HANDBOOK: APPROACHES FOR REMEDIATION OF FEDERAL FACILITY SITES CONTAMINATED WITH EXPLOSIVE OR RADIOACTIVE WASTE

EPA Science Inventory

This publication was developed by the Center for Environmental Research Information (CERI), Office of Research and Development, of the U.S. Environmental Protection Agency (EPA). The information in the document is based primarily on presentations at two technology transfer semina...

Potential Nano-Enabled Environmental Applications for Radionuclides

EPA Pesticide Factsheets

This document provides information about nanotechnology materials and processes that may be applicable when cleaning up radioactively contaminated sites or materials, and presents a snapshot of lessons learned in nano-science and engineering.

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

NONE

This monthly publication contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. NRC documents that are publicly available may be examined without charge atmore » the NRC Public Document Room (PDR).« less

Title list of documents made publicly available, June 1-30, 1997

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

NONE

This document is a monthly publication describing information received and published by the U.S. Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, {open_quotes}docketed{close_quotes} does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records.

Title list of documents made publicly available, January 1-31, 1998

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

NONE

1998-03-01

The Title List of Documents Made Publicly Available is a monthly publication. It describes the information received and published by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and amore » Report Number Index. The docketed information in the Title List includes the information formerly issued through the Department of Energy publication Power Reactor Docket Information, last published in January 1979. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR). Duplicate copies in paper, microfiche, or (selectively) diskette, may be obtained for a fee.« less

Title list of documents made publicly available July 1-31, 1997

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

NONE

This monthly publication describes the information received and published by the U.S. Nuclear Regulatory Commission (US NRC). This includes information on docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and non-docketed material published by the US NRC pertinent to it`s role as a regulatory agency.

Title list of documents made publicly available. Volume 17, No. 5

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

NONE

1995-07-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (3) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index,more » and a Report Number Index.« less

Title list of documents made publicly available, December 1--31, 1993, Volume 15, No. 12

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

NONE

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the U.S. Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index,more » and a Report Number Index.« less

Title list of documents made publicly available: May 1--31, 1997. Volume 19, Number 5

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

NONE

The Title List of Documents Made Publicly Available is a monthly publication. It describes the information received and published by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and amore » Report Number Index.« less

Title list of documents made publicly available, September 1-30, 1997

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

NONE

The Title List of Documents Made Publicly Available is a monthly publication. It describes the information received and published by the U.S. Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and amore » Report Number Index.« less

Title list of documents made publicly available. Volume 17, No. 7

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

NONE

1995-09-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index,more » and a Report Number Index.« less

Title list of documents made publicly available, March 1--31, 1998. Volume 20, Number 3

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

NONE

The Title List of Documents Made Publicly Available is a monthly publication. It describes the information received and published by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a personal author index, a corporate source index, and amore » report number index.« less

Title list of documents made publicly available, January 1, 1997--January 31, 1997

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

NONE

1997-04-01

The Title List of Documents Made Publicly Available is a monthly publication. It describes the information received and published by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and amore » Report Number Index.« less

Reactor operations informal monthly report, May 1, 1995--May 31, 1995

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

Hauptman, H.M.; Petro, J.N.; Jacobi, O.

1995-05-01

This document is an informal progress report for the operational performance of the Brookhaven Medical Research Reactor, and the Brookhaven High Flux Beam Reactor, for the month of May, 1995. Both machines ran well during this period, with no reportable instrumentation problems, all scheduled maintenance performed, and only one reportable occurance, involving a particle on Vest Button, Personnel Radioactive Contamination.

Selected radionuclides important to low-level radioactive waste management

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

NONE

1996-11-01

The purpose of this document is to provide information to state representatives and developers of low level radioactive waste (LLW) management facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the environment. Extensive surveys of available literature provided information for this report. Certain radionuclides may contribute significantly to the dose estimated during a radiological performance assessment analysis of an LLW disposal facility. Among these are the radionuclides listed in Title 10 of the Code of Federal Regulations Part 61.55, Tables 1 and 2 (including alpha emitting transuranics with half-lives greater than 5 years). Thismore » report discusses these radionuclides and other radionuclides that may be significant during a radiological performance assessment analysis of an LLW disposal facility. This report not only includes essential information on each radionuclide, but also incorporates waste and disposal information on the radionuclide, and behavior of the radionuclide in the environment and in the human body. Radionuclides addressed in this document include technetium-99, carbon-14, iodine-129, tritium, cesium-137, strontium-90, nickel-59, plutonium-241, nickel-63, niobium-94, cobalt-60, curium -42, americium-241, uranium-238, and neptunium-237.« less

Recent Improvement Of The Institutional Radioactive Waste Management System In Slovenia

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

Sueiae, S.; Fabjan, M.; Hrastar, U.

2008-07-01

The task of managing institutional radioactive waste was assigned to the Slovenian National Agency for Radwaste Management by the Governmental Decree of May 1999. This task ranges from the collection of waste at users' premises to the storage in the Central Storage Facility in (CSF) and afterwards to the planned Low and Intermediate Level Waste (LILW) repository. By this Decree ARAO also became the operator of the CSF. The CSF has been in operation since 1986. Recent improvements of the institutional radioactive waste management system in Slovenia are presented in this paper. ARAO has been working on the reestablishment ofmore » institutional radioactive waste management since 1999. The Agency has managed to prepare the most important documents and carry out the basic activities required by the legislation to assure a safe and environmentally acceptable management of the institutional radioactive waste. With the aim to achieve a better organized operational system, ARAO took the advantage of the European Union Transition Facility (EU TF) financing support and applied for the project named 'Improvement of the management of institutional radioactive waste in Slovenia via the design and implementation of an Information Business System'. Through a public invitation for tenders one of the Slovenian largest software company gained the contract. Two international radwaste experts from Belgium were part of their project team. The optimization of the operational system has been carried out in 2007. The project was executed in ten months and it was divided into two phases. The first phase of the project was related with the detection of weaknesses and implementation of the necessary improvements in the current ARAO operational system. With the evaluation of the existing system, possible improvements were identified. In the second phase of the project the software system Information Business System (IBS) was developed and implemented by the group of IT experts. As a software development life-cycle methodology the Waterfall methodology was used. The reason for choosing this methodology lied in its simple approach: analyze the problem, design the solution, implement the code, test the code, integrate and deploy. ARAO's institutional radioactive waste management process was improved in the way that it is more efficient, better organized, allowing traceability and availability of all documents and operational procedures within the field of institutional radioactive waste. The tailored made IBS system links all activities of the institutional radioactive waste management process: collection, transportation, takeover, acceptance, storing, treatment, radiation protection, etc. into one management system. All existing and newly designed evidences, operational procedures and other documents can be searched and viewed via secured Internet access from different locations. (authors)« less

Title list of documents made publicly available: June 1--30, 1995. Volume 17, Number 6

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

NONE

1995-08-01

This monthly publication contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

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

Morris, E.B.

The Title List of Documents Made Publicly Available is a monthly publication. It describes the information received and published by the U.S. Nuclear Regulatory Commission (NRC). This information includes (1) docketed, material associated with civilian nuclear power plants and other uses of radioactive materials and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index and amore » Report Number Index.« less

Title list of documents made publicly available: April 1--30, 1996. Volume 18, Number 4

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

NONE

1996-06-01

This publication describes the information received and published by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

Background for protective action recommendations: accidental radioactive contamination of food and animal feeds. Final report

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

Shleien, B.; Schmidt, G.D.; Chiacchierini, R.P.

This report provides background material for the development of FDA's Protective Action Recommendations: Accidental Radioactive Contamination of Food and Animal Feeds. The rationale, dosimetric and agricultural transport models for the Protective Action Guides are presented, along with information on dietary intake. In addition, the document contains a discussion of field methods of analysis of radionuclides deposited on the ground or contained in milk and herbage. Various protective actions are described and evaluated, and a cost-effectiveness analysis for the recommendations performed.

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

Morris, E.B.

The Title List of Documents Made Publicly Available is a monthly publication. It describes the information received and published by the U.S. Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and amore » Report Number Index. The docketed information contained in the Title List includes the information formerly issued through the Department of Energy publication Power Reactor Docket Information, last published in January 1979.« less

Surplus Highly Enriched Uranium Disposition Program plan

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

NONE

1996-10-01

The purpose of this document is to provide upper level guidance for the program that will downblend surplus highly enriched uranium for use as commercial nuclear reactor fuel or low-level radioactive waste. The intent of this document is to outline the overall mission and program objectives. The document is also intended to provide a general basis for integration of disposition efforts among all applicable sites. This plan provides background information, establishes the scope of disposition activities, provides an approach to the mission and objectives, identifies programmatic assumptions, defines major roles, provides summary level schedules and milestones, and addresses budget requirements.

Radioactive Liquid Waste Treatment Facility: Environmental Information Document

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

Haagenstad, H.T.; Gonzales, G.; Suazo, I.L.

1993-11-01

At Los Alamos National Laboratory (LANL), the treatment of radioactive liquid waste is an integral function of the LANL mission: to assure U.S. military deterrence capability through nuclear weapons technology. As part of this mission, LANL conducts nuclear materials research and development (R&D) activities. These activities generate radioactive liquid waste that must be handled in a manner to ensure protection of workers, the public, and the environment. Radioactive liquid waste currently generated at LANL is treated at the Radioactive Liquid Waste Treatment Facility (RLWTF), located at Technical Area (TA)-50. The RLWTF is 30 years old and nearing the end ofmore » its useful design life. The facility was designed at a time when environmental requirements, as well as more effective treatment technologies, were not inherent in engineering design criteria. The evolution of engineering design criteria has resulted in the older technology becoming less effective in treating radioactive liquid wastestreams in accordance with current National Pollutant Discharge Elimination System (NPDES) and Department of Energy (DOE) regulatory requirements. Therefore, to support ongoing R&D programs pertinent to its mission, LANL is in need of capabilities to efficiently treat radioactive liquid waste onsite or to transport the waste off site for treatment and/or disposal. The purpose of the EID is to provide the technical baseline information for subsequent preparation of an Environmental Impact Statement (EIS) for the RLWTF. This EID addresses the proposed action and alternatives for meeting the purpose and need for agency action.« less

Title list of documents made publicly available, November 1-30, 1995

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

NONE

1996-01-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the U.S. Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Indexmore » and a Report Number Index. The docketed information contained in the Title List includes the information formerly issued through the Department of Energy publication Power Reactor Docker Information, last published in January 1979. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR). Duplicate copies may be obtained for a fee. Standing orders for certain categories of documents are also available. Clients may search for and order desired titles through the PDR computerized Bibliographic Retrieval System, which is accessible both at the PDR and remotely. The PDR is staffed by professional technical librarians, who provide reference assistance to users.« less

Title list of documents made publicly available, December 1-31, 1997

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

NONE

This report includes the information received and published by the U.S. Nuclear Regulatory Commission (NRC) in December 1997. It includes: (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. This series of documents is indexed by author, corporate source, and report number. This report includes six docketed items and 24 non-docketed items.

