable battery-powered personal radiation monitors should be widely available WTD personnel. The personal monitors can be used for personal and group radiation protection decisions, and to alert management to the need to get expert backup. All considerations of radiological instrumentation require considerations of training and periodic retraining of personnel, as well as periodic calibration and maintenance of instruments. Routine “innocent” alarms will occur due to medical radionuclides that are legally discharged into sanitary sewers on a daily basis.« less

Radiology/Imaging. Clinical Rotation. Instructor's Packet and Student Study Packet.

ERIC Educational Resources Information Center

Texas Univ., Austin. Extension Instruction and Materials Center.

The instructor's packet, the first of two packets, is one of a series of materials designed to help students who are investigating the activities within a radiology department or considering any of the imaging technologies as a career. The material is designed to relate training experience to information studied in the classroom. This packet…

Assisting in Radiology/Imaging. Instructor's Guide, Student's Manual, and Student Learning Activities.

ERIC Educational Resources Information Center

Fair, Helena J.

The instructor's guide, the first of three documents in this package, is designed for a course to help students who are investigating the activities within a radiology department or considering any of the imaging technologies as a career. The material is designed to relate training experience to information studied in the classroom. This…

Characterization and remediation of a mixed waste-contaminated site at Kirtland Air Force Base, New Mexico

DOE Office of Scientific and Technical Information (OSTI.GOV)

Johnston, J.W.; Thacker, M.S.; DeWitt, C.B.

In the area of environmental restoration, one of the most challenging problems is the task of remediating mixed waste-contaminated sites. This paper discusses a successful Interim Corrective Measure (ICM) performed at a mixed waste-contaminated site on Kirtland Air Force Base (AFB) in Albuquerque, New Mexico. The site, known as RW-68, Cratering Area and Radium Dump/Slag Piles, was used during the late 1940s and early 1950s for the destruction and incineration of captured World War II aircraft. It contained 19 slag piles totaling approximately 150 tons of slag, ash, refractory brick, and metal debris. The piles were contaminated with radium-226 andmore » RCRA-characteristic levels of heavy metals. Therefore, the piles were considered mixed waste. To eliminate the threat to human health and the environment, an ICM of removal, segregation, stabilization, and disposal was conducted from October through December 1996. Approximately 120 cubic yards (cu yds) of mixed waste, 188 cu yds of low-level radioactive-contaminated soil, 1 cu yd of low-level radioactive-contaminated debris, 5 cu yds of RCRA-characteristic hazardous waste, and 45 tons of nonhazardous debris were stabilized and disposed of during the ICM. To render the RCRA metals and radionuclides insoluble, stabilization was performed on the mixed and RCRA-characteristic waste streams. All stabilized material was subjected to TCLP analysis to verify it no longer exhibited RCRA-characteristic properties. Radiological and geophysical surveys were conducted concurrently with site remediation activities. These surveys provided real-time documentation of site conditions during each phase of the ICM and confirmed successful cleanup of the site. The three radioactive waste streams, stabilized mixed waste, low-level radioactive-contaminated soil, and low-level radioactive-contaminated debris, were disposed of at the Envirocare low-level radioactive disposal facility.« less

An evaluation of early countermeasures to reduce the risk of internal radiation exposure after the Fukushima nuclear incident in Japan.

PubMed

Nomura, Shuhei; Tsubokura, Masaharu; Gilmour, Stuart; Hayano, Ryugo S; Watanabe, Yuni N; Kami, Masahiro; Kanazawa, Yukio; Oikawa, Tomoyoshi

2016-05-01

After a radiation-release incident, intake of radionuclides in the initial stage immediately following the incident may be the major contributor to total internal radiation exposure for individuals in affected areas. However, evaluation of early internal contamination risk is greatly lacking. This study assessed the relationship between initial stage evacuation/indoor sheltering and internal radiation contamination levels 4 months after the 2011 Fukushima nuclear incident in Japan and estimated potential pathways of the contamination. The study population comprised 525 participants in the internal radiation screening program at Minamisoma Municipal General Hospital, 23 km north of the Fukushima nuclear plant. The analysed dataset included the results of a screening performed in July 2011, 4 months after the incident, and of a questionnaire on early-incident response behaviours, such as sheltering indoors and evacuations, completed by participants. Association between such early countermeasures and internal contamination levels of cesium-134 were assessed using Tobit multiple regression analyses. Our study shows that individuals who evacuated to areas outside Fukushima Prefecture had similar contamination levels of cesium-134 to individuals who stayed in Fukushima (relative risk: 0.86; 95% confidence interval: 0.74-0.99). Time spent outdoors had no significant relationship with contamination levels. The effects of inhalation from radiological plumes released from the nuclear plant on total internal radiation contamination might be so low as to be undetectable by the whole-body counting unit used to examine participants. Given the apparent limited effectiveness of evacuation and indoor sheltering on internal contamination, the decision to implement such early responses to a radiation-release incident should be made by carefully balancing their potential benefits and health risks. © The Author 2015. Published by Oxford University Press. All rights reserved. For permissions, please email: journals.permissions@oup.com.

Analysis of environmental contamination resulting from catastrophic incidents: part 1. Building and sustaining capacity in laboratory networks.

PubMed

Magnuson, Matthew; Ernst, Hiba; Griggs, John; Fitz-James, Schatzi; Mapp, Latisha; Mullins, Marissa; Nichols, Tonya; Shah, Sanjiv; Smith, Terry; Hedrick, Elizabeth

2014-11-01

Catastrophic incidents, such as natural disasters, terrorist attacks, and industrial accidents, can occur suddenly and have high impact. However, they often occur at such a low frequency and in unpredictable locations that planning for the management of the consequences of a catastrophe can be difficult. For those catastrophes that result in the release of contaminants, the ability to analyze environmental samples is critical and contributes to the resilience of affected communities. Analyses of environmental samples are needed to make appropriate decisions about the course of action to restore the area affected by the contamination. Environmental samples range from soil, water, and air to vegetation, building materials, and debris. In addition, processes used to decontaminate any of these matrices may also generate wastewater and other materials that require analyses to determine the best course for proper disposal. This paper summarizes activities and programs the United States Environmental Protection Agency (USEPA) has implemented to ensure capability and capacity for the analysis of contaminated environmental samples following catastrophic incidents. USEPA's focus has been on building capability for a wide variety of contaminant classes and on ensuring national laboratory capacity for potential surges in the numbers of samples that could quickly exhaust the resources of local communities. USEPA's efforts have been designed to ensure a strong and resilient laboratory infrastructure in the United States to support communities as they respond to contamination incidents of any magnitude. The efforts include not only addressing technical issues related to the best-available methods for chemical, biological, and radiological contaminants, but also include addressing the challenges of coordination and administration of an efficient and effective response. Laboratory networks designed for responding to large scale contamination incidents can be sustained by applying their resources during incidents of lesser significance, for special projects, and for routine surveillance and monitoring as part of ongoing activities of the environmental laboratory community. Published by Elsevier Ltd.

Social isolation and delayed discovery of bodies in houses: the value of forensic pathology, anthropology, odontology and entomology in the medico-legal investigation.

PubMed

Archer, M S; Bassed, R B; Briggs, C A; Lynch, M J

2005-07-16

The bodies of socially isolated people may remain undiscovered in their own houses for prolonged periods. Occasionally the body is in situ for sufficient time to become skeletonised, or partially so. Medico-legal investigation of these cases is complicated by degradation and contamination of evidence. Thus, a multidisciplinary forensic investigation is recommended. The potential contributions of forensic pathology, anthropology, odontology and entomology are outlined here with reference to two cases that occurred in Victoria, Australia, in 2003. Forensic pathologists are often unable to determine the cause of death in skeletonised bodies, however, they may find evidence to support either a natural or unnatural mode of death, and they may describe skeletal pathology or trauma, and identify skeletal features to support radiological identification of the deceased. Anthropologists can provide supplementary evidence of skeletal trauma. Additionally, they can assess age, sex, stature and racial affiliation from skeletal remains. Odontologists can identify individuals through comparison with ante-mortem dental records; however, potential difficulties exist in identifying the treating dentist of a socially isolated person. Odontologists may also examine the teeth and oro-facial skeleton for trauma. Entomologists may estimate minimum death time and/or season of death. Entomological examination of insect remains may also confirm that a body has lain in situ for a considerable period.

Associations Between NIH Funding and Advanced Bibliometric Indices Among Radiological Investigators.

PubMed

Rosenkrantz, Andrew B; Jiang, Anthony

2016-06-01

Whereas data support the h index (reflecting both publications and citations) as an indicator of academic productivity, other advanced bibliometric indices aiming to address shortcomings of the h index remain poorly studied. Our objective was to compare the associations between bibliometric indices and total National Institutes of Health (NIH) grant funding among investigators within U.S. academic radiology departments. NIH grant funding amounts for 400 NIH-funded investigators within radiology departments were obtained from Blue Ridge Institute for Medical Research. Investigators' publications and associated citations were identified using Scopus. Indices computed for each investigator included: publication count, citation count, h index, i-10 index, hc index (h index adjusted for recency of publications), m quotient (h index adjusted for career duration), and e index and g index (both account for highly cited articles). Spearman correlations were performed between indices and funding. Multivariable linear regression was performed to identify significant independent predictors of funding. For MD investigators: the indices exhibited no-to-weak correlations with funding (r = 0.173-0.387); m quotient exhibited the largest correlation and was the only significant (albeit weak) independent predictor of funding (P = 0.011). For PhD investigators: correlation with funding was weak for m quotient (r = 0.323), although moderate for other indices (r = 0.518-0.568); publication count exhibited highest correlation; publication count (P < 0.001) and hc index (P = 0.024) were significant independent predictors of funding. Bibliometric indices were more strongly associated with grant funding for PhD than for MD radiology investigators, with publication count exhibiting the strongest association in the latter group. Time-weighted adjustments, as reflected by the m quotient and hc index, may improve efforts to predict funding using bibliometrics. Copyright © 2016 The Association of University Radiologists. Published by Elsevier Inc. All rights reserved.

Surface water sampling and analysis plan for environmental monitoring in Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1994-06-01

This Sampling and Analysis Plan addresses surface water monitoring, sampling, and analysis activities that will be conducted in support of the Environmental Monitoring Plan for Waste Area Grouping (WAG) 6. WAG 6 is a shallow-burial land disposal facility for low-level radioactive waste at the Oak Ridge National Laboratory, a research facility owned by the US Department of Energy and managed by Martin Marietta Energy Systems, Inc. Surface water monitoring will be conducted at nine sites within WAG 6. Activities to be conducted will include the installation, inspection, and maintenance of automatic flow-monitoring and sampling equipment and manual collection of variousmore » water and sediment samples. The samples will be analyzed for various organic, inorganic, and radiological parameters. The information derived from the surface water monitoring, sampling, and analysis will aid in evaluating risk associated with contaminants migrating off-WAG, and will be used in calculations to establish relationships between contaminant concentration (C) and flow (Q). The C-Q relationship will be used in calculating the cumulative risk associated with the off-WAG migration of contaminants.« less

US Department of Energy Grand Junction Projects Office Remedial Action Project. Final report of the decontamination and decommissioning of Building 52 at the Grand Junction Projects Office Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Krabacher, J.E.

1996-08-01

The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, also was the remedial action contractor. Building 52more » was found to be radiologically contaminated and was demolished in 1994. The soil area within the footprint of the building has been remediated in accordance with the identified standards and the area can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.« less

Final report of the decontamination and decommission of Building 31 at the Grand Junction Projects Office Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Krabacher, J.E.

1996-07-01

The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the domestic uranium procurement program funded by the U.S. Atomic Energy Commission. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, also was the remedial actionmore » contractor. Radiological contamination was identified in Building 31 and the building was demolished in 1992. The soil area within the footprint of the building has been remediated in accordance with the identified standards and the area can be released for unlimited exposure and unrestricted use. This area was addressed in the summary final report of the remediation of the exterior areas of the GJPO facility. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.« less

Ames Laboratory site environmental report, calendar year 1988

DOE Office of Scientific and Technical Information (OSTI.GOV)

Mathison, L.K.

1989-05-01

The summarized data and conclusions from the Ames Laboratory environmental monitoring program are presented in this Annual Site Environmental Report. Ames Laboratory is located on the campus of Iowa State University (ISU) and occupies several buildings owned by the Department of Energy. A study is being conducted to identify environmental sampling methods which can characterize and separate the impact of Ames Laboratory's campus activities and that of ISU. This will enable the Laboratory to determine what possible impact it's operations may be having to the environment, if any. Two Pollution Abatement projects were begun in 1988. They were: removal ofmore » thorium contaminated soil resulting from a historical release of thorium at the Laboratory, to the Ames, Iowa Water Pollution Control (sewage) Plant and demolition of a small Blockhouse'' constructed of concrete block which had been used for low level radioactive waste handling. The contaminated soil has been removed and transported to Hanford, WA for disposal. A final site radiological survey for thorium is pending. In addition, contaminated debris was transported to Hanford, WA for disposal and a final site survey is pending. 7 refs., 4 figs., 1 tab.« less

Treatment options for low-level radiologically contaminated ORNL filtercake

DOE Office of Scientific and Technical Information (OSTI.GOV)

Lee, Hom-Ti; Bostick, W.D.