W-320 Department of Health documentation

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

Bailey, J.W.

1998-08-07

The purpose of this document is to gather information required to show that Project W-320 is in compliance with Washington State Department of Health requirements as specified in Radioactive Air Emissions Notice of Construction Project W-320, Tank 241-C-106 Sluicing, DOE/RL-95-45. Specifically, that W-320 is in compliance with ASME N509-1989 (Nuclear Power Plant Air-Cleaning Units and Components) and ASME N5 10-1989 (Testing of Nuclear Air Treatment Systems) for the 296-C-006 exhaust system.

Interpreting and Reporting Radiological Water-Quality Data

USGS Publications Warehouse

McCurdy, David E.; Garbarino, John R.; Mullin, Ann H.

2008-01-01

This document provides information to U.S. Geological Survey (USGS) Water Science Centers on interpreting and reporting radiological results for samples of environmental matrices, most notably water. The information provided is intended to be broadly useful throughout the United States, but it is recommended that scientists who work at sites containing radioactive hazardous wastes need to consult additional sources for more detailed information. The document is largely based on recognized national standards and guidance documents for radioanalytical sample processing, most notably the Multi-Agency Radiological Laboratory Analytical Protocols Manual (MARLAP), and on documents published by the U.S. Environmental Protection Agency and the American National Standards Institute. It does not include discussion of standard USGS practices including field quality-control sample analysis, interpretive report policies, and related issues, all of which shall always be included in any effort by the Water Science Centers. The use of 'shall' in this report signifies a policy requirement of the USGS Office of Water Quality.

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

Virginia Finley

This report presents the results of environmental activities and monitoring programs at the Princeton Plasma Physics Laboratory (PPPL) for Calendar Years 2009-2010. The report provides the U.S. Department of Energy (DOE) and the public with information on the level of radioactive and non-radioactive pollutants, if any, that are released into the environment as a result of PPPL operations. The report also summarizes environmental initiatives, assessments, and programs that were undertaken in 2009-2010. The objective of the Site Environmental Report is to document PPPL's efforts to protect the public's health and the environment through its environmental protection, safety, and health programs.more » __________________________________________________« less

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

Not Available

The papers in this document comprise the proceedings of the Department of Energy's Twelfth Annual Low-Level Radioactive Waste Management Conference, which was held in Chicago, Illinois, on August 28 and 29, 1990. General subjects addressed during the conference included: mixed waste, low-level radioactive waste tracking and transportation, public involvement, performance assessment, waste stabilization, financial assurance, waste minimization, licensing and environmental documentation, below-regulatory-concern waste, low-level radioactive waste temporary storage, current challenges, and challenges beyond 1990.

Iraq liquid radioactive waste tanks maintenance and monitoring program plan.

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

Dennis, Matthew L.; Cochran, John Russell; Sol Shamsaldin, Emad

2011-10-01

The purpose of this report is to develop a project management plan for maintaining and monitoring liquid radioactive waste tanks at Iraq's Al-Tuwaitha Nuclear Research Center. Based on information from several sources, the Al-Tuwaitha site has approximately 30 waste tanks that contain varying amounts of liquid or sludge radioactive waste. All of the tanks have been non-operational for over 20 years and most have limited characterization. The program plan embodied in this document provides guidance on conducting radiological surveys, posting radiation control areas and controlling access, performing tank hazard assessments to remove debris and gain access, and conducting routine tankmore » inspections. This program plan provides general advice on how to sample and characterize tank contents, and how to prioritize tanks for soil sampling and borehole monitoring.« less

Radioactivity in fossils at the Hagerman Fossil Beds National Monument.

PubMed

Farmer, C Neal; Kathren, Ronald L; Christensen, Craig

2008-08-01

Since 1996, higher than background levels of naturally occurring radioactivity have been documented in both fossil and mineral deposits at Hagerman Fossil Beds National Monument in south-central Idaho. Radioactive fossil sites occur primarily within an elevation zone of 900-1000 m above sea level and are most commonly found associated with ancient river channels filled with sand. Fossils found in clay rich deposits do not exhibit discernable levels of radioactivity. Out of 300 randomly selected fossils, approximately three-fourths exhibit detectable levels of natural radioactivity ranging from 1 to 2 orders of magnitude above ambient background levels when surveyed with a portable hand held Geiger-Muller survey instrument. Mineral deposits in geologic strata also show above ambient background levels of radioactivity. Radiochemical lab analysis has documented the presence of numerous natural radioactive isotopes. It is postulated that ancient groundwater transported radioactive elements through sand bodies containing fossils which precipitated out of solution during the fossilization process. The elevated levels of natural radioactivity in fossils may require special precautions to ensure that exposures to personnel from stored or displayed items are kept as low as reasonably achievable (ALARA).

Title list of documents made publicly available, March 1--31, 1995: Volume 17, No. 3

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

NONE

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index,more » and a Report Number Index. The docketed information contained in the Title List includes the information formerly issued through the Department of Energy publication Power Reactor Docket Information, last published in January 1979. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR). Duplicate copies may be obtained for a fee. Standing orders for certain categories of documents are also available. Clients may search for and order desired titles through the PDR computerized Bibliographic Retrieval System, which is accessible both at the PDR and remotely. The PDR is staffed by professional technical librarians, who provide reference assistance to users. See NOTES at the end of the preface for information about reaching the PDR. Microfiche of the docketed information listed in the Title List is available for sale on a subscription basis from the National Technical Information Service (NTIS).« less

Biological Information Document, Radioactive Liquid Waste Treatment Facility

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

Biggs, J.

1995-12-31

This document is intended to act as a baseline source material for risk assessments which can be used in Environmental Assessments and Environmental Impact Statements. The current Radioactive Liquid Waste Treatment Facility (RLWTF) does not meet current General Design Criteria for Non-reactor Nuclear Facilities and could be shut down affecting several DOE programs. This Biological Information Document summarizes various biological studies that have been conducted in the vicinity of new Proposed RLWTF site and an Alternative site. The Proposed site is located on Mesita del Buey, a mess top, and the Alternative site is located in Mortandad Canyon. The Proposedmore » Site is devoid of overstory species due to previous disturbance and is dominated by a mixture of grasses, forbs, and scattered low-growing shrubs. Vegetation immediately adjacent to the site is a pinyon-juniper woodland. The Mortandad canyon bottom overstory is dominated by ponderosa pine, willow, and rush. The south-facing slope was dominated by ponderosa pine, mountain mahogany, oak, and muhly. The north-facing slope is dominated by Douglas fir, ponderosa pine, and oak. Studies on wildlife species are limited in the vicinity of the proposed project and further studies will be necessary to accurately identify wildlife populations and to what extent they utilize the project area. Some information is provided on invertebrates, amphibians and reptiles, and small mammals. Additional species information from other nearby locations is discussed in detail. Habitat requirements exist in the project area for one federally threatened wildlife species, the peregrine falcon, and one federal candidate species, the spotted bat. However, based on surveys outside of the project area but in similar habitats, these species are not expected to occur in either the Proposed or Alternative RLWTF sites. Habitat Evaluation Procedures were used to evaluate ecological functioning in the project area.« less

49 CFR 173.469 - Tests for special form Class 7 (radioactive) materials.

Code of Federal Regulations, 2010 CFR

2010-10-01

... prescribed in the International Organization for Standardization document ISO 9978-1992(E): “Radiation... not less than 90%. (v) The process in paragraphs (c)(2)(i), (c)(2)(ii), and (c)(2)(iii) of this... International Organization for Standardization document ISO 2919-1980(e), “Sealed Radioactive Sources...

Radioactive liquid wastes discharged to ground in the 200 Areas during 1978

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

Anderson, J. D.; Poremba, B. E.

1979-03-26

This document is issued quarterly for the purpose of summarizing the radioactive liquid wastes that have been discharged to the ground in the 200 Areas. In addition to data for 1978, cumulative data since plant startup are presented. Also, in this document is a listing of decayed activity to the various plant sites.

Geochemical Aspects of Radioactive Waste Disposal

NASA Astrophysics Data System (ADS)

Moody, Judith B.

1984-04-01

The author's stated purpose in writing this book is to summarize the large number of government-sponsored research reports on the geochemical aspects of high-level nuclear waste isolation. Although this book has a 1984 publication date, the majority of the cited documents were published before 1982. Unfortunately, passage of the Nuclear Waste Policy Act (NWPA) of 1982 and its signing into law by President Reagan (January 1983) [U.S. Congress, 1983] has significantly altered the U.S. Department of Energy (DOE) Civilian Radioactive Waste Management (CRWM) Program. Therefore this book does not accurately reflect the present U.S. program in geologic disposal of high-level nuclear waste. For example, chapter 2, “Radioactive Waste Management,” is almost 3 years out of date in a field that is changing rapidly (see U.S. DOE [1984a] for the current status of the CRWM Program). Additionally, the source material, which forms the input for this book, is chiefly grey literature, i.e., the referenced documents may or may not have undergone peer review and therefore do not represent the technical judgment of the scientific community. Also, this book only presents a selective sampling of information because the literature cited does not include a representative selection of the widespread available literature on this topic.

Evaluation of radioactive scrap metal recycling

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

Nieves, L.A.; Chen, S.Y.; Kohout, E.J.

1995-12-01

This report evaluates the human health risks and environmental and socio-political impacts of options for recycling radioactive scrap metal (RSM) or disposing of and replacing it. Argonne National Laboratory (ANL) is assisting the US Department of Energy (DOE), Office of Environmental Restoration and Waste Management, Oak Ridge Programs Division, in assessing the implications of RSM management alternatives. This study is intended to support the DOE contribution to a study of metal recycling being conducted by the Task Group on Recycling and Reuse of the Organization for Economic Cooperation and Development. The focus is on evaluating the justification for the practicemore » of recycling RSM, and the case of iron and steel scrap is used as an example in assessing the impacts. To conduct the evaluation, a considerable set of data was compiled and developed. Much of this information is included in this document to provide a source book of information.« less

Implementation of Information Management System for Radiation Safety of Personnel at the Russian Northwest Center for Radioactive Waste Management 'SevRAO' - 13131

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

Chizhov, K.; Simakov, A.; Seregin, V.

2013-07-01

The report is an overview of the information-analytical system designed to assure radiation safety of workers. The system was implemented in the Northwest Radioactive Waste Management Center 'SevRAO' (which is a branch of the Federal State Unitary Enterprise 'Radioactive Waste Management Enterprise RosRAO'). The center is located in the Northwest Russia. In respect to 'SevRAO', the Federal Medical-Biological Agency is the regulatory body, which deals with issues of radiation control. The main document to regulate radiation control is 'Reference levels of radiation factors in radioactive wastes management center'. This document contains about 250 parameters. We have developed a software toolmore » to simplify control of these parameters. The software includes: input interface, the database, dose calculating module and analytical block. Input interface is used to enter radiation environment data. Dose calculating module calculates the dose on the route. Analytical block optimizes and analyzes radiation situation maps. Much attention is paid to the GUI and graphical representation of results. The operator can enter the route at the industrial site or watch the fluctuations of the dose rate field on the map. Most of the results are presented in a visual form. Here we present some analytical tasks, such as comparison of the dose rate in some point with control levels at this point, to be solved for the purpose of radiation safety control. The program helps to identify points making the largest contribution to the collective dose of the personnel. The tool can automatically calculate the route with the lowest dose, compare and choose the best route. The program uses several options to visualize the radiation environment at the industrial site. This system will be useful for radiation monitoring services during the operation, planning of works and development of scenarios. The paper presents some applications of this system on real data over three years - from March 2009 to February 2012. (authors)« less

Title list of documents made publicly available, April 1--30 1997, Vol. 19, No. 4

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

Morris, E.B.

This report describes the information received and published by the U.S. Nuclear Regulatory Commission (NRC). This information includes: (1) material associated with civilian nuclear power plants and other uses of radioactive materials and (2) material received and published by NRC pertinent to its role as a regulatory agency. In this report, 7 items of the first type are included, and 25 regulatory type items are listed. The report is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

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

Langton, C.

Concrete containment structures and cement-based fills and waste forms are used at the Savannah River Site to enhance the performance of shallow land disposal systems designed for containment of low-level radioactive waste. Understanding and measuring transport through cracked concrete is important for describing the initial condition of radioactive waste containment structures at the Savannah River Site (SRS) and for predicting performance of these structures over time. This report transmits the results of a literature review on transport through cracked concrete which was performed by Professor Jason Weiss, Purdue University per SRR0000678 (RFP-RQ00001029-WY). This review complements the NRC-sponsored literature review andmore » assessment of factors relevant to performance of grouted systems for radioactive waste disposal. This review was performed by The Center for Nuclear Waste Regulatory Analyses, San Antonio, TX, and The University of Aberdeen, Aberdeen Scotland and was focused on tank closure. The objective of the literature review on transport through cracked concrete was to identify information in the open literature which can be applied to SRS transport models for cementitious containment structures, fills, and waste forms. In addition, the literature review was intended to: (1) Provide a framework for describing and classifying cracks in containment structures and cementitious materials used in radioactive waste disposal, (2) Document the state of knowledge and research related to transport through cracks in concrete for various exposure conditions, (3) Provide information or methodology for answering several specific questions related to cracking and transport in concrete, and (4) Provide information that can be used to design experiments on transport through cracked samples and actual structures.« less

Spent fuel and high-level radioactive waste transportation report

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

Not Available

This publication is intended to provide its readers with an introduction to the issues surrounding the subject of transportation of spent nuclear fuel and high-level radioactive waste, especially as those issues impact the southern region of the United States. It was originally issued by the Southern States Energy Board (SSEB) in July 1987 as the Spent Nuclear Fuel and High-Level Radioactive Waste Transportation Primer, a document patterned on work performed by the Western Interstate Energy Board and designed as a ``comprehensive overview of the issues.`` This work differs from that earlier effort in that it is designed for the educatedmore » layman with little or no background in nuclear waste issues. In addition, this document is not a comprehensive examination of nuclear waste issues but should instead serve as a general introduction to the subject. Owing to changes in the nuclear waste management system, program activities by the US Department of Energy and other federal agencies and developing technologies, much of this information is dated quickly. While this report uses the most recent data available, readers should keep in mind that some of the material is subject to rapid change. SSEB plans periodic updates in the future to account for changes in the program. Replacement pages sew be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list.« less

Spent fuel and high-level radioactive waste transportation report

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

Not Available

This publication is intended to provide its readers with an introduction to the issues surrounding the subject of transportation of spent nuclear fuel and high-level radioactive waste, especially as those issues impact the southern region of the United States. It was originally issued by the Southern States Energy Board (SSEB) in July 1987 as the Spent Nuclear Fuel and High-Level Radioactive Waste Transportation Primer, a document patterned on work performed by the Western Interstate Energy Board and designed as a ``comprehensive overview of the issues.`` This work differs from that earlier effort in that it is designed for the educatedmore » layman with little or no background in nuclear waste issues. In addition, this document is not a comprehensive examination of nuclear waste issues but should instead serve as a general introduction to the subject. Owing to changes in the nuclear waste management system, program activities by the US Department of Energy and other federal agencies and developing technologies, much of this information is dated quickly. While this report uses the most recent data available, readers should keep in mind that some of the material is subject to rapid change. SSEB plans periodic updates in the future to account for changes in the program. Replacement pages will be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list.« less

Spent Fuel and High-Level Radioactive Waste Transportation Report

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

Not Available

This publication is intended to provide its readers with an introduction to the issues surrounding the subject of transportation of spent nuclear fuel and high-level radioactive waste, especially as those issues impact the southern region of the United States. It was originally issued by SSEB in July 1987 as the Spent Nuclear Fuel and High-Level Radioactive Waste Transportation Primer, a document patterned on work performed by the Western Interstate Energy Board and designed as a ``comprehensive overview of the issues.`` This work differs from that earlier effort in that it is designed for the educated layman with little or nomore » background in nuclear waste Issues. In addition. this document is not a comprehensive examination of nuclear waste issues but should instead serve as a general introduction to the subject. Owing to changes in the nuclear waste management system, program activities by the US Department of Energy and other federal agencies and developing technologies, much of this information is dated quickly. While this report uses the most recent data available, readers should keep in mind that some of the material is subject to rapid change. SSEB plans periodic updates in the future to account for changes in the program. Replacement pages will be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list.« less

RadNet Air Quality (Fixed Station) Data

EPA Pesticide Factsheets

RadNet is a national network of monitoring stations that regularly collect air for analysis of radioactivity. The RadNet network, which has stations in each State, has been used to track environmental releases of radioactivity from nuclear weapons tests and nuclear accidents. RadNet also documents the status and trends of environmental radioactivity

Spent Nuclear Fuel Transportation: An Examination of Potential Lessons Learned From Prior Shipping Campaigns

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

Marsha Keister; Kathryn McBride

The Nuclear Waste Policy Act of 1982 (NWPA), as amended, assigned the Department of Energy (DOE) responsibility for developing and managing a Federal system for the disposal of spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for accepting, transporting, and disposing of SNF and HLW at the Yucca Mountain repository in a manner that protects public health, safety, and the environment; enhances national and energy security; and merits public confidence. OCRWM faces a near-term challenge—to develop and demonstrate a transportation system that will sustain safe and efficient shipments ofmore » SNF and HLW to a repository. To better inform and improve its current planning, OCRWM has extensively reviewed plans and other documents related to past high-visibility shipping campaigns of SNF and other radioactive materials within the United States. This report summarizes the results of this review and, where appropriate, lessons learned.« less

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2010

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

West, B.; Waltz, R.

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2010 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2010 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per SRR-LWE-2009-00138, HLW Tank Farm Inspection Plan for 2010, were completed. Ultrasonic measurements (UT) performed in 2010 met the requirements of C-ESG-00006, In-Service Inspection Program for Highmore » Level Waste Tanks, Rev. 3, and WSRC-TR-2002-00061, Rev.6. UT inspections were performed on Tanks 30, 31 and 32 and the findings are documented in SRNL-STI-2010-00533, Tank Inspection NDE Results for Fiscal Year 2010, Waste Tanks 30, 31 and 32. A total of 5824 photographs were made and 1087 visual and video inspections were performed during 2010. Ten new leaksites at Tank 5 were identified in 2010. The locations of these leaksites are documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.5. Ten leaksites at Tank 5 were documented during tank wall/annulus cleaning activities. None of these new leaksites resulted in a release to the environment. The leaksites were documented during wall cleaning activities and the waste nodules associated with the leaksites were washed away. Previously documented leaksites were reactivated at Tank 12 during waste removal activities.« less

Nuclear criticality safety assessment of the low level radioactive waste disposal facility trenches

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

Kahook, S.D.

1994-04-01

Results of the analyses performed to evaluate the possibility of nuclear criticality in the Low Level Radioactive Waste Disposal Facility (LLRWDF) trenches are documented in this report. The studies presented in this document are limited to assessment of the possibility of criticality due to existing conditions in the LLRWDF. This document does not propose nor set limits for enriched uranium (EU) burial in the LLRWDF and is not a nuclear criticality safety evaluation nor analysis. The calculations presented in the report are Level 2 calculations as defined by the E7 Procedure 2.31, Engineering Calculations.

Decision Support System For Management Of Low-Level Radioactive Waste Disposal At The Nevada Test Site

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

Shott, G.; Yucel, V.; Desotell, L.

2006-07-01

The long-term safety of U.S. Department of Energy (DOE) low-level radioactive disposal facilities is assessed by conducting a performance assessment -- a systematic analysis that compares estimated risks to the public and the environment with performance objectives contained in DOE Manual 435.1-1, Radioactive Waste Management Manual. Before site operations, facilities design features such as final inventory, waste form characteristics, and closure cover design may be uncertain. Site operators need a modeling tool that can be used throughout the operational life of the disposal site to guide decisions regarding the acceptance of problematic waste streams, new disposal cell design, environmental monitoringmore » program design, and final site closure. In response to these needs the National Nuclear Security Administration Nevada Site Office (NNSA/NSO) has developed a decision support system for the Area 5 Radioactive Waste Management Site in Frenchman Flat on the Nevada Test Site. The core of the system is a probabilistic inventory and performance assessment model implemented in the GoldSim{sup R} simulation platform. The modeling platform supports multiple graphic capabilities that allow clear documentation of the model data sources, conceptual model, mathematical implementation, and results. The combined models have the capability to estimate disposal site inventory, contaminant concentrations in environmental media, and radiological doses to members of the public engaged in various activities at multiple locations. The model allows rapid assessment and documentation of the consequences of waste management decisions using the most current site characterization information, radionuclide inventory, and conceptual model. The model is routinely used to provide annual updates of site performance, evaluate the consequences of disposal of new waste streams, develop waste concentration limits, optimize the design of new disposal cells, and assess the adequacy of environmental monitoring programs. (authors)« less

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

Garabedian, G.