1996-04-01

Water softening sludge (>4000 stored low level contaminated drums; 600 drums per year) generated by the ORNL Process Waste Treatment Plant must be treated, stabilized, and placed in safe storage/disposal. The sludge is primarily CaCO{sub 3} and is contaminated by low levels of {sup 90}Sr and {sup 137}Cs. In this study, microwave sintering and calcination were evaluated for treating the sludge. The microwave melting experiments showed promise: volume reductions were significant (3-5X), and the waste form was durable with glass additives (LiOH, fly ash). A commercial vendor using surrogate has demonstrated a melt mineralization process that yields a dense monolithicmore » waste form with a volume reduction factor (VR) of 7.7. Calcination of the sludge at 850-900 C yielded a VR of 2.5. Compaction at 4500 psi increased the VR to 4.2, but the compressed form is not dimensionally stable. Addition of paraffin helped consolidate fines and yielded a VR of 3.5. In conclusion, microwave melting or another form of vitrification is likely to be the best method; however for immediate implementation, the calculation/compaction/waxing process is viable.« less

Medical management of radiation accidents: capabilities and deployment principles of the Bundeswehr Institute of Radiobiology.

PubMed

Dörr, Harald; Meineke, Viktor

2012-10-01

Radiation accidents are fortunately infrequent occurrences, but since their consequences can be very serious as in the Chernobyl and the Fukushima nuclear accidents, medical management of radiation accidents is of great importance. Besides several other tasks, medical management of radiation accidents is one of the key tasks of the Bundeswehr Institute of Radiobiology. Within a Task Force Unit for medical chemical, biological, radiological, and nuclear (CBRN) Defense, the institute provides designated personnel who will perform clinical investigations on the scene and will liaise with the institute, where different methods for biological dosimetry and dose reconstruction will be performed. The most important aspects of efficient medical management of radiation accidents are diagnosis of radiation-induced health damage, determination of the cause, dealing with contamination/incorporation, pathophysiological and therapeutic principles, preparatory planning, national and international cooperation and training. Military and non-military institutions have to work closely together when it comes to radiation accidents and since national resources are limited and could be exhausted, international networks can help to ensure medical treatment for radiation accident victims.

CBRN Decontamination: Multiservice Tactics, Techniques, and Procedures for Chemical, Biological, Radiological, and Nuclear Decontamination

DTIC Science & Technology

2006-04-01

b. Principles of Decontamination Operations. Decontaminate immediately for an agent on the skin . Perform higher levels of decontamination as a...the mask and hood with paper towels or rags. NOTE: Cool, soapy water is not as effective for removing contamination, but it can be used if you scrub ...N/A N/A 5 N/A Sponge, cellulose II Each As required N/A N/A N/A N/A 2 N/A 4 6 Brush, scrub II Each As required N/A N/A N/A N/A 2 N/A 2 N/A Towels

Factors influencing career choices in radiology trainees in Queensland, Australia.

PubMed

Ip, S W; Ko, H S; Applegate, K E

2010-04-01

The aim of this study was to investigate factors influencing career choices in radiology trainees. We distributed a 27-question written survey to all radiology registrars in Queensland. The questions investigated whether radiology was their first specialty choice, career satisfaction, ideal working conditions and attitudes regarding having children during the time of training. Forty-four of 51 surveys were returned (86% participation rate, 73% men, P = 0.048055) with 100% reporting a high job satisfaction; 28% of male registrars compared to 8% of female registrars did extra work outside of training to earn extra money (P = 0.000003), and 17% of female registrars took a leave of absence during their training, while no male registrar did (P = 0.087923). Only one female trainee worked part-time (P = 0.272727). In addition, 58% of female registrars planned a pregnancy (P = 0.731789) before completion of training; 83% of women versus 75% of men had no children (P = 0.329263). Only 5% of trainees agreed that it was easy to arrange part-time training, only 14% stated that it was easy to negotiate flexible work schedules and 7% agreed that it was easy to return to work after a period of absence. 'Time spent with immediate family' was rated the most important lifestyle factor, followed by 'work hours' and 'on-call duty'. The least important factors were 'being away from extended family', 'availability of part-time work' and whether 'work was in a rural location'. Overall job satisfaction is high among radiology trainees. Nevertheless, lifestyle factors, particularly those related to work time, are becoming more important for career decisions. This should be taken into account when designing and structuring radiology training to ensure that it is considered an attractive career choice.

WASTE HANDLING BUILDING VENTILATION SYSTEM DESCRIPTION DOCUMENT

DOE Office of Scientific and Technical Information (OSTI.GOV)

P.A. Kumar

2000-06-21

The Waste Handling Building Ventilation System provides heating, ventilation, and air conditioning (HVAC) for the contaminated, potentially contaminated, and uncontaminated areas of the Monitored Geologic Repository's (MGR) Waste Handling Building (WHB). In the uncontaminated areas, the non-confinement area ventilation system maintains the proper environmental conditions for equipment operation and personnel comfort. In the contaminated and potentially contaminated areas, in addition to maintaining the proper environmental conditions for equipment operation and personnel comfort, the contamination confinement area ventilation system directs potentially contaminated air away from personnel in the WHB and confines the contamination within high-efficiency particulate air (HEPA) filtration units. Themore » contamination confinement areas ventilation system creates airflow paths and pressure zones to minimize the potential for spreading contamination within the building. The contamination confinement ventilation system also protects the environment and the public by limiting airborne releases of radioactive or other hazardous contaminants from the WHB. The Waste Handling Building Ventilation System is designed to perform its safety functions under accident conditions and other Design Basis Events (DBEs) (such as earthquakes, tornadoes, fires, and loss of the primary electric power). Additional system design features (such as compartmentalization with independent subsystems) limit the potential for cross-contamination within the WHB. The system provides status of important system parameters and equipment operation, and provides audible and/or visual indication of off-normal conditions and equipment failures. The Waste Handling Building Ventilation System confines the radioactive and hazardous material within the building such that the release rates comply with regulatory limits. The system design, operations, and maintenance activities incorporate ALARA (as low as is reasonably achievable) principles to maintain personnel radiation doses to all occupational workers below regulatory limits and as low as is reasonably achievable. The Waste Handling Building Ventilation System interfaces with the Waste Handling Building System by being located within the WHB and by maintaining specific pressures, temperatures, and humidity within the building. The system also depends on the WHB for water supply. The system interfaces with the Site Radiological Monitoring System for continuous monitoring of the exhaust air; the Waste Handling Building Fire Protection System for detection of fire and smoke; the Waste Handling Building Electrical System for normal, emergency, and standby power; and the Monitored Geologic Repository Operations Monitoring and Control System for monitoring and control of the system.« less

Nuclear Forensics and Attribution: A National Laboratory Perspective

NASA Astrophysics Data System (ADS)

Hall, Howard L.

2008-04-01

Current capabilities in technical nuclear forensics - the extraction of information from nuclear and/or radiological materials to support the attribution of a nuclear incident to material sources, transit routes, and ultimately perpetrator identity - derive largely from three sources: nuclear weapons testing and surveillance programs of the Cold War, advances in analytical chemistry and materials characterization techniques, and abilities to perform ``conventional'' forensics (e.g., fingerprints) on radiologically contaminated items. Leveraging that scientific infrastructure has provided a baseline capability to the nation, but we are only beginning to explore the scientific challenges that stand between today's capabilities and tomorrow's requirements. These scientific challenges include radically rethinking radioanalytical chemistry approaches, developing rapidly deployable sampling and analysis systems for field applications, and improving analytical instrumentation. Coupled with the ability to measure a signature faster or more exquisitely, we must also develop the ability to interpret those signatures for meaning. This requires understanding of the physics and chemistry of nuclear materials processes well beyond our current level - especially since we are unlikely to ever have direct access to all potential sources of nuclear threat materials.

Contained radiological analytical chemistry module

DOEpatents

Barney, David M.

1989-01-01

A system which provides analytical determination of a plurality of water chemistry parameters with respect to water samples subject to radiological contamination. The system includes a water sample analyzer disposed within a containment and comprising a sampling section for providing predetermined volumes of samples for analysis; a flow control section for controlling the flow through the system; and a gas analysis section for analyzing samples provided by the sampling system. The sampling section includes a controllable multiple port valve for, in one position, metering out sample of a predetermined volume and for, in a second position, delivering the material sample for analysis. The flow control section includes a regulator valve for reducing the pressure in a portion of the system to provide a low pressure region, and measurement devices located in the low pressure region for measuring sample parameters such as pH and conductivity, at low pressure. The gas analysis section which is of independent utility provides for isolating a small water sample and extracting the dissolved gases therefrom into a small expansion volume wherein the gas pressure and thermoconductivity of the extracted gas are measured.

Contained radiological analytical chemistry module

DOEpatents

Barney, David M.

1990-01-01

A system which provides analytical determination of a plurality of water chemistry parameters with respect to water samples subject to radiological contamination. The system includes a water sample analyzer disposed within a containment and comprising a sampling section for providing predetermined volumes of samples for analysis; a flow control section for controlling the flow through the system; and a gas analysis section for analyzing samples provided by the sampling system. The sampling section includes a controllable multiple port valve for, in one position, metering out sample of a predetermined volume and for, in a second position, delivering the material sample for analysis. The flow control section includes a regulator valve for reducing the pressure in a portion of the system to provide a low pressure region, and measurement devices located in the low pressure region for measuring sample parameters such as pH and conductivity, at low pressure. The gas analysis section which is of independent utility provides for isolating a small water sample and extracting the dissolved gases therefrom into a small expansion volume wherein the gas pressure and thermoconductivity of the extracted gas are measured.

Qualification tests for {sup 192}Ir sealed sources

DOE Office of Scientific and Technical Information (OSTI.GOV)

Iancso, Georgeta, E-mail: georgetaiancso@yahoo.com; Iliescu, Elena, E-mail: georgetaiancso@yahoo.com; Iancu, Rodica, E-mail: georgetaiancso@yahoo.com

This paper describes the results of qualification tests for {sup 192}Ir sealed sources, available in Testing and Nuclear Expertise Laboratory of National Institute for Physics and Nuclear Engineering 'Horia Hulubei' (I.F.I.N.-HH), Romania. These sources had to be produced in I.F.I.N.-HH and were tested in order to obtain the authorization from The National Commission for Nuclear Activities Control (CNCAN). The sources are used for gammagraphy procedures or in gammadefectoscopy equipments. Tests, measurement methods and equipments used, comply with CNCAN, AIEA and International Quality Standards and regulations. The qualification tests are: 1. Radiological tests and measurements: dose equivalent rate at 1 m;more » tightness; dose equivalent rate at the surface of the transport and storage container; external unfixed contamination of the container surface. 2. Mechanical and climatic tests: thermal shock; external pressure; mechanic shock; vibrations; boring; thermal conditions for storage and transportation. Passing all tests, it was obtained the Radiological Security Authorization for producing the {sup 192}Ir sealed sources. Now IFIN-HH can meet many demands for this sealed sources, as the only manufacturer in Romania.« less

Air and smear sample calculational tool for Fluor Hanford Radiological control

DOE Office of Scientific and Technical Information (OSTI.GOV)

BAUMANN, B.L.

2003-07-11

A spreadsheet calculation tool was developed to automate the calculations performed for determining the concentration of airborne radioactivity and smear counting as outlined in HNF-13536, Section 5.2.7, ''Analyzing Air and Smear Samples''. This document reports on the design and testing of the calculation tool. Radiological Control Technicians (RCTs) will save time and reduce hand written and calculation errors by using an electronic form for documenting and calculating work place air samples. Current expectations are RCTs will perform an air sample and collect the filter or perform a smear for surface contamination. RCTs will then survey the filter for gross alphamore » and beta/gamma radioactivity and with the gross counts utilize either hand calculation method or a calculator to determine activity on the filter. The electronic form will allow the RCT with a few key strokes to document the individual's name, payroll, gross counts, instrument identifiers; produce an error free record. This productivity gain is realized by the enhanced ability to perform mathematical calculations electronically (reducing errors) and at the same time, documenting the air sample.« less

Assessment of microbial contamination of radiographic equipment and materials during intraoral imaging procedures.

PubMed

Pinheiro, S L; Martoni, S C; Ogera, R R

2012-05-01

Aim of the present study was to assess microbial contamination of radiology procedures. Patients who needed radiographic exams were selected and the bisecting technique was used: G1 - (control): absence of plastic barrier and overgloving or disinfectant solutions; G2 - alcohol spraying; G3 - protection of the film with a plastic barrier and alcohol spray; G4 - protection of film with plastic barrier, use of overgloving and alcohol spray. The following regions were assessed: trigger switch, X-ray tube, sleeve of the portable dark chamber, water, developer and fixer. The areas for microbiological sample collection were standardized with a label cut internally so that the hollow area was 5 cm long and 2 cm wide. One mL of the developer, water and fixer were also collected before and after developing the films. The samples were incubated under anaerobiosis and aerobiosis. The results were submitted to the Cochran's Q and Mann-Whitney tests. The sleeve of the developing chamber showed greater anaerobic contamination followed by the X-ray tube and only the use of alcohol associated with mechanical barriers was efficient to control this microbiota. The trigger showed higher aerobic microbial contamination and the use of alcohol or alcohol associated with mechanical barriers was efficient to control this microbiota. The developing solutions presented no significant growth of anaerobic and aerobic bacteria. The characteristic of an aerobic or anaerobic microbial strain influences microbial contamination while radiographic projections are being taken and the use of alcohol associated with a plastic barrier and overgloving is indicated to reduce this microbiota.

Transport and transformations of chlorinated-solvent contamination in a saprolite and fractured rock aquifer near a former wastewater-treatment plant, Greenville, South Carolina

USGS Publications Warehouse

Vroblesky, D.A.; Bradley, P.M.; Lane, J.W.; Robertson, J.F.