This document details the decontamination and decommissioning (D&D) process of Rooms 248 and 250 of Building 62 at the Ernest Orlando Lawrence Berkeley National Laboratory (LBNL). The document describes the D&D efforts for the rooms, their contents, and adjacent areas containing ancillary equipment. The rooms and equipment, before being released, were required to meet the unrestricted release criteria and requirements set forth in DOE orders 5400.5 and 5480.11, LBNL`s internal release-criteria procedure (EH&S Procedure 708), and the LBNL Radiological Control Manual. The radioactive material and items not meeting the release criteria were either sent to the Hazardous Waste Handling Facilitymore » (HWHF) for disposal or transferred to other locations approved for radioactive material. The D&D was undertaken by the Radiation Protection Group of LBNL`s Environment, Health and Safety (EH&S) Division at the request of the Materials Sciences Division. Current and past use of radioactive material in both Rooms 248 and 250 necessitated the D&D in order to release both rooms for nonradioactive work. (1) Room 248 was designated a {open_quotes}controlled area.{close_quotes} There was contained radioactive material in some of the equipment. The previous occupants of Room 248 had worked with radioactive materials. (2) Room 250 was designated a {open_quotes}Radioactive Materials Management Area{close_quotes} (RMMA) because the current occupants used potentially dispersible radioisotopes. Both laboratories, during the occupancy of U.C. Berkeley Professor Leo Brewer and Ms. Karen Krushwitz, were kept in excellent condition. There was a detailed inventory of all radioactive materials and chemicals. All work and self surveys were documented. The labs were kept extremely orderly, clean, and in compliance. In October 1993 Ms. Krushwitz received an award in recognition of her efforts in Environmental Protection, Health, and Safety at LBNL.« less

The Spanish General Radioactive Waste Management Plan

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

Espejo, J.M.; Abreu, A.

This paper mainly describes the strategies, the necessary actions and the technical solutions to be developed by ENRESA in the short, medium and long term, aimed at ensuring the adequate management of radioactive waste, the dismantling and decommissioning of nuclear and radioactive facilities and other activities, including economic and financial measures required to carry them out. Starting with the Spanish administrative organization in this field, which identifies the different agents involved and their roles, and after referring to the waste generation, the activities to be performed in the areas of LILW, SF and HLW management, decommissioning of installations and othersmore » are summarized. Finally, the future management costs are estimated and the financing system currently in force is explained. The so-called Sixth General Radioactive Waste Plan (6. GRWP), approved by the Spanish Government, is the 'master document' of reference where all the above mentioned issues are contemplated. In summary: The 6. GRWP includes the strategies and actions to be performed by Enresa in the coming years. The document, revised by the Government and subject to a process of public information, underlines the fact that Spain possesses an excellent infrastructure for the safe and efficient management of radioactive waste, from the administrative, technical and economic-financial points of view. From the administrative point of view there is an organisation, supported by ample legislative developments, that contemplates and governs the main responsibilities of the parties involved in the process (Government, CSN, ENRESA and waste producers). As regards the technical aspect, the experience accumulated to date by Enresa is particularly significant, as are the technologies now available in the field of management and for dismantling processes. As regards the economic-financial basis, a system is in place that guarantees the financing of radioactive waste management costs. This system is based on the generation of funds up front, during the operating lifetime of the facilities, through the application of fees established by Statutory provisions. Finally, a mandatory mechanism of annual revision for both technical issues and economic and financial aspects, allows to have updated all the courses of action. (authors)« less

Karlsruhe Database for Radioactive Wastes (KADABRA) - Accounting and Management System for Radioactive Waste Treatment - 12275

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

Himmerkus, Felix; Rittmeyer, Cornelia

2012-07-01

The data management system KADABRA was designed according to the purposes of the Cen-tral Decontamination Department (HDB) of the Wiederaufarbeitungsanlage Karlsruhe Rueckbau- und Entsorgungs-GmbH (WAK GmbH), which is specialized in the treatment and conditioning of radioactive waste. The layout considers the major treatment processes of the HDB as well as regulatory and legal requirements. KADABRA is designed as an SAG ADABAS application on IBM system Z mainframe. The main function of the system is the data management of all processes related to treatment, transfer and storage of radioactive material within HDB. KADABRA records the relevant data concerning radioactive residues, interimmore » products and waste products as well as the production parameters relevant for final disposal. Analytical data from the laboratory and non destructive assay systems, that describe the chemical and radiological properties of residues, production batches, interim products as well as final waste products, can be linked to the respective dataset for documentation and declaration. The system enables the operator to trace the radioactive material through processing and storage. Information on the actual sta-tus of the material as well as radiological data and storage position can be gained immediately on request. A variety of programs accessed to the database allow the generation of individual reports on periodic or special request. KADABRA offers a high security standard and is constantly adapted to the recent requirements of the organization. (authors)« less

Waste certification program plan for Oak Ridge National Laboratory. Revision 1

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

Orrin, R.C.

1997-05-01

This document defines the waste certification program developed for implementation at Oak Ridge National Laboratory (ORNL). The document describes the program structure, logic, and methodology for certification of ORNL wastes. The purpose of the waste certification program is to provide assurance that wastes are properly characterized and that the Waste Acceptance Criteria (WAC) for receiving facilities are met. The program meets the waste certification requirements outlined in US Department of Energy (DOE) Order 5820.2A, Radioactive Waste Management, and ensures that 40 CFR documentation requirements for waste characterization are met for mixed (both radioactive and hazardous) and hazardous (including polychlorinated biphenyls)more » waste. Program activities will be conducted according to ORNL Level 1 document requirements.« less

Radioactive contamination in the environs of the Hanford Works for the period April, May, June 1949

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

Paas, H.J.; Singlevich, W.

1950-04-03

This report summarizes the measurements made for radioactive contamination in the environs of the Hanford Works for the quarter April through June 1949. This belated document is issued for the records to fill in the gap for the quarterly reports not issued in 1949 because of personnel shortage at that time. Although the data summarized in this report were already reported in the H. I. Evirons Reports for the months involved, it is still of value to study the data combining the three months of data which give better opportunity to evaluate the trends and patterns of the levels ofmore » radioactive contamination emanating from the various sources at the Hanford Works. This document discusses: meteorological data and radioactive contamination in vegetation, the atmosphere, rain, Hanford wastes, the Columbia River, and in drinking water and test wells.« less

Contextual Information for the Potential Enhancement of Annual Radiation Protection Program Review Reports.

PubMed

Emery, Robert J; Gutiérrez, Janet M

2017-08-01

Organizations possessing sources of ionizing radiation are required to develop, document, and implement a "radiation protection program" that is commensurate with the scope and extent of permitted activities and sufficient to ensure compliance with basic radiation safety regulations. The radiation protection program must also be reviewed at least annually, assessing program content and implementation. A convenience sample assessment of web-accessible and voluntarily-submitted radiation protection program annual review reports revealed that while the reports consistently documented compliance with necessary regulatory elements, very few included any critical contextual information describing how important the ability to possess radiation sources was to the central mission of the organization. Information regarding how much radioactive material was currently possessed as compared to license limits was also missing. Summarized here are suggested contextual elements that can be considered for possible inclusion in annual radiation protection program reviews to enhance stakeholder understanding and appreciation of the importance of the ability to possess radiation sources and the importance of maintaining compliance with associated regulatory requirements.

SU-G-PinS Room/Hall E-00: HAZMAT Training for the Medical Physicist - Part II

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

NONE

Medical Physicists are frequently involved in shipping radioactive materials or supervising those who do. Current U.S. Department of Transportation Hazardous Material Regulations, 49 CFR Parts 171 - 185, require hazmat employees to have documented training specified in 49 CFR 172 Subpart H. A hazmat employee is defined as an individual who: (1) loads, unloads or handles hazardous material; (2) manufactures, tests, reconditions, repairs, modifies, marks or otherwise represents containers, drums or packagings as qualified for use in the transportation of hazardous materials; (3) prepares hazardous materials for transportation; (4) is responsible for safety of transporting hazardous materials; or (5) operatesmore » a vehicle used to transport hazardous materials. Recurrent training is required at least once every three years. (The IATA two year training interval is not applicable and is generally misunderstood.) FAA has escalated inspection and enforcement. Facilities who ship radiopharmaceuticals to other laboratories, return radiopharmaceuticals or radioactive sources to suppliers, or otherwise ship radioactive materials have been cited for failure to provide and document the required training. The interrelationship of transportation regulations, 49 CFR, IATA, ICAO and other transportation regulations, which are frequently misunderstood, will be explained. The course will cover typical shipments by air and highway which are encountered in a medical institution. Items such as fissile materials, highway route controlled quantities, rail shipments, vessel shipments and such will be omitted; although specific questions may be addressed. A major objective of the course is to present the process of shipping radioactive material in a sequential and logical fashion. How radioactive materials for transportation purposes are defined by activity concentrations for exempt materials and activity limits for exempt consignments will be explained. Radioactive material shipments of excepted packages and Type A packages will be emphasized. The program is designed to meet the function specific DOT training requirements for shippers of medical radioactive materials. General awareness training and security awareness training can be obtained from two free DOT training CDs. Safety training and security awareness training is generally satisfied by the training required under the institution’s radioactive material license. For shippers of radioactive Yellow III labeled packages an in-depth written security plan and training are no longer required as of April 8, 2010. In general almost all shippers of medical radioactive material are now not required to have an in-depth security plan. Contents of general awareness training, security awareness training and in-depth security plans will be briefly outlined. It is the hazmat employer’s responsibility to ensure that each hazmat employee is properly trained. No third party can fulfill that requirement. It is the hazmat employer’s responsibility to determine the degree to which this course meets the employer’s requirements, including contents of the course and the examination. Participants will gain sufficient knowledge to prepare hazmat training programs for others in their institutions. A handout will be posted which should be printed out and brought to the course for reference during the presentation. The handout will also satisfy part of the training documentation required by DOT. A feature handout section is a composite table which provides A1, A2, RQ, Exempt Concentration, and Exempt Consignment values in a single table in both Becquerel and Curie units. Course attendance will be certified through the AAPM CEU documentation system. Learning Objectives: Understand the regulatory requirements for shipping radioactive materials. Understand the regulatory requirements for training of hazmat employees. Comprehend how to classify, package, mark, label, document, placard, and transport radioactive materials.« less