1997-01-01

The transport and fate of chlorinated-ethene contamination was investigated in a fractured-rock aquifer downgradient from a wastewater-treatment plant at a gas-turbine manufacturing facility in Greenville, South Carolina. A vapor-diffusion-sampler technique, developed for this investigation, located fracture zones that discharged contaminated ground water to surface water. The distribution of chlorinated compounds and sulfate, comparison of borehole geophysical data, driller's logs, and the aquifer response to pumpage allowed subsurface contaminant-transport pathways to be delineated.The probable contaminant-transport pathway from the former aeration lagoon was southward. The probable pathway of contaminant transport from the former sludge lagoon was southward to and beneath Little Rocky Creek. South of the creek, the major pathway of contaminant transport appeared to be at a depth of approximately 80 to 107 feet below land surface. The contaminant-transport pathway from the former industrial lagoon was not readily discernible from existing data. A laboratory investigation, as well as examination of ground- water-chemistry data collected during this investigation and concentrations of chlorinated compounds collected during previous investigations,indicates that higher chlorinated compounds are being degraded to lower-chlorinated compounds in the contaminated aquifer. The approaches used in this investigation, as well as the findings, have potential application to other fractured-rock aquifers contaminated by chlorinated ethenes.

Association between bacterial infection and radiologically confirmed pneumonia among children.

PubMed

Nascimento-Carvalho, Cristiana M; Araújo-Neto, César A; Ruuskanen, Olli

2015-05-01

The role of chest radiograph (CXR) among children with community-acquired pneumonia is controversial. We aimed to assess if there is association between a specific etiology and radiologically confirmed pneumonia. This was a prospective cross-sectional study. Based on report of respiratory complaints and fever/difficulty breathing plus the detection of pulmonary infiltrate/pleural effusion on the CXR taken upon admission read by the pediatrician on duty, children <5-year-old hospitalized with community-acquired pneumonia were enrolled. On admission, clinical data and biological samples were collected to investigate 19 etiological agents (11 viruses and 8 bacteria). CXR taken upon admission was independently read by a pediatric radiologist blinded to clinical data. The study group comprised 209 cases with evaluated CXR and establishment of a probable etiology. Radiologically confirmed pneumonia, normal CXR and other radiographic diagnoses were described for 165 (79.0%), 36 (17.2%) and 8 (3.8%) patients, respectively. Viral infection was significantly more common among patients without radiologically confirmed pneumonia (68.2% vs. 47.9%; P = 0.02), particularly among those with normal CXR (66.7% vs. 47.9%; P = 0.04) when compared with patients with radiologically confirmed pneumonia. Bacterial infection was more frequent among cases with radiologically confirmed pneumonia (52.1% vs. 31.8%; P = 0.02). Likewise, pneumococcal infection was more frequently detected among children with radiologically confirmed pneumonia in regard to children with normal CXR (24.2% vs. 8.3%; P = 0.04). Sensitivity (95% confidence interval) of radiologically confirmed pneumonia for pneumococcal infection was 93% (80-98%), and negative predictive value (95% confidence interval) of normal CXR for pneumococcal infection was 92% (77-98%). Bacterial infection, especially pneumococcal one, is associated with radiologically confirmed pneumonia.

Role of follow-up endoscopic examination in treatment response assessment for patients with gastric diffuse large B cell lymphoma.

PubMed

Yoon, Seung Bae; Lee, In Seok; Lee, Ha Ni; Kim, Eunyoung; Kim, Woohyeon; Lee, Han Hee; Lee, Bo-In; Choi, Myung-Gyu; Jung, Seung Eun; Choi, Byung Ock; Park, Gyeong Sin; Cho, Seok-Goo

2016-09-01

According to lymphoma guidelines, gastric diffuse large B cell lymphoma (DLBCL) patients should undergo regular computed tomography (CT) and/or positron emission tomography (PET) examinations to assess treatment response. Endoscopic examinations are not indicated in the guidelines. The aim of this study was to investigate the utility of endoscopic examinations during and after treatment for DLBCL. We reviewed the patients diagnosed with gastric DLBCL at Seoul St. Mary's Hospital. All patients underwent endoscopy and radiologic examinations at every follow-up appointment. Radiologic response was defined according to World Health Organization criteria and endoscopic response was determined based on the Groupe d'Etude des Lymphomes de l'Adult grading system that is widely used in post-treatment evaluation of gastric MALT lymphoma. Forty-five patients were analyzed. Within a median follow-up period of 34 months, 35 patients achieved both radiologic and endoscopic complete remission (CR). The median times to endoscopic and radiologic CR were not significantly different (21 versus 16 weeks, p = 0.118). However, in 25 patients with stage I disease, endoscopic CR [median (range), 20 (11-36)] was achieved later than radiologic CR [median (range), 13 (8-36)] (p = 0.027). Among 40 patients who achieved radiologic CR, 35 patients who also achieved endoscopic CR maintained remission during the follow-up. Two of the five patients who achieved radiologic CR without endoscopic CR experienced recurrence. In gastric DLBCL patients, endoscopic response does not always correlate with radiologic response and might predict disease recurrence. We suggest that follow-up endoscopic examination with biopsy should be performed in addition to radiologic examination.

Mixed methods study on the use of and attitudes towards safety checklists in interventional radiology.

PubMed

Munn, Zachary; Giles, Kristy; Aromataris, Edoardo; Deakin, Anita; Schultz, Timothy; Mandel, Catherine; Peters, Micah Dj; Maddern, Guy; Pearson, Alan; Runciman, William

2018-02-01

The use of safety checklists in interventional radiology is an intervention aimed at reducing mortality and morbidity. Currently there is little known about their practical use in Australian radiology departments. The primary aim of this mixed methods study was to evaluate how safety checklists (SC) are used and completed in radiology departments within Australian hospitals, and attitudes towards their use as described by Australian radiologists. A mixed methods approach employing both quantitative and qualitative techniques was used for this study. Direct observations of checklist use during radiological procedures were performed to determine compliance. Medical records were also audited to investigate whether there was any discrepancy between practice (actual care measured by direct observation) and documentation (documented care measured by an audit of records). A focus group with Australian radiologists was conducted to determine attitudes towards the use of checklists. Among the four participating radiology departments, overall observed mean completion of the components of the checklist was 38%. The checklist items most commonly observed to be addressed by the operating theatre staff as noted during observations were correct patient (80%) and procedure (60%). Findings from the direct observations conflicted with the medical record audit, where there was a higher percentage of completion (64% completion) in comparison to the 38% observed. The focus group participants spoke of barriers to the use of checklists, including the culture of radiology departments. This is the first study of safety checklist use in radiology within Australia. Overall completion was low across the sites included in this study. Compliance data collected from observations differed markedly from reported compliance in medical records. There remain significant barriers to the proper use of safety checklists in Australian radiology departments. © 2017 The Royal Australian and New Zealand College of Radiologists.

NOTE: Investigating the potential of polymer gel dosimetry for interventional radiology: first results

NASA Astrophysics Data System (ADS)

Antoniou, P. E.; Bousbouras, P.; Sandaltzopoulos, R.; Kaldoudi, E.

2008-04-01

Complex interventional radiology (IR) procedures contribute an increasing percentage of the overall medical radiation exposure of the population making accurate dosimetry a challenge. Magnetic resonance (MR) based polymer gel dosimetry has been widely employed in complex dosimetric problems in radiotherapy. The aim of this note is to investigate the feasibility of normoxic gel dosimetry in IR. Dose response, energy dependence and dose rate dependence were investigated in irradiation set-ups relevant to IR for a particular normoxic gel, based on methacrylic acid (MAA) as the monomer and including tetrakis-hydroxy-methyl-phosphonium chloride (THPC) as antioxidant. The gel presents a linear dose response beyond a 25 cGy threshold. No significant energy dependence was observed in the useful range of interventional radiology (80-110 kVp). A linear correlation between the gel response and dose rate was observed in the range of dose rates relevant to IR (5-8 cGy min-1). These results demonstrate a reduction of gel sensitivity at very low dose rate levels. A possible explanation of this effect is suggested.

An assessment of air as a source of DNA contamination encountered when performing PCR.

PubMed

Witt, Nina; Rodger, Gillian; Vandesompele, Jo; Benes, Vladimir; Zumla, Alimuddin; Rook, Graham A; Huggett, Jim F

2009-12-01

Sensitive molecular methods, such as the PCR, can detect low-level contamination, and careful technique is required to reduce the impact of contaminants. Yet, some assays that are designed to detect high copy-number target sequences appear to be impossible to perform without contamination, and frequently, personnel or laboratory environment are held responsible as the source. This complicates diagnostic and research analysis when using molecular methods. To investigate the air specifically as a source of contamination, which might occur during PCR setup, we exposed tubes of water to the air of a laboratory and clean hood for up to 24 h. To increase the chances of contamination, we also investigated a busy open-plan office in the same way. All of the experiments showed the presence of human and rodent DNA contamination. However, there was no accumulation of the contamination in any of the environments investigated, suggesting that the air was not the source of contamination. Even the air from a busy open-plan office was a poor source of contamination for all of the DNA sequences investigated (human, bacterial, fungal, and rodent). This demonstrates that the personnel and immediate laboratory environment are not necessarily to blame for the observed contamination.

Radioactivity in Virgin Soils and Soils from Some Areas with Closed Uranium Mining Facilities in Bulgaria

NASA Astrophysics Data System (ADS)

Yordanova, I.; Staneva, D.; Misheva, L.; Bineva, Ts.; Banov, M.

2012-04-01

The soil radioecology is an important part of the environmental research in the country. Since the beginning of the 1970's regular monitoring of the content of different radionuclides in Bulgarian soils has been done. Objective of the studies were virgin soils from high mountain areas, hills and plains (the region of Kozloduy NPP and the Danube river valley). Natural and men-made radionuclides were observed. In the 25-year period after the the contamination with radionuclides due to the 1986 Chernobyl NPP accident a rich data base has been collected, recording the radiation status of the soils in Bulgaria. Special attention has been paid to the contamination with the long-lived technogenic radionuclides caesium-137 and strontium-90. This paper presents a summary of the obtained results. Caesium-137 and strontium-90 were the main men-made radionuclides detected in the examined Bulgarian soils few years after the Chernobyl NPP accident. Their content in the soils from high mountain areas (Rodopa and Rila mountains) is several times higher than that in the soils from North Bulgaria and Sofia fields. High non-homogenity in the pollution within small areas (even as small as several square meters) has been observed. Natural radioactivity was also studied. Averaged values for natural radionuclides like uranium-238, thorium-232, and radium-226 in virgin soils from different areas in the country are presented. A comparison of the dynamics of their behavior throughout the years is done. Bulgaria is a country with intensive uranium mining activities in the past years. That is why radiological monitoring of closed uranium mining facilities in different regions of the country are obligatory and of great interest. This work presents results from such investigations made in regions where remediation has been done. The results have been evaluated according to the Bulgarian radionuclide environment contamination legislation. The necessity of permanent environmental monitoring is assessed.

Making the invisible visible: a qualitative study of the values, attitudes and norms of radiologists relating to radiation safety.

PubMed

Fridell, Kent; Ekberg, Jessica

2016-06-01

Some shortcomings regarding safety have emerged in inspections by the Swedish Radiation Safety Authority of Swedish radiology departments which perform 5.4 million radiological examinations and 100 000 nuclear scans annually. To ensure safety in the healthcare system and to build a strong environment of radiation protection for patients (and for employees) there must be a strong culture of safety. To understand an organization's behaviour, decisions and actions it is important to study its cultural values. The aims of this study were to discuss how values, attitudes and norms affect radiologists' decisions as well as how they influence the implementation of various radiation protection measures. To investigate this, focus group interviews and in-depth individual interviews were performed in a sample from a number of radiology departments at hospitals in Sweden. The results show that the core value was derived from the patients' perspective with the focus on the knowledge that he or she has come to the healthcare system for a particular reason: to discover disease or, in the best case, to be declared healthy. The majority attitudes were based on experiences associated with aspects that the radiologist could not influence. This often concerns increased pressure on radiology investigations from clinics in the various operational units. Under the concept of norms, the radiologists in the study requested that the development of regulations and guidelines should be connected to issues of justification for various radiological queries.

Computer-assisted virtual autopsy using surgical navigation techniques.

PubMed

Ebert, Lars Christian; Ruder, Thomas D; Martinez, Rosa Maria; Flach, Patricia M; Schweitzer, Wolf; Thali, Michael J; Ampanozi, Garyfalia

2015-01-01

OBJECTIVE; Virtual autopsy methods, such as postmortem CT and MRI, are increasingly being used in forensic medicine. Forensic investigators with little to no training in diagnostic radiology and medical laypeople such as state's attorneys often find it difficult to understand the anatomic orientation of axial postmortem CT images. We present a computer-assisted system that permits postmortem CT datasets to be quickly and intuitively resliced in real time at the body to narrow the gap between radiologic imaging and autopsy. Our system is a potentially valuable tool for planning autopsies, showing findings to medical laypeople, and teaching CT anatomy, thus further closing the gap between radiology and forensic pathology.

Evaluation of residual uranium contamination in the dirt floor of an abandoned metal rolling mill.