SU-CD-PinS Room/Hall E-00: HAZMAT Training for the Medical Physicist - Part I

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

NONE

Medical Physicists are frequently involved in shipping radioactive materials or supervising those who do. Current U.S. Department of Transportation Hazardous Material Regulations, 49 CFR Parts 171 - 185, require hazmat employees to have documented training specified in 49 CFR 172 Subpart H. A hazmat employee is defined as an individual who: (1) loads, unloads or handles hazardous material; (2) manufactures, tests, reconditions, repairs, modifies, marks or otherwise represents containers, drums or packagings as qualified for use in the transportation of hazardous materials; (3) prepares hazardous materials for transportation; (4) is responsible for safety of transporting hazardous materials; or (5) operatesmore » a vehicle used to transport hazardous materials. Recurrent training is required at least once every three years. (The IATA two-year training interval is not applicable and is generally misunderstood.) FAA has escalated inspection and enforcement. Facilities who ship radiopharmaceuticals to other laboratories, return radiopharmaceuticals or radioactive sources to suppliers, or otherwise ship radioactive materials have been cited for failure to provide and document the required training. The interrelationship of transportation regulations, 49 CFR, IATA, ICAO and other transportation regulations, which are frequently misunderstood, will be explained. The course will cover typical shipments by air and highway which are encountered in a medical institution. Items such as fissile materials, highway route controlled quantities, rail shipments, vessel shipments and such will be omitted; although specific questions may be addressed. A major objective of the course is to present the process of shipping radioactive material in a sequential and logical fashion. How radioactive materials for transportation purposes are defined by activity concentrations for exempt materials and activity limits for exempt consignments will be explained. Radioactive material shipments of excepted packages and Type A packages will be emphasized. The program is designed to meet the function specific DOT training requirements for shippers of medical radioactive materials. General awareness training and security awareness training can be obtained from two free DOT training CDs. Safety training and security awareness training is generally satisfied by the training required under the institution’s radioactive material license. For shippers of radioactive Yellow III labeled packages an in-depth written security plan and training are no longer required as of April 8, 2010. In general almost all shippers of medical radioactive material are now not required to have an in-depth security plan. Contents of general awareness training, security awareness training and in-depth security plans will be briefly outlined. It is the hazmat employer’s responsibility to ensure that each hazmat employee is properly trained. No third party can fulfill that requirement. It is the hazmat employer’s responsibility to determine the degree to which this course meets the employer’s requirements, including contents of the course and the examination. Participants will gain sufficient knowledge to prepare hazmat training programs for others in their institutions. A handout will be posted which should be printed out and brought to the course for reference during the presentation. The handout will also satisfy part of the training documentation required by DOT. A feature handout section is a composite table which provides A1, A2, RQ, Exempt Concentration, and Exempt Consignment values in a single table in both Becquerel and Curie units. Course attendance will be certified through the AAPM CEU documentation system. Learning Objectives: Understand the regulatory requirements for shipping radioactive materials. Understand the regulatory requirements for training of hazmat employees. Comprehend how to classify, package, mark, label, document, placard, and transport radioactive materials.« less

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

Parker, R.

Medical Physicists are frequently involved in shipping radioactive materials or supervising those who do. Current U.S. Department of Transportation Hazardous Material Regulations, 49 CFR Parts 171 - 185, require hazmat employees to have documented training specified in 49 CFR 172 Subpart H. A hazmat employee is defined as an individual who: (1) loads, unloads or handles hazardous material; (2) manufactures, tests, reconditions, repairs, modifies, marks or otherwise represents containers, drums or packagings as qualified for use in the transportation of hazardous materials; (3) prepares hazardous materials for transportation; (4) is responsible for safety of transporting hazardous materials; or (5) operatesmore » a vehicle used to transport hazardous materials. Recurrent training is required at least once every three years. (The IATA two-year training interval is not applicable and is generally misunderstood.) FAA has escalated inspection and enforcement. Facilities who ship radiopharmaceuticals to other laboratories, return radiopharmaceuticals or radioactive sources to suppliers, or otherwise ship radioactive materials have been cited for failure to provide and document the required training. The interrelationship of transportation regulations, 49 CFR, IATA, ICAO and other transportation regulations, which are frequently misunderstood, will be explained. The course will cover typical shipments by air and highway which are encountered in a medical institution. Items such as fissile materials, highway route controlled quantities, rail shipments, vessel shipments and such will be omitted; although specific questions may be addressed. A major objective of the course is to present the process of shipping radioactive material in a sequential and logical fashion. How radioactive materials for transportation purposes are defined by activity concentrations for exempt materials and activity limits for exempt consignments will be explained. Radioactive material shipments of excepted packages and Type A packages will be emphasized. The program is designed to meet the function specific DOT training requirements for shippers of medical radioactive materials. General awareness training and security awareness training can be obtained from two free DOT training CDs. Safety training and security awareness training is generally satisfied by the training required under the institution’s radioactive material license. For shippers of radioactive Yellow III labeled packages an in-depth written security plan and training are no longer required as of April 8, 2010. In general almost all shippers of medical radioactive material are now not required to have an in-depth security plan. Contents of general awareness training, security awareness training and in-depth security plans will be briefly outlined. It is the hazmat employer’s responsibility to ensure that each hazmat employee is properly trained. No third party can fulfill that requirement. It is the hazmat employer’s responsibility to determine the degree to which this course meets the employer’s requirements, including contents of the course and the examination. Participants will gain sufficient knowledge to prepare hazmat training programs for others in their institutions. A handout will be posted which should be printed out and brought to the course for reference during the presentation. The handout will also satisfy part of the training documentation required by DOT. A feature handout section is a composite table which provides A1, A2, RQ, Exempt Concentration, and Exempt Consignment values in a single table in both Becquerel and Curie units. Course attendance will be certified through the AAPM CEU documentation system. Learning Objectives: Understand the regulatory requirements for shipping radioactive materials. Understand the regulatory requirements for training of hazmat employees. Comprehend how to classify, package, mark, label, document, placard, and transport radioactive materials.« less

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

Parker, R.

Medical Physicists are frequently involved in shipping radioactive materials or supervising those who do. Current U.S. Department of Transportation Hazardous Material Regulations, 49 CFR Parts 171 - 185, require hazmat employees to have documented training specified in 49 CFR 172 Subpart H. A hazmat employee is defined as an individual who: (1) loads, unloads or handles hazardous material; (2) manufactures, tests, reconditions, repairs, modifies, marks or otherwise represents containers, drums or packagings as qualified for use in the transportation of hazardous materials; (3) prepares hazardous materials for transportation; (4) is responsible for safety of transporting hazardous materials; or (5) operatesmore » a vehicle used to transport hazardous materials. Recurrent training is required at least once every three years. (The IATA two year training interval is not applicable and is generally misunderstood.) FAA has escalated inspection and enforcement. Facilities who ship radiopharmaceuticals to other laboratories, return radiopharmaceuticals or radioactive sources to suppliers, or otherwise ship radioactive materials have been cited for failure to provide and document the required training. The interrelationship of transportation regulations, 49 CFR, IATA, ICAO and other transportation regulations, which are frequently misunderstood, will be explained. The course will cover typical shipments by air and highway which are encountered in a medical institution. Items such as fissile materials, highway route controlled quantities, rail shipments, vessel shipments and such will be omitted; although specific questions may be addressed. A major objective of the course is to present the process of shipping radioactive material in a sequential and logical fashion. How radioactive materials for transportation purposes are defined by activity concentrations for exempt materials and activity limits for exempt consignments will be explained. Radioactive material shipments of excepted packages and Type A packages will be emphasized. The program is designed to meet the function specific DOT training requirements for shippers of medical radioactive materials. General awareness training and security awareness training can be obtained from two free DOT training CDs. Safety training and security awareness training is generally satisfied by the training required under the institution’s radioactive material license. For shippers of radioactive Yellow III labeled packages an in-depth written security plan and training are no longer required as of April 8, 2010. In general almost all shippers of medical radioactive material are now not required to have an in-depth security plan. Contents of general awareness training, security awareness training and in-depth security plans will be briefly outlined. It is the hazmat employer’s responsibility to ensure that each hazmat employee is properly trained. No third party can fulfill that requirement. It is the hazmat employer’s responsibility to determine the degree to which this course meets the employer’s requirements, including contents of the course and the examination. Participants will gain sufficient knowledge to prepare hazmat training programs for others in their institutions. A handout will be posted which should be printed out and brought to the course for reference during the presentation. The handout will also satisfy part of the training documentation required by DOT. A feature handout section is a composite table which provides A1, A2, RQ, Exempt Concentration, and Exempt Consignment values in a single table in both Becquerel and Curie units. Course attendance will be certified through the AAPM CEU documentation system. Learning Objectives: Understand the regulatory requirements for shipping radioactive materials. Understand the regulatory requirements for training of hazmat employees. Comprehend how to classify, package, mark, label, document, placard, and transport radioactive materials.« less

Radioactivity in returned lunar materials

NASA Technical Reports Server (NTRS)

1972-01-01

The H-3, Ar-37, and Ar-39 radioactivities were measured at several depths in the large documented lunar rocks 14321 and 15555. The comparison of the Ar-37 activities from similar locations in rocks 12002, 14321, and 15555 gives direct measures of the amount of Ar-37 produced by the 2 November 1969 and 24 January 1971 solar flares. The tritium contents in the documented rocks decreased with increasing depths. The solar flare intensity averaged over 30 years obtained from the tritium depth dependence was approximately the same as the flare intensity averaged over 1000 years obtained from the Ar-37 measurements. Radioactivities in two Apollo 15 soil samples, H-3 in several Surveyor 3 samples, and tritium and radon weepage were also measured.

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

Finley, V.L.; Stencel, J.R.

This report gives the results of the environmental activities and monitoring programs at the Princeton Plasma Physics Laboratory (PPPL) for CY91. The report is prepared to provide the US Department of Energy (DOE) and the public with information on the level of radioactive and nonradioactive pollutants, if any, added to the environment as a result of PPPL operations, as well as environmental initiatives, assessments, and programs. The objective of the Annual Site Environmental Report is to document evidence that DOE facility environmental protection programs adequately protect the environment and the public health.

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

Finley, V.L.; Wieczorek, M.A.

This report gives the results of the environmental activities and monitoring programs at the Princeton Plasma Physics Laboratory (PPPL) for CY92. The report is prepared to provide the US Department of Energy (DOE) and the public with information on the level of radioactive and nonradioactive pollutants, if any, added to the environment as a result of PPPL operations, as well as environmental initiatives, assessments, and programs. The objective of the Annual Site Environmental Report is to document evidence that DOE facility environmental protection programs adequately protect the environment and the public health.

The Accumulation of Radioactive Contaminants in Drinking Water Distribution Systems

EPA Science Inventory

The accumulation of trace contaminants in drinking water distribution systems has been documented and the subsequent release of the contaminants back to the water is a potential exposure pathway. Radioactive contaminants are of particular concern because of their known health eff...

Authorized limits for Fernald copper ingots

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

Frink, N.; Kamboj, S.; Hensley, J.

This development document contains data and analysis to support the approval of authorized limits for the unrestricted release of 59 t of copper ingots containing residual radioactive material from the U.S. Department of Energy (DOE) Fernald Environmental Management Project (FEMP). The analysis presented in this document comply with the requirements of DOE Order 5400.5, {open_quotes}Radiation Protection of the Public and the Environment,{close_quotes} as well as the requirements of the proposed promulgation of this order as 10 CFR Part 834. The document was developed following the step-by-step process described in the Draft Handbook for Controlling Release for Reuse or Recycle Propertymore » Containing Residual Radioactive Material.« less

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

Clayton, C.; Gueretta, J.; Tack, J.

The Manhattan Engineer District (MED) and U.S. Atomic Energy Commission (AEC) contracted for support work through private and academic parties through the early 1960's. The work often involved radioactive materials. Residual radioactive contamination was left at some of more than 600 potentially contaminated (candidate) sites, and worker health and safety concerns remain from the site operations and subsequent remediation activities. The U.S. Department of Energy (DOE) initiated a program to identify and protect records of MED/AEC activities and of remediation work conducted under the Formerly Utilized Sites Remedial Action Program (FUSRAP) to aid in resolving questions about site conditions, liability,more » and worker health and safety and to ensure ongoing protectiveness of human health and the environment. This paper discusses DOE activities undertaken to locate records collections, confirm retention schedules and access requirements, and document information about the collections for use by future stewards. In conclusion: DOE-LM recognizes that records and information management is a critical component of effective LTS and M. Records are needed to answer questions about site conditions and demonstrate to the public in the future that the sites are safe. DOE-LM is working to satisfy present needs and anticipate future uses for FUSRAP records, and compile a collection of site and program information from which future stewards can readily locate and retrieve needed information. (authors)« less

Thirteenth annual U.S. DOE low-level radioactive waste management conference: Proceedings

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

NONE

1991-12-31

The 40 papers in this document comprise the proceedings of the Department of Energy`s Thirteenth Annual Low-Level Radioactive Waste Management Conference that was held in Atlanta, Georgia, on November 19--21, 1991. General subjects addressed during the conference included: disposal facility design; greater-than-class C low-level waste; public acceptance considerations; waste certification; site characterization; performance assessment; licensing and documentation; emerging low-level waste technologies; waste minimization; mixed waste; tracking and transportation; storage; and regulatory changes. Papers have been processed separately for inclusion on the data base.

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2009

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

West, B.; Waltz, R.

2010-06-21

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2009 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2009 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per LWO-LWE-2008-00423, HLW Tank Farm Inspection Plan for 2009, were completed. All Ultrasonic measurements (UT) performed in 2009 met the requirements of C-ESG-00006, In-Service Inspection Program formore » High Level Waste Tanks, Rev. 1, and WSRC-TR-2002-00061, Rev.4. UT inspections were performed on Tank 29 and the findings are documented in SRNL-STI-2009-00559, Tank Inspection NDE Results for Fiscal Year 2009, Waste Tank 29. Post chemical cleaning UT measurements were made in Tank 6 and the results are documented in SRNL-STI-2009-00560, Tank Inspection NDE Results Tank 6, Including Summary of Waste Removal Support Activities in Tanks 5 and 6. A total of 6669 photographs were made and 1276 visual and video inspections were performed during 2009. Twenty-Two new leaksites were identified in 2009. The locations of these leaksites are documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.4. Fifteen leaksites at Tank 5 were documented during tank wall/annulus cleaning activities. Five leaksites at Tank 6 were documented during tank wall/annulus cleaning activities. Two new leaksites were identified at Tank 19 during waste removal activities. Previously documented leaksites were reactivated at Tanks 5 and 12 during waste removal activities. Also, a very small amount of additional leakage from a previously identified leaksite at Tank 14 was observed.« less

Sandia National Laboratories performance assessment methodology for long-term environmental programs : the history of nuclear waste management.

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

Marietta, Melvin Gary; Anderson, D. Richard; Bonano, Evaristo J.

2011-11-01

Sandia National Laboratories (SNL) is the world leader in the development of the detailed science underpinning the application of a probabilistic risk assessment methodology, referred to in this report as performance assessment (PA), for (1) understanding and forecasting the long-term behavior of a radioactive waste disposal system, (2) estimating the ability of the disposal system and its various components to isolate the waste, (3) developing regulations, (4) implementing programs to estimate the safety that the system can afford to individuals and to the environment, and (5) demonstrating compliance with the attendant regulatory requirements. This report documents the evolution of themore » SNL PA methodology from inception in the mid-1970s, summarizing major SNL PA applications including: the Subseabed Disposal Project PAs for high-level radioactive waste; the Waste Isolation Pilot Plant PAs for disposal of defense transuranic waste; the Yucca Mountain Project total system PAs for deep geologic disposal of spent nuclear fuel and high-level radioactive waste; PAs for the Greater Confinement Borehole Disposal boreholes at the Nevada National Security Site; and PA evaluations for disposal of high-level wastes and Department of Energy spent nuclear fuels stored at Idaho National Laboratory. In addition, the report summarizes smaller PA programs for long-term cover systems implemented for the Monticello, Utah, mill-tailings repository; a PA for the SNL Mixed Waste Landfill in support of environmental restoration; PA support for radioactive waste management efforts in Egypt, Iraq, and Taiwan; and, most recently, PAs for analysis of alternative high-level radioactive waste disposal strategies including repositories deep borehole disposal and geologic repositories in shale and granite. Finally, this report summarizes the extension of the PA methodology for radioactive waste disposal toward development of an enhanced PA system for carbon sequestration and storage systems. These efforts have produced a generic PA methodology for the evaluation of waste management systems that has gained wide acceptance within the international community. This report documents how this methodology has been used as an effective management tool to evaluate different disposal designs and sites; inform development of regulatory requirements; identify, prioritize, and guide research aimed at reducing uncertainties for objective estimations of risk; and support safety assessments.« less

Documenting Ground-Water Modeling at Sites Contaminated with Radioactive Substances

EPA Pesticide Factsheets

This report is the product of the Interagency Environmental Pathway Modeling Working Group. This report demonstrates how to document model applications in a consistent manner and is intended to assist technical staff.

Rooting Characteristics of Vegetation Near Areas 3 and 5 Radioactive Waste Management Sites at the Nevada Test Site--Part 1

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

D. J. Hansen

2003-09-30

The U.S. Department of Energy emplaced high-specific-activity low-level radioactive wastes and limited quantities of classified transuranic wastes in Greater Confinement Disposal (GCD) boreholes from 1984 to 1989. The boreholes are located at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada Test Site (NTS) in southern Nevada. The boreholes were backfilled with native alluvium soil. The surface of these boreholes and trenches is expected to be colonized by native vegetation in the future. Considering the long-term performance of the disposal facilities, bioturbation (the disruption of buried wastes by biota) is considered a primary release mechanism for radionuclides disposedmore » in GCD boreholes as well as trenches at both Areas 3 and 5 RWMSs. This report provides information about rooting characteristics of vegetation near Areas 3 and 5 RWMSs. Data from this report are being used to resolve uncertainties involving parameterization of performance assessment models used to characterize the biotic mixing of soils and radionuclide transport processes by biota. The objectives of this study were to: (1) survey the prior ecological literature on the NTS and identify pertinent information about the vegetation, (2) conduct limited field studies to describe the current vegetation in the vicinity of Areas 3 and 5 RWMSs so as to correlate findings with more extensive vegetation data collected at Yucca Mountain and the NTS, ( 3 ) review prior performance assessment documents and evaluate model assumptions based on current ecological information, and (4) identify data deficiencies and make recommendations for correcting such deficiencies.« less

NRC`s proposed rulemaking on the documentation and reporting of low-level radioactive waste shipment manifest information

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

Lahs, W.R.; Haisfield, M.F.

1991-12-31

Since the 1982 promulgation of regulations for the land disposal of low-level radioactive waste (LLW), requirements have been in place to control transfers of LLW intended for disposal at licensed land disposal facilities. These requirements established a manifest tracking system and defined processes to control transfers of LLW intended for disposal at a land disposal facility. Because the regulations did not specify the format for the LLW shipment manifests, it was not unexpected that the two operators of the three currently operating disposal sites should each have developed their own manifest forms. The forms have many similarities and the collectedmore » information, in many cases, is identical; however, these manifests incorporate unique operator preferences and also reflect the needs of the Agreement State regulatory authority in the States where the disposal sites are located. Since Agreement State regulations must be compatible with, but need not always be identical to, those of the Nuclear Regulatory Commission (NRC), the possibility of a proliferation of different manifest forms containing variations in collected information could be envisioned. If these manifests were also to serve a shipping paper purpose, effective integration of the Department of Transportations` (DOT) requirements would also have to be addressed. This wide diversity in uses of manifest information by Federal and State regulatory authorities, other State or Compact entities, and disposal site operators, suggested a single consolidated approach to develop a uniform manifest format with a baseline information content and to define recordkeeping requirements. The NRC, in 1989, had embarked on a rulemaking activity to establish a base set of manifest information needs for regulatory purposes. In response to requests from State and Regional Compact organizations who are attempting to design, develop and operate LLW disposal facilities, and with the general support of Agreement State regulatory authorities, this original data base rulemaking was expanded to include development of a uniform low-level radioactive waste manifest.« less

PATRAM '92: 10th international symposium on the packaging and transportation of radioactive materials [Papers presented by Sandia National Laboratories

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

None

This document provides the papers presented by Sandia Laboratories at PATRAM '92, the tenth International symposium on the Packaging and Transportation of Radioactive Materials held September 13--18, 1992 in Yokohama City, Japan. Individual papers have been cataloged separately. (FL)

Living With and Learning about Radioactivity: A Comparative Conceptual Study.

ERIC Educational Resources Information Center

Alsop, Steve

2001-01-01

Documents a quasi-scientific comparative study of two groups of 'recent school leavers' in the UK. Studies non-science university undergraduates and explores whether people living with the immediacy and relevance of higher-than-average levels of radioactivity were more knowledgeable and emotionally detached than a similar group removed from this…

76 FR 44619 - In the Matter of Bozeman Deaconess Foundation, dba Bozeman Deaconess Hospital, Bozeman, MT...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-07-26

... radioactive materials from unauthorized access or removal from the facility's nuclear medicine laboratory (hot... secure radioactive material during periods when authorized personnel were absent from the hot lab. Based... E-Filing system time-stamps the document and sends the submitter an e-mail notice confirming receipt...