PubMed

Glassford, Eric; Spitz, Henry; Lobaugh, Megan; Spitler, Grant; Succop, Paul; Rice, Carol

2013-02-01

A single, large, bulk sample of uranium-contaminated material from the dirt floor of an abandoned metal rolling mill was separated into different types and sizes of aliquots to simulate samples that would be collected during site remediation. The facility rolled approximately 11,000 tons of hot-forged ingots of uranium metal approximately 60 y ago, and it has not been used since that time. Thirty small mass (≈ 0.7 g) and 15 large mass (≈ 70 g) samples were prepared from the heterogeneously contaminated bulk material to determine how measurements of the uranium contamination vary with sample size. Aliquots of bulk material were also resuspended in an exposure chamber to produce six samples of respirable particles that were obtained using a cascade impactor. Samples of removable surface contamination were collected by wiping 100 cm of the interior surfaces of the exposure chamber with 47-mm-diameter fiber filters. Uranium contamination in each of the samples was measured directly using high-resolution gamma ray spectrometry. As expected, results for isotopic uranium (i.e., U and U) measured with the large-mass and small-mass samples are significantly different (p < 0.001), and the coefficient of variation (COV) for the small-mass samples was greater than for the large-mass samples. The uranium isotopic concentrations measured in the air and on the wipe samples were not significantly different and were also not significantly different (p > 0.05) from results for the large- or small-mass samples. Large-mass samples are more reliable for characterizing heterogeneously distributed radiological contamination than small-mass samples since they exhibit the least variation compared to the mean. Thus, samples should be sufficiently large in mass to insure that the results are truly representative of the heterogeneously distributed uranium contamination present at the facility. Monitoring exposure of workers and the public as a result of uranium contamination resuspended during site remediation should be evaluated using samples of sufficient size and type to accommodate the heterogeneous distribution of uranium in the bulk material.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Noshkin, V. E.; Robison, W. L.

Between June 1946 and October 1958, Enewetak and Bikini Atolls were used by the United States as testing grounds for 66 nuclear devices. The combined explosive yield from these tests was 107 Mt (Mt TNT equivalents). This testing produced close-in fallout debris that was contaminated with quantities of radioactive fission and particle activated products, and unspent radioactive nuclear fuel that entered the aquatic environment of the atolls. Today, the sediments in the lagoons are reservoirs for 10's of TBq of the transuranics and some long-lived fission and activation products. The larger amounts of contamination are associated with fine and coarsemore » sediment material adjacent to the locations of the high yield explosions. Radionuclides are also distributed vertically in the sediment column to various depths in all regions of the lagoons. Concentrations greater than fallout background levels are found in filtered water sampled over several decades from all locations and depths in the lagoons. This is a direct indication that the radionuclides are continuously mobilized to solution from the solid phases. Of particular importance is the fact that the long-lived radionuclides are accumulated to different levels by indigenous aquatic plants and organisms that are used as food by resident people. One might anticipate finding continuous high contamination levels in many of the edible marine organisms from the lagoons, since the radionuclides associated with the sediments are not contained and are available to the different organisms in a relatively shallow water environment. This is not the case. We estimate that the radiological dose from consumption of the edible parts of marine foods at Enewetak and Bikini is presently about 0.05% of the total 50-year integral effective dose from all other exposure pathways that include ingestion of terrestrial foods and drinking water, external exposure and inhalation. The total radiological dose from the marine pathway is dominated by the natural radionuclides, {sup 210}Po and {sup 210}Pb. Man-made radionuclides presently contribute less than 0.3% of the dose from these natural radionuclides in the marine food chain.« less

Current radiological situation in areas of Ukraine contaminated by the Chernobyl accident: Part 1. Human dietary exposure to Caesium-137 and possible mitigation measures.

PubMed

Labunska, I; Kashparov, V; Levchuk, S; Santillo, D; Johnston, P; Polishchuk, S; Lazarev, N; Khomutinin, Y

2018-08-01

This study reports for the first time temporal trends for the period of 2011-2016 in 137 Cs content in cow's milk originating from private farms and households of 14 settlements located in the territories of the Rivne region, Ukraine. These areas are still radioactively contaminated as a result of the accident at the Chernobyl Nuclear Power Plant (ChNPP) in 1986. In 2016, the average 137 Cs activity concentration in milk exceeded the Ukrainian Permissible Level (PL) for adults of 100 Bq/l in samples from 6 settlements and the PL for children of 40 Bq/l in 8 settlements, reaching activity concentration of around 500 Bq/l in some samples. Estimated annual effective doses calculated utilizing two different methodologies were in the range of 1.4-2.6 mSv/year and 1.2-1.8 mSv/year, respectively. The estimated effective period of milk semi-purification (T 1/2 _ eff ) from 137 Cs in these settlements was in the range from 8 to 17 years. The estimated ecological period of milk semi-purification (T 1/2 _ eco ) from 137 Cs was in the range from 11 to 36 years. The optimization of the remedial actions strategy for investigated settlements exposed to an effective dose above 1 mSv/year (as estimated in 2016) has shown that a diversity of measures can decrease effective dose for a representative person to below 1 mSv/year. Such measures include application of Ferrocyn to cows, mineral fertilization of potato fields, information campaigns on consumption of wild mushrooms and other forestry products, and feeding pigs with uncontaminated fodder. The total costs of such measures are estimated to be about 71,000 Euro per year for the combined population (8336 inhabitants) of the six villages investigated in this study that showed the highest median residual 137 Cs activity concentrations in milk, with a subsequent decrease in cost in the future. This would result in an averted collective dose of 11 man-Sv, at an average cost of 6.5 kEuro/man-Sv averted. In the absence of governmental programs for implementation of necessary protective measures to reduce radiological risks to impacted populations, the exceedance of PL for the activity concentration of 137 Cs in cow's milk for adults of 100 Bq/l in the Chernobyl-affected areas of Ukraine could persist for many more years - until at least 2040. Copyright © 2018 Elsevier Ltd. All rights reserved.

Root cause investigation of a viral contamination incident occurred during master cell bank (MCB) testing and characterization--a case study.

PubMed

Chen, Dayue; Nims, Raymond; Dusing, Sandra; Miller, Pamela; Luo, Wen; Quertinmont, Michelle; Parekh, Bhavin; Poorbaugh, Josh; Boose, Jeri Ann; Atkinson, E Morrey

2008-11-01

An adventitious agent contamination occurred during a routine 9 CFR bovine viral screening test at BioReliance for an Eli Lilly Chinese Hamster Ovary (CHO) cell-derived Master Cell Bank (MCB) intended for biological production. Scientists from the sponsor (Eli Lilly and Company) and the testing service company (BioReliance) jointly conducted a systematic investigation in an attempt to determine the root cause of the contamination. Our investigation resulted in the identification of the viral nature of the contaminant. Subsequent experiments indicated that the viral contaminant was a non-enveloped and non-hemadsorbing virus. Transmission electron microscopy (TEM) revealed that the viral contaminant was 25-30 nm in size and morphologically resembled viruses of the family Picornaviridae. The contaminant virus was readily inactivated when exposed to acidic pH, suggesting that the viral contaminant was a member of rhinoviruses. Although incapable of infecting CHO cells, the viral contaminant replicated efficiently in Vero cell with a life cycle of approximately 16 h. Our investigation provided compelling data demonstrating that the viral contaminant did not originate from the MCB. Instead, it was introduced into the process during cell passaging and a possible entry point was proposed. We identified the viral contaminant as an equine rhinitis A virus using molecular cloning and DNA sequencing. Finally, our investigation led us to conclude that the source of the viral contaminant was the equine serum added to the cell growth medium in the 9 CFR bovine virus test.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Haywood, F.F.; Dickson, H.W.; Cottrell, W.D.

A radiological survey was made of the former Bridgeport Brass Special Metals Extrusion Plant in Adrian, Michigan, now owned by General Motors Corporation. This plant was operated to extrude uranium metal which was used in the fabrication of reactor fuel for the Hanford, Washington, and Savannah River, South Carolina, plants. Activities at the Adrian plant included preparation of material for extrusion, abrasive sawing, storing, packaging, and shipping. When the original contract was concluded, most of the equipment was dismantled and salvaged. The current property owner cleaned much of the building and conducted his own radiological survey. The results of themore » General Motors survey indicated that the area originally involved in the uranium handling and processing operation was within tolerances under the provision of guidelines applicable at the time the facility was decommissioned. A comprehensive survey was conducted in that area by a team of health physicists from the Oak Ridge National Laboratory (ORNL). The results of this survey tend to confirm the findings of the General Motors report, except that some floor areas were contaminated in excess of applicable guidelines and some off-gas ducts which had been used in the cutting area were found to be contaminated with uranium. These ducts were removed, the floor areas were cleaned, and a subsequent resurvey of the plant was made. An additional survey of a portion of the facility was conducted by ORNL health physicists after learning that service pits had existed beneath the extrusion units. Sometime after extrusion operations ceased, these pits were filled with sand and covered over at the existing floor level with concrete. Results of this survey revealed concentrations of /sup 238/U up to 21,000 pCi/g of residue, scale, and other miscellaneous materials collected from the bottom of service pits, service manholes, and holding tanks.« less

Predicted cumulative dose to firefighters and the offsite public from natural and anthropogenic radionuclides in smoke from wildland fires at the Savannah River Site, South Carolina USA.

PubMed

Viner, Brian J; Jannik, Tim; Hepworth, Allan; Adetona, Olorunfemi; Naeher, Luke; Eddy, Teresa; Doman, Eric; Blake, John

2018-02-01

The contaminated ground surface at Savannah River Site (SRS) is a result of the decades of work that has been performed maintaining the country's nuclear stockpile and performing research and development on nuclear materials. The volatilization of radionuclides during wildfire results in airborne particles that are dispersed within the smoke plume and may result in doses to downwind firefighters and the public. To better understand the risk that these smoke plumes present, we have characterized four regions at SRS in terms of their fuel characteristics and radiological contamination on the ground. Combined with general meteorological conditions describing typical and extreme burn conditions, we have simulated potential fires in these regions and predicted the potential radiological dose that could be received by firefighting personnel and the public surrounding the SRS. In all cases, the predicted cumulative dose was a small percent of the US Department of Energy regulatory limit (0.25 mSv). These predictions were conservative and assumed that firefighters would be exposed for the duration of their shift and the public would be exposed for the entire day over the duration of the burn. Realistically, firefighters routinely rotate off the firefront during their shift and the public would likely remain indoors much of the day. However, we show that even under worst-case conditions the regulatory limits are not exceeded. We can infer that the risks associated with wildfires would not be expected to cause cumulative doses above the level of concern to either responding personnel or the offsite public. Copyright © 2017 Elsevier Ltd. All rights reserved.

A public health perspective on the U.S. response to the Fukushima radiological emergency.

PubMed

Whitcomb, Robert C; Ansari, Armin J; Buzzell, Jennifer J; McCurley, M Carol; Miller, Charles W; Smith, James M; Evans, D Lynn

2015-03-01

On 11 March 2011, northern Japan was struck by first a magnitude 9.0 earthquake off the eastern coast and then by an ensuing tsunami. At the Fukushima Dai-ichi Nuclear Power Plant (NPP), these twin disasters initiated a cascade of events that led to radionuclide releases. Radioactive material from Japan was subsequently transported to locations around the globe, including the U.S. The levels of radioactive material that arrived in the U.S. were never large enough to cause health effects, but the presence of this material in the environment was enough to require a response from the public health community. Events during the response illustrated some U.S. preparedness challenges that previously had been anticipated and others that were newly identified. Some of these challenges include the following: (1) Capacity, including radiation health experts, for monitoring potentially exposed people for radioactive contamination are limited and may not be adequate at the time of a large-scale radiological incident; (2) there is no public health authority to detain people contaminated with radioactive materials; (3) public health and medical capacities for response to radiation emergencies are limited; (4) public health communications regarding radiation emergencies can be improved to enhance public health response; (5) national and international exposure standards for radiation measurements (and units) and protective action guides lack uniformity; (6) access to radiation emergency monitoring data can be limited; and (7) the Strategic National Stockpile may not be currently prepared to meet the public health need for KI in the case of a surge in demand from a large-scale radiation emergency. Members of the public health community can draw on this experience to improve public health preparedness.

Predicted cumulative dose to firefighters and the offsite public from natural and anthropogenic radionuclides in smoke from wildland fires at the Savannah River Site, South Carolina USA

DOE PAGES

Viner, Brian J.; Jannik, Tim; Hepworth, Allan; ...

2017-11-22

The contaminated ground surface at Savannah River Site (SRS) is a result of the decades of work that has been performed maintaining the country's nuclear stockpile and performing research and development on nuclear materials. The volatilization of radionuclides during wildfire results in airborne particles that are dispersed within the smoke plume and may result in doses to downwind firefighters and the public. To better understand the risk that these smoke plumes present, we have characterized four regions at SRS in terms of their fuel characteristics and radiological contamination on the ground. Combined with general meteorological conditions describing typical and extrememore » burn conditions, we have simulated potential fires in these regions and predicted the potential radiological dose that could be received by firefighting personnel and the public surrounding the SRS. In all cases, the predicted cumulative dose was a small percent of the US Department of Energy regulatory limit (0.25 mSv). These predictions were conservative and assumed that firefighters would be exposed for the duration of their shift and the public would be exposed for the entire day over the duration of the burn. Realistically, firefighters routinely rotate off the firefront during their shift and the public would likely remain indoors much of the day. However, we show that even under worst-case conditions the regulatory limits are not exceeded. In conclusion, we can infer that the risks associated with wildfires would not be expected to cause cumulative doses above the level of concern to either responding personnel or the offsite public.« less

Predicted cumulative dose to firefighters and the offsite public from natural and anthropogenic radionuclides in smoke from wildland fires at the Savannah River Site, South Carolina USA

DOE Office of Scientific and Technical Information (OSTI.GOV)

Viner, Brian J.; Jannik, Tim; Hepworth, Allan

The contaminated ground surface at Savannah River Site (SRS) is a result of the decades of work that has been performed maintaining the country's nuclear stockpile and performing research and development on nuclear materials. The volatilization of radionuclides during wildfire results in airborne particles that are dispersed within the smoke plume and may result in doses to downwind firefighters and the public. To better understand the risk that these smoke plumes present, we have characterized four regions at SRS in terms of their fuel characteristics and radiological contamination on the ground. Combined with general meteorological conditions describing typical and extrememore » burn conditions, we have simulated potential fires in these regions and predicted the potential radiological dose that could be received by firefighting personnel and the public surrounding the SRS. In all cases, the predicted cumulative dose was a small percent of the US Department of Energy regulatory limit (0.25 mSv). These predictions were conservative and assumed that firefighters would be exposed for the duration of their shift and the public would be exposed for the entire day over the duration of the burn. Realistically, firefighters routinely rotate off the firefront during their shift and the public would likely remain indoors much of the day. However, we show that even under worst-case conditions the regulatory limits are not exceeded. In conclusion, we can infer that the risks associated with wildfires would not be expected to cause cumulative doses above the level of concern to either responding personnel or the offsite public.« less

Maintenance action readiness assessment plan for White Oak Creek and Melton Branch Weir Stilling Pool cleanout at Oak Ridge National Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1995-08-01

This Readiness Assessment Plan has been prepared to document operational readiness for the following maintenance action: (1) removal of sediment from the White Oak Creek and Melton Branch Weir Stilling Pools and (2) disposal of the radiologically contaminated sediment in another location upstream of the weirs in an area previously contaminated by stream overflow from Melton Branch in Waste Area Grouping 2 (WAG) at Oak Ridge National Laboratory. This project is being performed as a maintenance action rather than an action under the Comprehensive Environmental Response, Compensation, and Liability Act because the risk to human health and environment is wellmore » below the US Environmental Protection Agency`s level of concern. The decision to proceed as a maintenance action was documented by an interim action proposed plan, which is included in the administrative record. The administrative record is available for review at the US Department of Energy Information Resource Center, 105 Broadway Avenue, Oak Ridge, Tennessee 37830.« less

Removal site evaluation report for the Isotope Facilities at Oak Ridge National Laboratory, Oak Ridge, Tennessee

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

This removal site evaluation (RmSE) report of the Isotope Facilities at Oak Ridge National Laboratory (ORNL) was prepared to provide the Environmental Restoration Program with information necessary to evaluate whether hazardous and/or radiological contaminants in and around the Isotopes Facility pose a substantial risk to human health or the environment and if remedial site evaluations (RSEs) or removal actions are required. The scope of the project included: (1) a review of historical evidence regarding operations and use of the facility; (2) interviews with facility personnel concerning current and past operating practices; (3) a site inspection; and (4) identification of hazardmore » areas requiring maintenance, removal, or remedial actions. The results of RmSE indicate that no substantial risks exist from contaminants present in the Isotope Facilities because adequate controls and practices exist to protect human health and the environment. The recommended correction from the RmSE are being conducted as maintenance actions; accordingly, this RmSE is considered complete and terminated.« less

Effectiveness of sheltering in buildings and vehicles for plutonium

DOE Office of Scientific and Technical Information (OSTI.GOV)

Engelmann, R.J.

1990-07-30

The purpose of this paper is to collect and present current knowledge relevant to the protection offered by sheltering against exposure to plutonium particles released to the atmosphere during accidents. For those many contaminants for which effects are linear with the airborne concentration, it is convenient to define a Dose Reduction Factor (DRF). In the past, the DRF has been defined as the ratio of the radiological dose that may be incurred within the shelter to that in the outdoors. As such, it includes the dose through shine from plumes aloft and from material deposited on the surface. For thismore » paper, which is concerned only with the inhalation pathway, the DRF is the ratio of the time-integrated concentration inside the shelter to that outdoors. It is important to note that the range over which effects are linear with concentration may be limited for many contaminants. Examples are when concentrations produce effects that are irreversible, or when concentrations are below effects threshold levels. 71 refs., 4 figs., 8 tabs.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

The U.S. Department of Energy Weldon Spring Site Remedial Action Project (chemical plant site), is a former uranium processing facility located in eastern Missouri on the property of the former U.S. Army Weldon Spring Ordnance Works. Surface water, soil, sludge, sediment, and groundwater within the chemical plant site contain chemical and radioactive contaminants. The Agency for Toxic Substances and Disease Registry (ATSDR) reviewed on-site chemical exposure information and site conditions. ATSDR also prepared several Health Consultations on chemical and radioactive contaminants in areas on and off the DOE chemical plant site. ATSDR also reviewed on-site and off-site radiological exposure informationmore » and conditions. The exposure scenarios ATSDR evaluated include: trespassers swimming in quarry or raffinate pits; reservists performing field activities in the training area; anglers fishing, hunters haunting, and hikers hiking in the conservation areas; residents drinking from off-site private wells; staff and students attending the Francis Howell High School; and consumers of crops (e.g., corn) grown in conservation areas.« less

Dutch guideline for clinical foetal-neonatal and paediatric post-mortem radiology, including a review of literature.

PubMed

Sonnemans, L J P; Vester, M E M; Kolsteren, E E M; Erwich, J J H M; Nikkels, P G J; Kint, P A M; van Rijn, R R; Klein, W M

2018-06-01

Clinical post-mortem radiology is a relatively new field of expertise and not common practice in most hospitals yet. With the declining numbers of autopsies and increasing demand for quality control of clinical care, post-mortem radiology can offer a solution, or at least be complementary. A working group consisting of radiologists, pathologists and other clinical medical specialists reviewed and evaluated the literature on the diagnostic value of post-mortem conventional radiography (CR), ultrasonography, computed tomography (PMCT), magnetic resonance imaging (PMMRI), and minimally invasive autopsy (MIA). Evidence tables were built and subsequently a Dutch national evidence-based guideline for post-mortem radiology was developed. We present this evaluation of the radiological modalities in a clinical post-mortem setting, including MIA, as well as the recently published Dutch guidelines for post-mortem radiology in foetuses, neonates, and children. In general, for post-mortem radiology modalities, PMMRI is the modality of choice in foetuses, neonates, and infants, whereas PMCT is advised in older children. There is a limited role for post-mortem CR and ultrasonography. In most cases, conventional autopsy will remain the diagnostic method of choice. Based on a literature review and clinical expertise, an evidence-based guideline was developed for post-mortem radiology of foetal, neonatal, and paediatric patients. What is Known: • Post-mortem investigations serve as a quality check for the provided health care and are important for reliable epidemiological registration. • Post-mortem radiology, sometimes combined with minimally invasive techniques, is considered as an adjunct or alternative to autopsy. What is New: • We present the Dutch guidelines for post-mortem radiology in foetuses, neonates and children. • Autopsy remains the reference standard, however minimal invasive autopsy with a skeletal survey, post-mortem computed tomography, or post-mortem magnetic resonance imaging can be complementary thereof.

The Evolution of the Federal Monitoring and Assessment Center

DOE Office of Scientific and Technical Information (OSTI.GOV)

NSTec Aerial Measurement System

2012-07-31

The Federal Radiological Monitoring and Assessment Center (FRMAC) is a federal emergency response asset whose assistance may be requested by the Department of Homeland Security (DHS), the Department of Defense (DoD), the Environmental Protection Agency (EPA), the Nuclear Regulatory Commission (NRC), and state and local agencies to respond to a nuclear or radiological incident. It is an interagency organization with representation from the Department of Energy’s National Nuclear Security Administration (DOE/NNSA), the Department of Defense (DoD), the Environmental Protection Agency (EPA), the Department of Health and Human Services (HHS), the Federal Bureau of Investigation (FBI), and other federal agencies. FRMAC,more » in its present form, was created in 1987 when the radiological support mission was assigned to the DOE’s Nevada Operations Office by DOE Headquarters. The FRMAC asset, including its predecessor entities, was created, grew, and evolved to function as a response to radiological incidents. Radiological emergency response exercises showed the need for a coordinated approach to managing federal emergency monitoring and assessment activities. The mission of FRMAC is to coordinate and manage all federal radiological environmental monitoring and assessment activities during a nuclear or radiological incident within the United States in support of state,local, tribal governments, DHS, and the federal coordinating agency. Radiological emergency response professionals with the DOE’s national laboratories support the Radiological Assistance Program (RAP), National Atmospheric Release Advisory Center (NARAC), the Aerial MeasuringSystem (AMS), and the Radiation Emergency Assistance Center/Training Site (REAC/TS). These teams support the FRMAC to provide: Atmospheric transport modeling; Radiation monitoring; Radiological analysis and data assessments; and Medical advice for radiation injuries In support of field operations, the FRMAC provides geographic information systems, communications, mechanical, electrical, logistics, and administrative support. The size of the FRMAC is tailored to the incident and is comprised of emergency response professionals drawn from across the federal government. State and local emergency response teams may also integrate their operations with FRMAC, but are not required to.« less

Assessing the Gap in Female Authorship in Radiology: Trends Over the Past Two Decades.

PubMed

Liang, Teresa; Zhang, Cathy; Khara, Rohan M; Harris, Alison C

2015-07-01

The aim of this study was to retrospectively identify trends in the representation of female authorship in prominent general radiology journals over the past 2 decades. A comprehensive search was conducted for all articles published in 1993, 2003, and 2013 in Radiology, the American Journal of Roentgenology (AJR), European Radiology, and Investigative Radiology. The genders of the first and last authors were collected. Chi-square tests were used for statistical analysis, and P values < .05 were considered to indicate statistical significance. A total of 3,786 articles were reviewed. Overall, women constituted 20.0% authorship, 24.7% of first authors, and 15.2% of senior authors. The average overall female first and senior authorship grew from 19.7% to 32.1% and from 13.6% to 19.1%, respectively from 1993 to 2013. Female first authorship grew over the past 2 decades in the journals reviewed, with significant growth in AJR and Radiology (P < .0001). Female first authorship in the individual journals grew from 16.4%-29.1% in 1993, to 29.1%-34.8% in 2013. Female senior authorship also demonstrated growth in the past 2 decades, growing from 4.3%-17.5% in 1993 to 15.5%-23.2% in 2013. There was significant growth in senior female authorship in Radiology (from 12.1% to 19.2%, P = .004) and European Radiology (from 4.3% to 15.5%, P = .0433). Female senior authorship remained significantly lower than first authorship over the past 2 decades (P = .002, P < .001, and P < .0001). Although women's growth in first authorship in radiology literature is proportional to their growth in the specialty, they continue to remain a minority, especially in senior authorship, and demonstrate similar participation to other medical specialties. Copyright © 2015 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Directional phytoscreening: contaminant gradients in trees for plume delineation.

PubMed

Limmer, Matt A; Shetty, Mikhil K; Markus, Samantha; Kroeker, Ryan; Parker, Beth L; Martinez, Camilo; Burken, Joel G

2013-08-20

Tree sampling methods have been used in phytoscreening applications to delineate contaminated soil and groundwater, augmenting traditional investigative methods that are time-consuming, resource-intensive, invasive, and costly. In the past decade, contaminant concentrations in tree tissues have been shown to reflect the extent and intensity of subsurface contamination. This paper investigates a new phytoscreening tool: directional tree coring, a concept originating from field data that indicated azimuthal concentrations in tree trunks reflected the concentration gradients in the groundwater around the tree. To experimentally test this hypothesis, large diameter trees were subjected to subsurface contaminant concentration gradients in a greenhouse study. These trees were then analyzed for azimuthal concentration gradients in aboveground tree tissues, revealing contaminant centroids located on the side of the tree nearest the most contaminated groundwater. Tree coring at three field sites revealed sufficiently steep contaminant gradients in trees reflected nearby groundwater contaminant gradients. In practice, trees possessing steep contaminant gradients are indicators of steep subsurface contaminant gradients, providing compass-like information about the contaminant gradient, pointing investigators toward higher concentration regions of the plume.

Coping in a calamity: Radiology during the cloudburst at Leh

PubMed Central

Sen, Debraj

2013-01-01

The service hospital at Leh is a multispeciality hospital situated at an altitude of 11000 feet above mean sea level. On the nights of 4 and 5 Aug 2010, Leh was struck by a cloudburst leading to mudslides and consequently extensive damage to life and property. Being the only functional hospital, over a period of about 48 hours, 331 casualties were received. 549 casualties were received over the week with 108 admissions, 16 major surgeries and 138 minor surgeries. 178 radiographs, 17 CT scans and 09 ultrasound-colour Doppler examinations were performed on an urgent basis over 48 hours apart from the routine radiological investigations. Apart from chronicling the event, we hope that sharing the unique experience of the Radiology Department in dealing with the large influx of patients would provide an insight into the role of Radiology during the disaster and help in planning and developing management protocols during other calamities. PMID:23986626

Executive summary: Weldon Spring Site Environmental Report for calendar year 1992. Weldon Spring Site Remedial Action Project, Weldon Spring, Missouri

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1993-06-01

This report has been prepared to provide information about the public safety and environmental protection programs conducted by the Weldon Spring Site Remedial Action Project. The Weldon Spring site is located in southern St. Charles County, Missouri, approximately 48 km (30 mi) west of St. Louis. The site consists of two main areas, the Weldon Spring Chemical Plant and raffinate pits and the Weldon Spring Quarry. The objectives of the Site Environmental Report are to present a summary of data from the environmental monitoring program, to characterize trends and environmental conditions at the site, and to confirm compliance with environmentalmore » and health protection standards and requirements. The report also presents the status of remedial activities and the results of monitoring these activities to assess their impacts on the public and environment. The scope of the environmental monitoring program at the Weldon Spring site has changed since it was initiated. Previously, the program focused on investigations of the extent and level of contaminants in the groundwater, surface waters, buildings, and air at the site. In 1992, the level of remedial activities required monitoring for potential impacts of those activities, particularly on surface water runoff and airborne effluents. This report includes monitoring data from routine radiological and nonradiological sampling activities. These data include estimates of dose to the public from the Weldon Spring site; estimates of effluent releases; and trends in groundwater contaminant levels. Also, applicable compliance requirements, quality assurance programs, and special studies conducted in 1992 to support environmental protection programs are reviewed.« less

An Assessment of Air As a Source of DNA Contamination Encountered When Performing PCR

PubMed Central

Witt, Nina; Rodger, Gillian; Vandesompele, Jo; Benes, Vladimir; Zumla, Alimuddin; Rook, Graham A.; Huggett, Jim F.