A workshop on developing risk assessment methods for medical use of radioactive material. Volume 2: Supporting documents

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

Tortorelli, J.P.

A workshop was held at the Idaho National Engineering Laboratory, August 16--18, 1994 on the topic of risk assessment on medical devices that use radioactive isotopes. Its purpose was to review past efforts to develop a risk assessment methodology to evaluate these devices, and to develop a program plan and a scoping document for future methodology development. This report contains presentation material and a transcript of the workshop. Participants included experts in the fields of radiation oncology, medical physics, risk assessment, human-error analysis, and human factors. Staff from the US Nuclear Regulatory Commission (NRC) associated with the regulation of medicalmore » uses of radioactive materials and with research into risk-assessment methods participated in the workshop. The workshop participants concurred in NRC`s intended use of risk assessment as an important technology in the development of regulations for the medical use of radioactive material and encouraged the NRC to proceed rapidly with a pilot study. Specific recommendations are included in the executive summary and the body of this report.« less

Radioactive and other environmental threats to the United States and the Arctic resulting from past Soviet activities

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

NONE

Earlier this year the Senate Intelligence Committee began to receive reports from environmental and nuclear scientists in Russia detailing the reckless nuclear waste disposal practices, nuclear accidents and the use of nuclear detonations. We found that information disturbing to say the least. Also troubling is the fact that 15 Chernobyl style RBMK nuclear power reactors continue to operate in the former Soviet Union today. These reactors lack a containment structure and they`re designed in such a way that nuclear reaction can actually increase when the reactor overheats. As scientists here at the University of Alaska have documented, polar air massesmore » and prevailing weather patterns provide a pathway for radioactive contaminants from Eastern Europe and Western Russia, where many of these reactors are located. The threats presented by those potential radioactive risks are just a part of a larger Arctic pollution problem. Every day, industrial activities of the former Soviet Union continue to create pollutants. I think we should face up to the reality that in a country struggling for economic survival, environment protection isn`t necessarily the high priority. And that could be very troubling news for the Arctic in the future.« less

High-level waste tank farm set point document

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

Anthony, J.A. III

1995-01-15

Setpoints for nuclear safety-related instrumentation are required for actions determined by the design authorization basis. Minimum requirements need to be established for assuring that setpoints are established and held within specified limits. This document establishes the controlling methodology for changing setpoints of all classifications. The instrumentation under consideration involve the transfer, storage, and volume reduction of radioactive liquid waste in the F- and H-Area High-Level Radioactive Waste Tank Farms. The setpoint document will encompass the PROCESS AREA listed in the Safety Analysis Report (SAR) (DPSTSA-200-10 Sup 18) which includes the diversion box HDB-8 facility. In addition to the PROCESS AREASmore » listed in the SAR, Building 299-H and the Effluent Transfer Facility (ETF) are also included in the scope.« less

Low-level liquid radioactive waste treatment at Murmansk, Russia: Technical design and review of facility upgrade and expansion

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

Dyer, R.S.; Diamante, J.M.; Duffey, R.B.

1996-07-01

The governments of Norway and the US have committed their mutual cooperation and support the Murmansk Shipping Company (MSCo) to expand and upgrade the Low-Level Liquid Radioactive Waste (LLRW) treatment system located at the facilities of the Russian company RTP Atomflot, in Murmansk, Russia. RTP Atomflot provides support services to the Russian icebreaker fleet operated by the MSCo. The objective is to enable Russia to permanently cease disposing of this waste in Arctic waters. The proposed modifications will increase the facility`s capacity from 1,200 m{sup 3} per year to 5,000 m{sup 3} per year, will permit the facility to processmore » high-salt wastes from the Russian Navy`s Northern fleet, and will improve the stabilization and interim storage of the processed wastes. The three countries set up a cooperative review of the evolving design information, conducted by a joint US and Norwegian technical team from April through December, 1995. To ensure that US and Norwegian funds produce a final facility which will meet the objectives, this report documents the design as described by Atomflot and the Russian business organization, ASPECT, both in design documents and orally. During the detailed review process, many questions were generated, and many design details developed which are outlined here. The design is based on the adsorption of radionuclides on selected inorganic resins, and desalination and concentration using electromembranes. The US/Norwegian technical team reviewed the available information and recommended that the construction commence; they also recommended that a monitoring program for facility performance be instituted.« less

10 CFR 961.11 - Text of the contract.

Code of Federal Regulations, 2012 CFR

2012-01-01

... characteristic, of a specific or technical nature. It may, for example, document research, experimental... computer software documentation). Examples of technical data include research and engineering data... repository, to take title to the spent nuclear fuel or high-level radioactive waste involved as expeditiously...

10 CFR 961.11 - Text of the contract.

Code of Federal Regulations, 2011 CFR

2011-01-01

... characteristic, of a specific or technical nature. It may, for example, document research, experimental... computer software documentation). Examples of technical data include research and engineering data... repository, to take title to the spent nuclear fuel or high-level radioactive waste involved as expeditiously...

Risk-informed radioactive waste classification and reclassification.

PubMed

Croff, Allen G

2006-11-01

Radioactive waste classification systems have been developed to allow wastes having similar hazards to be grouped for purposes of storage, treatment, packaging, transportation, and/or disposal. As recommended in the National Council on Radiation Protection and Measurements' Report No. 139, Risk-Based Classification of Radioactive and Hazardous Chemical Wastes, a preferred classification system would be based primarily on the health risks to the public that arise from waste disposal and secondarily on other attributes such as the near-term practicalities of managing a waste, i.e., the waste classification system would be risk informed. The current U.S. radioactive waste classification system is not risk informed because key definitions--especially that of high-level waste--are based on the source of the waste instead of its inherent characteristics related to risk. A second important reason for concluding the existing U.S. radioactive waste classification system is not risk informed is there are no general principles or provisions for exempting materials from being classified as radioactive waste which would then allow management without regard to its radioactivity. This paper elaborates the current system for classifying and reclassifying radioactive wastes in the United States, analyzes the extent to which the system is risk informed and the ramifications of its not being so, and provides observations on potential future direction of efforts to address shortcomings in the U.S. radioactive waste classification system as of 2004.

Low-level radioactive waste management handbook series: Low-level radioactive waste management in medical and biomedical research institutions

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

Not Available

1987-03-01

Development of this handbook began in 1982 at the request of the Radhealth Branch of the California Department of Health Services. California Assembly Bill 1513 directed the DHS to ''evaluate the technical and economic feasibility of (1) reducing the volume, reactivity, and chemical and radioactive hazard of (low-level radioactive) waste and (2) substituting nonradioactive or short-lived radioactive materials for those radionuclides which require long-term isolation from the environment. A contract awarded to the University of California at Irvine-UCI (California Std. Agreement 79902), to develop a document focusing on methods for decreasing low-level radioactive waste (LLW) generation in institutions was amore » result of that directive. In early 1985, the US Department of Energy, through EG and G Idaho, Inc., contracted with UCI to expand, update, and revise the California text for national release.« less

77 FR 58416 - Comparative Environmental Evaluation of Alternatives for Handling Low-Level Radioactive Waste...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-09-20

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0218] Comparative Environmental Evaluation of Alternatives... public comment the Draft Comparative Environmental Evaluation of Alternatives for Handling Low-Level.... Availability of Documents ADAMS Accession No. Document title ML12256A965 Draft Comparative Environmental...

40 CFR 141.25 - Analytical methods for radioactivity.

Code of Federal Regulations, 2011 CFR

2011-07-01

... PROGRAMS (CONTINUED) NATIONAL PRIMARY DRINKING WATER REGULATIONS Monitoring and Analytical Requirements... obtaining these documents can be obtained from the Safe Drinking Water Hotline at 800-426-4791. Documents may be inspected at EPA's Drinking Water Docket, EPA West, 1301 Constitution Avenue, NW., Room 3334...

40 CFR 141.25 - Analytical methods for radioactivity.

Code of Federal Regulations, 2010 CFR

2010-07-01

... PROGRAMS (CONTINUED) NATIONAL PRIMARY DRINKING WATER REGULATIONS Monitoring and Analytical Requirements... obtaining these documents can be obtained from the Safe Drinking Water Hotline at 800-426-4791. Documents may be inspected at EPA's Drinking Water Docket, EPA West, 1301 Constitution Avenue, NW., Room 3334...

40 CFR 141.25 - Analytical methods for radioactivity.

Code of Federal Regulations, 2013 CFR

2013-07-01

... PROGRAMS (CONTINUED) NATIONAL PRIMARY DRINKING WATER REGULATIONS Monitoring and Analytical Requirements... obtaining these documents can be obtained from the Safe Drinking Water Hotline at 800-426-4791. Documents may be inspected at EPA's Drinking Water Docket, EPA West, 1301 Constitution Avenue, NW., Room 3334...

40 CFR 141.25 - Analytical methods for radioactivity.

Code of Federal Regulations, 2014 CFR

2014-07-01

... PROGRAMS (CONTINUED) NATIONAL PRIMARY DRINKING WATER REGULATIONS Monitoring and Analytical Requirements... obtaining these documents can be obtained from the Safe Drinking Water Hotline at 800-426-4791. Documents may be inspected at EPA's Drinking Water Docket, EPA West, 1301 Constitution Avenue, NW., Room 3334...

NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA, JUNE 2006

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

U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal.

Nevada Test Site Waste Acceptance Criteria

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

U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal.

Review of nuclear pharmacy practice in hospitals

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

Kawada, T.K.; Tubis, M.; Ebenkamp, T.

1982-02-01

An operational profile for nuclear pharmacy practice is presented, and the technical and professional role of nuclear pharmacists is reviewed. Key aspects of nuclear pharmacy practice in hospitals discussed are the basic facilities and equipment for the preparation, quality control, and distribution of radioactive drug products. Standards for receiving, storing, and processing radioactive material are described. The elements of a radiopharmaceutical quality assurance program, including the working procedures, documentation systems, data analysis, and specific control tests, are presented. Details of dose preparation and administration and systems of inventory control for radioactive products are outlined.

[Problems of safety regulation under radioactive waste management in Russia].