2009-01-01

Sensitive molecular methods, such as the PCR, can detect low-level contamination, and careful technique is required to reduce the impact of contaminants. Yet, some assays that are designed to detect high copy-number target sequences appear to be impossible to perform without contamination, and frequently, personnel or laboratory environment are held responsible as the source. This complicates diagnostic and research analysis when using molecular methods. To investigate the air specifically as a source of contamination, which might occur during PCR setup, we exposed tubes of water to the air of a laboratory and clean hood for up to 24 h. To increase the chances of contamination, we also investigated a busy open-plan office in the same way. All of the experiments showed the presence of human and rodent DNA contamination. However, there was no accumulation of the contamination in any of the environments investigated, suggesting that the air was not the source of contamination. Even the air from a busy open-plan office was a poor source of contamination for all of the DNA sequences investigated (human, bacterial, fungal, and rodent). This demonstrates that the personnel and immediate laboratory environment are not necessarily to blame for the observed contamination. PMID:19949694

Remedial Investigation Report Area of Contamination (AOC) 43G. Volume 1

DTIC Science & Technology

1996-02-01

FORT DEVENS FINAL REMEDIAL INVESTIGATION FOR GROUP 2 & 7 SITES FINAL REMEDIAL INVESTIGATION REPORT AREA OF CONTAMINATION ( AOC ) 43G VOLUME I OF II...Liability Act for environmental investigations and remedial actions at Fort Devens . The agreement required that Site Investigations be undertaken at each... Remedial Investigation (RI) Report on Area of Contamination ( AOC ) 43G at the Fort Devens U.S. Army Installation, Massachusetts (

78 FR 55694 - Draft Research Report: Investigation of Ground Water Contamination Near Pavillion, Wyoming

Federal Register 2010, 2011, 2012, 2013, 2014

2013-09-11

... Research Report: Investigation of Ground Water Contamination Near Pavillion, Wyoming AGENCY: Environmental... draft research report titled, ``Investigation of Ground Water Contamination near Pavillion, Wyoming.'' The draft research report was prepared by the National Risk Management Research Laboratory, within the...

Neurofilament light chain and oligoclonal bands are prognostic biomarkers in radiologically isolated syndrome.

PubMed

Matute-Blanch, Clara; Villar, Luisa M; Álvarez-Cermeño, José C; Rejdak, Konrad; Evdoshenko, Evgeniy; Makshakov, Gleb; Nazarov, Vladimir; Lapin, Sergey; Midaglia, Luciana; Vidal-Jordana, Angela; Drulovic, Jelena; García-Merino, Antonio; Sánchez-López, Antonio J; Havrdova, Eva; Saiz, Albert; Llufriu, Sara; Alvarez-Lafuente, Roberto; Schroeder, Ina; Zettl, Uwe K; Galimberti, Daniela; Ramió-Torrentà, Lluís; Robles, René; Quintana, Ester; Hegen, Harald; Deisenhammer, Florian; Río, Jordi; Tintoré, Mar; Sánchez, Alex; Montalban, Xavier; Comabella, Manuel

2018-04-01

The prognostic role of cerebrospinal fluid molecular biomarkers determined in early pathogenic stages of multiple sclerosis has yet to be defined. In the present study, we aimed to investigate the prognostic value of chitinase 3 like 1 (CHI3L1), neurofilament light chain, and oligoclonal bands for conversion to clinically isolated syndrome and to multiple sclerosis in 75 patients with radiologically isolated syndrome. Cerebrospinal fluid levels of CHI3L1 and neurofilament light chain were measured by enzyme-linked immunosorbent assay. Uni- and multivariable Cox regression models including as covariates age at diagnosis of radiologically isolated syndrome, number of brain lesions, sex and treatment were used to investigate associations between cerebrospinal fluid CHI3L1 and neurofilament light chain levels and time to conversion to clinically isolated syndrome and multiple sclerosis. Neurofilament light chain levels and oligoclonal bands were independent risk factors for the development of clinically isolated syndrome (hazard ratio = 1.02, P = 0.019, and hazard ratio = 14.7, P = 0.012, respectively) and multiple sclerosis (hazard ratio = 1.03, P = 0.003, and hazard ratio = 8.9, P = 0.046, respectively). The best cut-off to classify cerebrospinal fluid neurofilament light chain levels into high and low was 619 ng/l, and high neurofilament light chain levels were associated with a trend to shorter time to clinically isolated syndrome (P = 0.079) and significant shorter time to multiple sclerosis (P = 0.017). Similarly, patients with radiologically isolated syndrome presenting positive oligoclonal bands converted faster to clinically isolated syndrome and multiple sclerosis (P = 0.005 and P = 0.008, respectively). The effects of high neurofilament light chain levels shortening time to clinically isolated syndrome and multiple sclerosis were more pronounced in radiologically isolated syndrome patients with ≥37 years compared to younger patients. Cerebrospinal fluid CHI3L1 levels did not influence conversion to clinically isolated syndrome and multiple sclerosis in radiologically isolated syndrome patients. Overall, these findings suggest that cerebrospinal neurofilament light chain levels and oligoclonal bands are independent predictors of clinical conversion in patients with radiologically isolated syndrome. The association with a faster development of multiple sclerosis reinforces the importance of cerebrospinal fluid analysis in patients with radiologically isolated syndrome.

Water contamination in fallout areas. Project No. 7806

DOE Office of Scientific and Technical Information (OSTI.GOV)

Robeck, G.G.; Woodward, R.L.; Muschler, W.K.

1958-05-01

An evaluation of the potential radiological hazard to Air Force personnel from drinking water contaminated with fission products is presented. Ground water supplies should be safe from fallout contamination and only surface supplies may need special treatment. Even in untreated water, the radioactivity in surface supplies is not likely to reduce significantly the military effectiveness of personnel using it except where the general level of contamination is greater than 1000 r/hr at H + 1. Dust samples were collected at the Priscilla shot of Operation Plumbbob 24 June 1957. In each of the samples, material containing approximately 10% of themore » activity was soluble; however, strontium was preferentially dissolved by a factor of 5. For the first 10 days after fallout, a supply of one gallon of water per person per day will suffice for drinking and culinary purposes. Ion-exchange, which is over 99% efficient, is the most practical and economical method of supplying decontaminated water. For immediate demand, small mixed-bed demineralizers, which are easily installed and maintained, are recommended; for long term demand, pressure cation-exchange beds operated on the sodium cycle are recommended. A shelter accommodating 100 people would require a small mixed-bed demineralizer with an initial cost of $81 and an operating cost of $9 per day. A pressure cation-exchange bed could be installed for $7,500 which would have an operating cost of 15 cents per 1,000 gallons. This could supply an average daily water requirement of 50,000 gallons.« less

WATER CONTAMINATION IN FALLOUT AREAS

DOE Office of Scientific and Technical Information (OSTI.GOV)

Robeck, G.G.; Woodward, R.L.; Muschler, W.K.

1958-05-01

An evaluation of the potential radiological hazard to Air Force personnel from drinking water contaminated with fission products is presented. Ground water supplies should be safe from fall-out contamination and only surface supplies may need special treatment. Even in untreated water, the radioactivity in surface supplies is not likely to reduce significantly the military effectiveness of personnel using it except where the general level of contamination is greater than 1000 r/hr at H + 1. Dust samples were collected at the Priscilla shot of Operation Plumbbob 24 June 1957. In each of the samples, material containing approximately 10% of themore » activity was soluble; however, strontium was preferentially dissolved by a factor of 5. For the first 10 days after fall-out, a supply of one gallon of water per person per day will suffice for drinking and culinary purposes, Ion-exchange, which is over 99% efficient, is the most practical and economical method of supplying decontaminated water, For immediate demand, small mixed-bed demineralizers, which are easily installed and maintained, are recommended; for long term demand, pressure cation-exchange beds operated on the sodium cycle are recommended. A shelter accommodating 100 people would require a small mixed-bed demineralizer with an initial cost of and an operating cost of per day. A pressure cation-exchange bed could be installed for 500 which would have an operating cost of 15 cents per 1,000 gallons. This could supply an average daily water requirement of 50,000 gallons. (auth)« less

Sciatica-like symptoms and the sacroiliac joint: clinical features and differential diagnosis.

PubMed

Visser, L H; Nijssen, P G N; Tijssen, C C; van Middendorp, J J; Schieving, J

2013-07-01

To compare the clinical features of patients with sacroiliac joint (SIJ)-related sciatica-like symptoms to those with sciatica from nerve root compression and to investigate the necessity to perform radiological imaging in patients with sciatica-like symptoms derived from the SIJ. Patients with pain radiating below the buttocks with a duration of 4 weeks to 1 year were included. After physical and radiological examinations, a diagnosis of SI joint-related pain, pain due to disk herniation, or a combination of these two causes was made. Patients with SIJ-related leg pain (n = 77/186) were significantly more often female, had shorter statue, a shorter duration of symptoms, and had more often pain radiating to the groin and a history of a fall on the buttocks. Muscle weakness, corkscrew phenomenon, finger-floor distance ≥25 cm, lumbar scoliosis, positive Bragard or Kemp sign, and positive leg raising test were more often present when radiologic nerve root compression was present. Although these investigations may help, MRI of the spine is necessary to discriminate between the groups. Sciatica-like symptoms derived from the SIJ can clinically mimic a radiculopathy. We suggest to perform a thorough physical examination of the spine, SI joints, and hips with additional radiological tests to exclude other causes.

Improvement of radiological penumbra using intermediate energy photons (IEP) for stereotactic radiosurgery.

PubMed

O'Malley, Lauren; Pignol, Jean-Philippe; Beachey, David J; Keller, Brian M; Presutti, Joseph; Sharpe, Michael

2006-05-21

Using efficient immobilization and dedicated beam collimation devices, stereotactic radiosurgery ensures highly conformal treatment of small tumours with limited microscopic extension. One contribution to normal tissue irradiation remains the radiological penumbra. This work aims at demonstrating that intermediate energy photons (IEP), above orthovoltage but below megavoltage, improve dose distribution for stereotactic radiosurgery for small irradiation field sizes due to a dramatic reduction of radiological penumbra. Two different simulation systems were used: (i) Monte Carlo simulation to investigate the dose distribution of monoenergetic IEP between 100 keV and 1 MeV in water phantom; (ii) the Pinnacle3 TPS including a virtual IEP unit to investigate the dosimetry benefit of treating with 11 non-coplanar beams a 2 cm tumour in the middle of a brain adjacent to a 1 mm critical structure. Radiological penumbrae below 300 microm are generated for field size below 2 x 2 cm2 using monoenergetic IEP beams between 200 and 400 keV. An 800 kV beam generated in a 0.5 mm tungsten target maximizes the photon intensity in this range. Pinnacle3 confirms the dramatic reduction in penumbra size. DVHs show for a constant dose distribution conformality, improved dose distribution homogeneity and better sparing of critical structures using a 800 kV beam compared to a 6 MV beam.

Improvement of radiological penumbra using intermediate energy photons (IEP) for stereotactic radiosurgery

NASA Astrophysics Data System (ADS)

O'Malley, Lauren; Pignol, Jean-Philippe; Beachey, David J.; Keller, Brian M.; Presutti, Joseph; Sharpe, Michael

2006-05-01

Using efficient immobilization and dedicated beam collimation devices, stereotactic radiosurgery ensures highly conformal treatment of small tumours with limited microscopic extension. One contribution to normal tissue irradiation remains the radiological penumbra. This work aims at demonstrating that intermediate energy photons (IEP), above orthovoltage but below megavoltage, improve dose distribution for stereotactic radiosurgery for small irradiation field sizes due to a dramatic reduction of radiological penumbra. Two different simulation systems were used: (i) Monte Carlo simulation to investigate the dose distribution of monoenergetic IEP between 100 keV and 1 MeV in water phantom; (ii) the Pinnacle3 TPS including a virtual IEP unit to investigate the dosimetry benefit of treating with 11 non-coplanar beams a 2 cm tumour in the middle of a brain adjacent to a 1 mm critical structure. Radiological penumbrae below 300 µm are generated for field size below 2 × 2 cm2 using monoenergetic IEP beams between 200 and 400 keV. An 800 kV beam generated in a 0.5 mm tungsten target maximizes the photon intensity in this range. Pinnacle3 confirms the dramatic reduction in penumbra size. DVHs show for a constant dose distribution conformality, improved dose distribution homogeneity and better sparing of critical structures using a 800 kV beam compared to a 6 MV beam.

Surface radiological investigations at two creek receiving runoff from White Wing Scrap Yard, Oak Ridge Reservation, Oak Ridge, Tennessee. Environmental Restoration Program

DOE Office of Scientific and Technical Information (OSTI.GOV)

Uziel, M.S.; Tiner, P.F.; Williams, J.K.

1994-02-01

A surface radiological investigation was conducted intermittently from August 1992 July 1993 at two creeks receiving runoff from White Wing Scrap Yard. In this report, the two creeks (both unnamed tributaries of Bear Creek) are, referred to as the east creek and the west creek based on their respective locations relative to White Wing Scrap Yard. The radiological survey of accessible areas at the east creek revealed no detectable gamma exposure rates above typical background levels (8 to 12 {mu}R/h). The very slight elevations in gamma and beta-gamma levels found along the creek were generally associated with outcroppings of shalemore » and typical of naturally occurring radionuclides present in such material. No radiological anomalies were associated with an oily sheen observed on the water at three locations, three 55-gal metal drums in or near the creek, a small pile of metal debris near the creek, or several enclosures used in a 1969 study of animal excretion rates. Radionuclide analysis of three soil samples collected at the east creek demonstrated typical of {sup 60}Co, {sup 137}Cs, gross alpha activity, gross beta activity, and {sup 40}K.« less

Manual therapy in osteoarthritis of the hip: outcome in subgroups of patients.

PubMed

Hoeksma, H L; Dekker, J; Ronday, H K; Breedveld, F C; Van den Ende, C H M

2005-04-01

To investigate whether manual therapy has particular benefit in subgroups of patients defined on the basis of hip function, range of joint motion, pain and radiological deterioration. The study was performed in the out-patient clinic of physical therapy of a large hospital. Data on 109 patients with OA of the hip (clinical ACR criteria) participating in a randomized clinical trial on the effects of manual therapy were used. The outcomes for hip function (Harris hip score), range of joint motion (ROM) and pain (VAS) were compared for specific subgroups. Subgroups were assigned by the median split method. The interaction effect between subgroup and treatment was tested using multiple regression analysis. No differences were observed in the effect of manual therapy in specific subgroups of patients defined on the basis of baseline levels of hip function, pain and ROM. On the basis of radiological grading of osteoarthritis (OA), we found that patients with severe radiological grading of OA had significantly worse outcome on ROM as a result of manual therapy than patients with mild or moderate radiological grading of OA. A significant interaction effect was found for only 1 out of 12 hypotheses investigated. Therefore, we conclude that there is no evidence for the particular benefit of manual therapy in subgroups of patients.

[Severe lower gastrointestinal bleeding due to GIST tumor. Radiological embolization and surgery].

PubMed

Navas, Diana; Ríos, Antonio; Febrero, Beatriz; Rodríguez, José Manuel; Lloret, Francisco; Parrilla, Pascual

2014-01-01

Gastrointestinal stromal tumors (GIST) were identified only recently. These tumors usually have no symptoms, although they are localized, operable and curable. Although rare, if they are not diagnosed and treated early, they become very aggressive. The most common manifestation is gastrointestinal bleeding from mucosal erosion. Their presentation as severe lower gastrointestinal bleeding is exceptional. We report a patient with severe lower gastrointestinal bleeding stabilized by interventional radiology that subsequently required surgery for definitive care. Therapeutic use of radiological embolization is increasingly widespread in bleeding at various levels, achieving hemodynamic stabilization of patients. However, it must be kept in mind that, in cases of unknown etiology of lower gastrointestinal bleeding, possible causes must be investigated.

Radiological Risk Assessment for King County Wastewater Treatment Division

DOE Office of Scientific and Technical Information (OSTI.GOV)

Strom, Daniel J.

Staff of the King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into the combined sanitary and storm sewer system in King County, Washington. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include "dirty bombs" that are not nuclear detonations but are explosives designed to spread radioactive material (National Council on Radiation Protection and Measurements (NCRP) 2001). Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways andmore » water supply systems. This document develops plausible and/or likely scenarios, including the identification of likely radioactive materials and quantities of those radioactive materials to be involved. These include 60Co, 90Sr, 137Cs, 192Ir, 226Ra, plutonium, and 241Am. Two broad categories of scenarios are considered. The first category includes events that may be suspected from the outset, such as an explosion of a "dirty bomb" in downtown Seattle. The explosion would most likely be heard, but the type of explosion (e.g., sewer methane gas or RDD) may not be immediately known. Emergency first responders must be able to quickly detect the radioisotopes previously listed, assess the situation, and deploy a response to contain and mitigate (if possible) detrimental effects resulting from the incident. In such scenarios, advance notice of about an hour or two might be available before any contaminated wastewater reaches a treatment plant. The second category includes events that could go initially undetected by emergency personnel. Examples of such a scenario would be the inadvertent or surreptitious introduction of radioactive material into the sewer system. Intact rogue radioactive sources from industrial radiography devices, well-logging apparatus, or moisture density gages may get into wastewater and be carried to a treatment plant. Other scenarios might include a terrorist deliberately putting a dispersible radioactive material into wastewater. Alternatively, a botched terrorism preparation of an RDD may result in radioactive material entering wastewater without anyone's knowledge. Drinking water supplies may also be contaminated, with the result that some or most of the radioactivity ends up in wastewater.« less

Response of the REWARD detection system to the presence of a Radiological Dispersal Device

DOE Office of Scientific and Technical Information (OSTI.GOV)

Luis, R.; Baptista, M.; Barros, S.

2015-07-01

In recent years an increased international concern has emerged about the radiological and nuclear (RN) threats associated with the illicit trafficking of nuclear and radioactive materials that could be potentially used for terrorist attacks. The objective of the REWARD (Real Time Wide Area Radiation Surveillance System) project, co-funded by the European Union 7. Framework Programme Security, consisted in building a mobile system for real time, wide area radiation surveillance, using a CdZnTe detector for gamma radiation and a neutron detector based on novel silicon technologies. The sensing unit includes a GPS system and a wireless communication interface to send themore » data remotely to a monitoring base station, where it will be analyzed in real time and correlated with historical data from the tag location, in order to generate an alarm when an abnormal situation is detected. Due to its portability and accuracy, the system will be extremely useful in many different scenarios such as nuclear terrorism, lost radioactive sources, radioactive contamination or nuclear accidents. This paper shortly introduces the REWARD detection system, depicts some terrorist threat scenarios involving radioactive sources and special nuclear materials and summarizes the simulation work undertaken during the past three years in the framework of the REWARD project. The main objective consisted in making predictions regarding the behavior of the REWARD system in the presence of a Radiological Dispersion Device (RDD), one of the reference scenarios foreseen for REWARD, using the Monte Carlo simulation program MCNP6. The reference scenario is characterized in detail, from the i) radiological protection, ii) radiation detection requirements and iii) communications points of view. Experimental tests were performed at the Fire Brigades Facilities in Rome and at the Naples Fire Brigades, and the results, which validate the simulation work, are presented and analyzed. The response of the REWARD detection system to the presence of an RDD is predicted and discussed. (authors)« less

WASTE TREATMENT BUILDING SYSTEM DESCRIPTION DOCUMENT

DOE Office of Scientific and Technical Information (OSTI.GOV)

F. Habashi

2000-06-22

The Waste Treatment Building System provides the space, layout, structures, and embedded subsystems that support the processing of low-level liquid and solid radioactive waste generated within the Monitored Geologic Repository (MGR). The activities conducted in the Waste Treatment Building include sorting, volume reduction, and packaging of dry waste, and collecting, processing, solidification, and packaging of liquid waste. The Waste Treatment Building System is located on the surface within the protected area of the MGR. The Waste Treatment Building System helps maintain a suitable environment for the waste processing and protects the systems within the Waste Treatment Building (WTB) from mostmore » of the natural and induced environments. The WTB also confines contaminants and provides radiological protection to personnel. In addition to the waste processing operations, the Waste Treatment Building System provides space and layout for staging of packaged waste for shipment, industrial and radiological safety systems, control and monitoring of operations, safeguards and security systems, and fire protection, ventilation and utilities systems. The Waste Treatment Building System also provides the required space and layout for maintenance activities, tool storage, and administrative facilities. The Waste Treatment Building System integrates waste processing systems within its protective structure to support the throughput rates established for the MGR. The Waste Treatment Building System also provides shielding, layout, and other design features to help limit personnel radiation exposures to levels which are as low as is reasonably achievable (ALARA). The Waste Treatment Building System interfaces with the Site Generated Radiological Waste Handling System, and with other MGR systems that support the waste processing operations. The Waste Treatment Building System interfaces with the General Site Transportation System, Site Communications System, Site Water System, MGR Site Layout, Safeguards and Security System, Site Radiological Monitoring System, Site Electrical Power System, Site Compressed Air System, and Waste Treatment Building Ventilation System.« less

Contaminant deposition building shielding factors for US residential structures.

PubMed

Dickson, Elijah; Hamby, David; Eckerman, Keith

2017-10-10

This paper presents validated building shielding factors designed for contemporary US housing-stock under an idealized, yet realistic, exposure scenario from contaminant deposition on the roof and surrounding surfaces. The building shielding factors are intended for use in emergency planning and level three probabilistic risk assessments for a variety of postulated radiological events in which a realistic assessment is necessary to better understand the potential risks for accident mitigation and emergency response planning. Factors are calculated from detailed computational housing-units models using the general-purpose Monte Carlo N-Particle computational code, MCNP5, and are benchmarked from a series of narrow- and broad-beam measurements analyzing the shielding effectiveness of ten common general-purpose construction materials and ten shielding models representing the primary weather barriers (walls and roofs) of likely US housing-stock. Each model was designed to scale based on common residential construction practices and include, to the extent practical, all structurally significant components important for shielding against ionizing radiation. Calculations were performed for floor-specific locations from contaminant deposition on the roof and surrounding ground as well as for computing a weighted-average representative building shielding factor for single- and multi-story detached homes, both with and without basement as well for single-wide manufactured housing-unit. © 2017 IOP Publishing Ltd.

Contaminant deposition building shielding factors for US residential structures.

PubMed

Dickson, E D; Hamby, D M; Eckerman, K F

2015-06-01

This paper presents validated building shielding factors designed for contemporary US housing-stock under an idealized, yet realistic, exposure scenario from contaminant deposition on the roof and surrounding surfaces. The building shielding factors are intended for use in emergency planning and level three probabilistic risk assessments for a variety of postulated radiological events in which a realistic assessment is necessary to better understand the potential risks for accident mitigation and emergency response planning. Factors are calculated from detailed computational housing-units models using the general-purpose Monte Carlo N-Particle computational code, MCNP5, and are benchmarked from a series of narrow- and broad-beam measurements analyzing the shielding effectiveness of ten common general-purpose construction materials and ten shielding models representing the primary weather barriers (walls and roofs) of likely US housing-stock. Each model was designed to scale based on common residential construction practices and include, to the extent practical, all structurally significant components important for shielding against ionizing radiation. Calculations were performed for floor-specific locations from contaminant deposition on the roof and surrounding ground as well as for computing a weighted-average representative building shielding factor for single- and multi-story detached homes, both with and without basement as well for single-wide manufactured housing-unit.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Faillace, E.R.; Cheng, J.J.; Yu, C.

A series of benchmarking runs were conducted so that results obtained with the RESRAD code could be compared against those obtained with six pathway analysis models used to determine the radiation dose to an individual living on a radiologically contaminated site. The RESRAD computer code was benchmarked against five other computer codes - GENII-S, GENII, DECOM, PRESTO-EPA-CPG, and PATHRAE-EPA - and the uncodified methodology presented in the NUREG/CR-5512 report. Estimated doses for the external gamma pathway; the dust inhalation pathway; and the soil, food, and water ingestion pathways were calculated for each methodology by matching, to the extent possible, inputmore » parameters such as occupancy, shielding, and consumption factors.« less

C-14/I-29 Preservation and Hold Time Survey

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kitchen, S.

2015-04-08

Preservation and hold time of radionuclides must account for both nuclear half-lives and nonnuclear loss mechanisms, but variations in the latter are often neglected. Metals-based defaults are inappropriate for long-lived non-metals C-14 and I-129, which are vulnerable to chemical and biological volatilization. Non-acidification is already widely practiced for them. Recommended addition measures from radiological and chemical literature include glass containers where possible, water filtration where possible, headspace minimization, light shielding, cold (4°C) storage and unfiltered water hold time of 28 days. Soil hold time may need to be shortened when water-logged, excessively sandy, or still adjusting to significant new contamination.

[Assessment and control of health risk caused by the radiological accident at the TEPCO Fukushima Daiichi nuclear power plant].

PubMed

Matsuda, Naoki; Morita, Naoko; Miura, Miwa

2014-01-01

The accident at the Tokyo Electric Power Company (TEPCO) Fukushima Daiichi nuclear power plant on March 11, 2011, released a large amount of radioactive materials resulting in the radioactive contamination of a wide area of eastern Japan. Residents of the Fukushima prefecture experienced various unavoidable damages and fear of radiation effects on their health. A reliable communication of accurate risk assessment for residents is required as a countermeasure aimed at the reconstruction of Fukushima. Here, the current status of individual dose estimation and the issues relating to the radiation risk perception are discussed.

Virtual anthropology: useful radiological tools for age assessment in clinical forensic medicine and thanatology.

PubMed

Dedouit, Fabrice; Saint-Martin, Pauline; Mokrane, Fatima-Zohra; Savall, Frédéric; Rousseau, Hervé; Crubézy, Eric; Rougé, Daniel; Telmon, Norbert

2015-09-01

Virtual anthropology consists of the introduction of modern slice imaging to biological and forensic anthropology. Thanks to this non-invasive scientific revolution, some classifications and staging systems, first based on dry bone analysis, can be applied to cadavers with no need for specific preparation, as well as to living persons. Estimation of bone and dental age is one of the possibilities offered by radiology. Biological age can be estimated in clinical forensic medicine as well as in living persons. Virtual anthropology may also help the forensic pathologist to estimate a deceased person's age at death, which together with sex, geographical origin and stature, is one of the important features determining a biological profile used in reconstructive identification. For this forensic purpose, the radiological tools used are multislice computed tomography and, more recently, X-ray free imaging techniques such as magnetic resonance imaging and ultrasound investigations. We present and discuss the value of these investigations for age estimation in anthropology.

Machinery-related deaths: relevance of workplace investigation and antemortem radiological data in reconstructing the fatality.

PubMed

Cecchetto, Giovanni; Viel, Guido; De Lotto, Federica; Manara, Renzo; Montisci, Massimo; Zancaner, Silvano; Ferrara, S Davide

2010-05-01

Machinery-related fatalities are one of the leading causes of traumatic occupational deaths. In our report, we present the case of a 40-year-old male who suffered a severe head trauma while working in a cut-foam industry and died despite an early craniectomy. The radiological reconstruction of the skull based on preoperative computed tomography scans disclosed a large depressed conical fracture of the left parietal bone. The 3D-reconstruction of the work area, combined with a fit-matching analysis between the machinery and the depressed skull fracture allowed us to conclude that the head was crushed between the sliding bar of the cutting device and the metallic protuberance on the opposite side. The case underlines the importance of a detailed workplace investigation and of a thorough evaluation of all circumstantial, clinical, radiological, and autopsy data in the reconstruction of machinery-related fatalities to identify any possible legal responsibilities of the worker and/or the employer.

77 FR 19012 - Draft Research Report: Investigation of Ground Water Contamination Near Pavillion, WY

Federal Register 2010, 2011, 2012, 2013, 2014

2012-03-29

..., ``Investigation of Ground Water Contamination near Pavillion, Wyoming.'' The draft research report was prepared by... ENVIRONMENTAL PROTECTION AGENCY [FRL-9654-3; Docket ID No. EPA-HQ-ORD-2011-0895] Draft Research Report: Investigation of Ground Water Contamination Near Pavillion, WY AGENCY: Environmental Protection...

77 FR 62234 - Draft Research Report: Investigation of Ground Water Contamination Near Pavillion, WY

Federal Register 2010, 2011, 2012, 2013, 2014

2012-10-12

..., ``Investigation of Ground Water Contamination near Pavillion, Wyoming.'' The draft research report was prepared by... ENVIRONMENTAL PROTECTION AGENCY [FRL-9741-5; Docket ID No. EPA-HQ-ORD-2011-0895] Draft Research Report: Investigation of Ground Water Contamination Near Pavillion, WY AGENCY: Environmental Protection...

78 FR 2396 - Draft Research Report: Investigation of Ground Water Contamination Near Pavillion, WY

Federal Register 2010, 2011, 2012, 2013, 2014

2013-01-11

..., ``Investigation of Ground Water Contamination near Pavillion, Wyoming.'' The draft research report was prepared by... ENVIRONMENTAL PROTECTION AGENCY [FRL-9769-5; Docket ID No. EPA-HQ-ORD-2011-0895] Draft Research Report: Investigation of Ground Water Contamination Near Pavillion, WY AGENCY: Environmental Protection...

Breast diseases in children: the spectrum of radiologic findings in a cohort study

PubMed Central

Durmaz, Emel; Öztek, Murat Alp; Habibi, Hatice Arıöz; Kesimal, Uğur; Sindel, Hakkı Timur

2017-01-01

PURPOSE We aimed to investigate the spectrum of radiologic findings and referral reasons for breast diseases in children considering age-appropriate presentation. METHODS Our retrospective cohort study included 348 consecutive pediatric patients aged <19 years (median, 13 years) referred to radiology with a clinical presentation between 2005 and 2016. Radiologic findings were reviewed in four age ranges (0–2 years, 2–8 years, 8–15 years, >15 years). RESULTS Of 348 patients, 257 had a referral reason. The most frequent referral reason was a palpable mass (35%). Developmental abnormalities accounted for 48% of all radiologic findings in 348 patients. We did not detect any breast malignancy. According to age groups, the most common radiologic findings were neonatal hypertrophy (0–2 years), early breast development (2–8 years), developmental abnormalities by a majority of gynecomastia (8–15 years), and normal findings or developmental abnormalities (>15 years). Interestingly, the frequency of gynecomastia was only 4% in neonatal period or early childhood. Fibroadenomas and fibroadenoma-like solid masses were seen after 8 years and constituted the majority of solid masses (65%). Cysts were seen at a rate of 7% and majority of them were of simple type, which tends to resolve in time. CONCLUSION In our study, the most common referral reason to radiology was a palpable breast mass. Neonatal hypertrophy and early breast development in younger children, and developmental abnormalities in older children may be kept in mind as the most common radiologic findings. Our study confirms the substantial absence of malignancies in children as well as a widely different disease spectrum in comparison with the adult population. PMID:29033391

Factors Influencing the Gender Breakdown of Academic Radiology Residency Programs.

PubMed

Campbell, James C; Yoon, Sora C; Cater, Sarah Wallace; Grimm, Lars J

2017-07-01

To determine the gender distribution of radiology residency programs and identify associations with radiology departmental factors. The residency programs affiliated with the top 50 research medical school from US News and World Report were identified. The gender of all radiology residency graduates from each program from 2011 to 2015 were collected. Radiology departmental factors were collected: gender of chairperson, gender of program director, gender of faculty, geographic location, and city population of the residency program. The median percentage of female radiology faculty and residents were calculated and classified as above or below the median. Comparisons were made between residency programs and departmental factors via a Pearson χ 2 univariate test or logistic regression. There were 618 (27.9%) female and 1,598 (72.1%) male residents in our study, with a median female representation of 26.4% in each program. Programs with a female residency program director were significantly more likely to have an above-median percentage of female residents versus a male program director (68.4% versus 38.7%, P = .04). Programs in the Northeast (70.6%) and West (70.0%) had higher above-median female representation than the South (10.0%) and Midwest (38.5%, P < .01). There was no association with city population size (P = .40), gender of faculty (P = .40), residency size (P = .91), or faculty size (P = .15). Radiology residency programs with a female residency program director and those in the Northeast or West have a greater concentration of female residents. Residency programs that aim to increase female representation should investigate modifiable factors that can improve their recruitment practices. Copyright © 2017 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Correlations between serum adipocytokine concentrations, disease stage, radiological status and total body fat content in the patients with primary knee osteoarthritis.

PubMed

Richter, Magdalena; Trzeciak, Tomasz; Rybka, Jakub Dalibor; Suchorska, Wiktoria; Augustyniak, Ewelina; Lach, Michał; Kaczmarek, Małgorzata; Kaczmarczyk, Jacek

2017-05-01

The study was designed to investigate whether serum concentrations of leptin, resistin and adiponectin in obese and normal-weight patients with primary knee osteoarthritis (OA) correlate with clinical and radiological stages of the disease and percentage of total body fat. Seventy-three patients with knee OA, divided into obese and normal-weight groups, were clinically evaluated according to the Knee Society Score (KSS), and radiologically assessed using Kellgren and Lawrence scale. The percentage of total body fat and some anthropometric data were also given. Serum leptin, resistin and adiponectin concentrations were measured by Elisa and were correlated with the clinical, radiological and anthropometric parameters. Leptin concentrations were significantly higher (p = 0.001) in the obese patients and positively correlated (R = 0.63) with radiologically assessed OA grade, but only in the normal-weight group. Resistin and adiponectin concentrations were identical in obese and normal-weight patients and negatively correlated (R = -0.41) with the clinical status of obese patients. In both groups, percentage of total body fat positively correlated (R = 0.29 and R = 0.53 for obese and normal-weight respectively) with radiologically assessed OA grade. However, no correlations were found with clinical status of the patients. It was found that in the obese patients with knee OA, increased percentage of total body fat and elevated serum leptin concentration might favour the advancement of clinical but not radiologically assessed changes in the joint structures, while in normal-weight patients it correlates only with radiologically assessed changes but does not affect to an appreciable extent the clinical status of the patients.

Citation Impact of Collaboration in Radiology Research.

PubMed

Rosenkrantz, Andrew B; Parikh, Ujas; Duszak, Richard

2018-02-01

Team science involving multidisciplinary and multi-institutional collaboration is increasingly recognized as a means of strengthening the quality of scientific research. The aim of this study was to assess associations between various forms of collaboration and the citation impact of published radiology research. In 2010, 876 original research articles published in Academic Radiology, the American Journal of Roentgenology, JACR, and Radiology were identified with at least one radiology-affiliated author. All articles were manually reviewed to extract features related to all authors' disciplines and institutions. Citations to these articles through September 2016 were extracted from Thomson Reuters Web of Science. Subsequent journal article citation counts were significantly higher (P < .05) for original research articles with at least seven versus six or fewer authors (26.2 ± 30.8 versus 20.3 ± 23.1, respectively), with authors from multiple countries versus from a single country (32.3 ± 39.2 versus 22.0 ± 25.0, respectively), with rather than without a nonuniversity collaborator (28.7 ± 38.6 versus 22.4 ± 24.9, respectively), and with rather than without a nonclinical collaborator (26.5 ± 33.1 versus 21.9 ± 24.4, respectively). On multivariate regression analysis, the strongest independent predictors of the number of citations were authors from multiple countries (β = 9.14, P = .002), a nonuniversity collaborator (β = 4.80, P = .082), and at least seven authors (β = 4.11, P = .038). With respect to subsequent journal article citations, various forms of collaboration are associated with greater scholarly impact of published radiology research. To enhance the relevance of their research, radiology investigators are encouraged to pursue collaboration across traditional disciplinary, institutional, and geographic boundaries. Copyright © 2017 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Influences of Radiology Trainees on Screening Mammography Interpretation.

PubMed

Hawley, Jeffrey R; Taylor, Clayton R; Cubbison, Alyssa M; Erdal, B Selnur; Yildiz, Vedat O; Carkaci, Selin

2016-05-01

Participation of radiology trainees in screening mammographic interpretation is a critical component of radiology residency and fellowship training. The aim of this study was to investigate and quantify the effects of trainee involvement on screening mammographic interpretation and diagnostic outcomes. Screening mammograms interpreted at an academic medical center by six dedicated breast imagers over a three-year period were identified, with cases interpreted by an attending radiologist alone or in conjunction with a trainee. Trainees included radiology residents, breast imaging fellows, and fellows from other radiology subspecialties during breast imaging rotations. Trainee participation, patient variables, results of diagnostic evaluations, and pathology were recorded. A total of 47,914 mammograms from 34,867 patients were included, with an overall recall rate for attending radiologists reading alone of 14.7% compared with 18.0% when involving a trainee (P < .0001). Overall cancer detection rate for attending radiologists reading alone was 5.7 per 1,000 compared with 5.2 per 1,000 when reading with a trainee (P = .517). When reading with a trainee, dense breasts represented a greater portion of recalls (P = .0001), and more frequently, greater than one abnormality was described in the breast (P = .013). Detection of ductal carcinoma in situ versus invasive carcinoma or invasive cancer type was not significantly different. The mean size of cancers in patients recalled by attending radiologists alone was smaller, and nodal involvement was less frequent, though not statistically significantly. These results demonstrate a significant overall increase in recall rate when interpreting screening mammograms with radiology trainees, with no change in cancer detection rate. Radiology faculty members should be aware of this potentiality and mitigate tendencies toward greater false positives. Copyright © 2016 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Patterns of Recent National Institutes of Health (NIH) Funding to Diagnostic Radiology Departments: Analysis Using the NIH RePORTER System.

PubMed

Franceschi, Ana M; Rosenkrantz, Andrew B

2017-09-01

This study aimed to characterize recent National Institutes of Health (NIH) funding for diagnostic radiology departments at US medical schools. This retrospective study did not use private identifiable information and thus did not constitute human subjects research. The public NIH Research Portfolio Online Reporting Tools Expenditure and Results system was used to extract information regarding 887 NIH awards in 2015 to departments of "Radiation-Diagnostic/Oncology." Internet searches were conducted to identify each primary investigator (PI)'s university web page, which was used to identify the PI's departmental affiliation, gender, degree, and academic rank. A total of 649 awards to diagnostic radiology departments, based on these web searches, were included; awards to radiation oncology departments were excluded. Characteristics were summarized descriptively. A total of 61 unique institutions received awards. The top five funded institutions represented 33.6% of all funding. The most common institutes administering these awards were the National Cancer Institute (29.0%) and the National Institute of Biomedical Imaging and Bioengineering (21.6%). Women received 15.9% of awards and 13.3% of funding, with average funding per award of $353,512 compared to $434,572 for men. PhDs received 77.7% of all awards, with average funding per award of $457,413 compared to $505,516 for MDs. Full professors received 51.2% of awards (average funding per award of $532,668), compared to assistant professors who received 18.4% of awards ($260,177). Average funding was $499,859 for multiple-PI awards vs. $397,932 for single-PI awards. Common spending categories included "neurosciences," "cancer," "prevention," and "aging." NIH funding for diagnostic radiology departments has largely been awarded to senior-ranking male PhD investigators, commonly at large major academic medical centers. Initiatives are warranted to address such disparities and promote greater diversity in NIH funding among diagnostic radiology investigators. Copyright © 2017 The Association of University Radiologists. Published by Elsevier Inc. All rights reserved.