PubMed

Monastyrskaia, S G; Kochetkov, O A; Barchukov, V G; Kuznetsova, L I

2012-01-01

Analysis of the requirements of Federal Law N 190 "About radioactive waste management and incorporation of changes into some legislative acts of the Russian Federation", as well as normative-legislative documents actual and planned to be published related to provision of radiation protection of the workers and the public have been done. Problems of safety regulation raised due to different approaches of Rospotrebnadzor, FMBA of Russia, Rostekhnadzor and Minprirody with respect to classification and categorization of the radioactive wastes, disposal, exemption from regulatory control, etc. have been discussed in the paper. Proposals regarding improvement of the system of safety regulation under radioactive waste management and of cooperation of various regulatory bodies have been formulated.

Multiple criteria approach to site selection of radioactive waste disposal facility in the Republic of Croatia

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

Schaller, A.; Skanata, D.

1995-12-31

Site selection approach to radioactive waste disposal facility, which is under way in Croatia, is presented in the paper. This approach is based on application of certain relevant terrestrial and technical criteria in the site selection process. Basic documentation used for this purpose are regional planning documents prepared by the Regional Planning Institute of Croatia. The basic result of research described in the paper is the proposal of several potential areas which are suitable for siting a radioactive waste repository. All relevant conclusions are based on both data groups -- generic and on-field experienced (measured). Out of a dozen potentialmore » areas, four have been chosen as representative by the authors. The presented comparative analysis was made by means of the VISA II computer code, developed by the V. Belton and SPV Software Products. The code was donated to the APO by the IAEA. The main objective of the paper is to initiate and facilitate further discussions on possible ways of evaluation and comparison of potential areas for sitting of radioactive waste repository in this country, as well as to provide additional contributions to the current site selection process in the Republic of Croatia.« less

76 FR 41241 - Proposed Agency Information Collection

Federal Register 2010, 2011, 2012, 2013, 2014

2011-07-13

... Material.'' The CoC defines the packaging, radioactive material content, and transportation restrictions... Radioactive Materials Packages; (3) Type of Request: New; (4) Purpose: This information collection is in... approved a radioactive material package as meeting the applicable safety standards [[Page 41242

Repository of not readily available documents for project W-320

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

Conner, J.C.

1997-04-18

The purpose of this document is to provide a readily available source of the technical reports needed for the development of the safety documentation provided for the waste retrieval sluicing system (WRSS), designed to remove the radioactive and chemical sludge from tank 241-C-106, and transport that material to double-shell tank 241-AY-102 via a new, temporary, shielded, encased transfer line.

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM - 2011

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

West, B.; Waltz, R.

2012-06-21

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2011 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2011 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per SRR-LWE-2011-00026, HLW Tank Farm Inspection Plan for 2011, were completed. Ultrasonic measurements (UT) performed in 2011 met the requirements of C-ESR-G-00006, In-Service Inspection Program for Highmore » Level Waste Tanks, Rev. 3, and WSRC-TR-2002-00061, Rev.6. UT inspections were performed on Tanks 25, 26 and 34 and the findings are documented in SRNL-STI-2011-00495, Tank Inspection NDE Results for Fiscal Year 2011, Waste Tanks 25, 26, 34 and 41. A total of 5813 photographs were made and 835 visual and video inspections were performed during 2011. A potential leaksite was discovered at Tank 4 during routine annual inspections performed in 2011. The new crack, which is above the allowable fill level, resulted in no release to the environment or tank annulus. The location of the crack is documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.6.« less

Proceedings of the 6th US/German Workshop on Salt Repository Research, Design, and Operation

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

Hansen, Francis D.; Walter Steininger; Wilhelm Bollingerfehr

The 6th US/German Workshop on Salt Repository Research, Design, and Operation was held in Dresden. Germany on September 7-9, 2015. Over seventy participants helped advance the technical basis for salt disposal of radioactive waste. The number of collaborative efforts continues to grow and to produce useful documentation, as well as to define the state of the art for research areas. These Proceedings are divided into Chapters, and a list of authors is included in the Acknowledgement Section. Also in this document are the Technical Agenda, List of Participants, Biographical Information, Abstracts, and Presentations. Proceedings of all workshops and other pertinentmore » information are posted on websites hosted by Sandia National Laboratories and the Nuclear Energy Agency Salt Club. The US/German workshops provide continuity for long-term research, summarize and publish status of mature areas, and develop appropriate research by consensus in a workshop environment. As before, major areas and findings are highlighted, which constitute topical Chapters in these Proceedings. In total, the scientific breadth is substantial and while not all subject matter is elaborated into chapter format, all presentations and abstracts are published in this document. In the following Proceedings, six selected topics are developed in detail.« less

Low-Level Waste Regulation: Putting Principles Into Practice - 13297 - The Richard S. Hodes, M.D., Honor Lecture Award

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

Kennedy, James E.

2013-07-01

In carrying out its mission to ensure the safe use of radioactive materials for beneficial civilian purposes while protecting people and the environment, the U.S. Nuclear Regulatory Commission (NRC) adheres to its Principles of Good Regulation. The Principles-Independence, Openness, Efficiency, Clarity, and Reliability-apply to the agency as a whole in its decision-making and to the individual conduct of NRC employees. This paper describes the application of the Principles in a real-life staff activity, a guidance document used in the NRC's low-level radioactive waste (LLW) program, the Concentration Averaging and Encapsulation Branch Technical Position (CA BTP). The staff's process to revisemore » the document, as well as the final content of the document, were influenced by following the Principles. For example, consistent with the Openness Principle, the staff conducted a number of outreach activities and received many comments on three drafts of the document. Stakeholder comments affected the final staff positions in some cases. The revised CA BTP, once implemented, is expected to improve management and disposal of LLW in the United States. Its positions have an improved nexus to health and safety; are more performance-based than previously, thus providing licensees with options for how they achieve the required outcome of protecting an inadvertent human intruder into a disposal facility; and provide for disposal of more sealed radioactive sources, which are a potential threat to national security. (author)« less

Spent Nuclear Fuel Trasportation: An Examination of Potential Lessons Learned From Prior Shipping Campaigns

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

M. Keister; K, McBride

The Nuclear Waste Policy Act of 1982 (NWPA), as amended, assigned the Department of Energy (DOE) responsibility for developing and managing a Federal system for the disposal of spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for accepting, transporting, and disposing of SNF and HLW at the Yucca Mountain repository (if licensed) in a manner that protects public health, safety, and the environment; enhances national and energy security; and merits public confidence. OCRWM faces a near-term challenge--to develop and demonstrate a transportation system that will sustain safe and efficientmore » shipments of SNF and HLW to a repository. To better inform and improve its current planning, OCRWM has extensively reviewed plans and other documents related to past high-visibility shipping campaigns of SNF and other radioactive materials within the United States. This report summarizes the results of this review and, where appropriate, lessons learned. The objective of this lessons learned study was to identify successful, best-in-class trends and commonalities from past shipping campaigns, which OCRWM could consider when planning for the development and operation of a repository transportation system. Note: this paper is for analytical and discussion purposes only, and is not an endorsement of, or commitment by, OCRWM to follow any of the comments or trends. If OCRWM elects to make such commitments at a future time, they will be appropriately documented in formal programmatic policy statements, plans and procedures. Reviewers examined an extensive study completed in 2003 by DOE's National Transportation Program (NTP), Office of Environmental Management (EM), as well as plans and documents related to SNF shipments since issuance of the NTP report. OCRWM examined specific planning, business, institutional and operating practices that have been identified by DOE, its transportation contractors, and stakeholders as important issues that arise repeatedly. In addition, the review identifies lessons learned or activities/actions which were found not to be productive to the planning and conduct of SNF shipments (i.e., negative impacts). This paper is a 'looking back' summary of lessons learned across multiple transportation campaigns. Not all lessons learned are captured here, and participants in some of the campaigns have divergent opinions and perspectives about which lessons are most critical. This analysis is part of a larger OCRWM benchmarking effort to identify best practices to consider in future transportation of radioactive materials ('looking forward'). Initial findings from this comprehensive benchmarking analysis are expected to be available in late fall 2006.« less

Knowledge Management Initiatives Used to Maintain Regulatory Expertise in Transportation and Storage of Radioactive Materials - 12177

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

Lindsay, Haile; Garcia-Santos, Norma; Saverot, Pierre

2012-07-01

The U.S. Nuclear Regulatory Commission (NRC) was established in 1974 with the mission to license and regulate the civilian use of nuclear materials for commercial, industrial, academic, and medical uses in order to protect public health and safety, and the environment, and promote the common defense and security. Currently, approximately half (∼49%) of the workforce at the NRC has been with the Agency for less than six years. As part of the Agency's mission, the NRC has partial responsibility for the oversight of the transportation and storage of radioactive materials. The NRC has experienced a significant level of expertise leavingmore » the Agency due to staff attrition. Factors that contribute to this attrition include retirement of the experienced nuclear workforce and mobility of staff within or outside the Agency. Several knowledge management (KM) initiatives have been implemented within the Agency, with one of them including the formation of a Division of Spent Fuel Storage and Transportation (SFST) KM team. The team, which was formed in the fall of 2008, facilitates capturing, transferring, and documenting regulatory knowledge for staff to effectively perform their safety oversight of transportation and storage of radioactive materials, regulated under Title 10 of the Code of Federal Regulations (10 CFR) Part 71 and Part 72. In terms of KM, the SFST goal is to share critical information among the staff to reduce the impact from staff's mobility and attrition. KM strategies in place to achieve this goal are: (1) development of communities of practice (CoP) (SFST Qualification Journal and the Packaging and Storing Radioactive Material) in the on-line NRC Knowledge Center (NKC); (2) implementation of a SFST seminar program where the seminars are recorded and placed in the Agency's repository, Agency-wide Documents Access and Management System (ADAMS); (3) meeting of technical discipline group programs to share knowledge within specialty areas; (4) development of written guidance to capture 'administrative and technical' knowledge (e.g., office instructions (OIs), generic communications (e.g., bulletins, generic letters, regulatory issue summary), standard review plans (SRPs), interim staff guidance (ISGs)); (5) use of mentoring strategies for experienced staff to train new staff members; (6) use of Microsoft SharePoint portals in capturing, transferring, and documenting knowledge for staff across the Division from Division management and administrative assistants to the project managers, inspectors, and technical reviewers; and (7) development and implementation of a Division KM Plan. A discussion and description of the successes and challenges of implementing these KM strategies at the NRC/SFST will be provided. (authors)« less

[The main directions of improving the system of state accounting and control of radioactive substances and radioactive waste products].

PubMed

2012-01-01

This paper describes a modification of the basic directions of state accounting and control of radioactive substances and radioactive waste products, whose implementation will significantly improve the efficiency of its operation at the regional level. Selected areas are designed to improve accounting and control system for the submission of the enterprises established by the reporting forms, the quality of the information contained in them, as well as structures of information and process for collecting, analyzing and data processing concerning radioactive substances and waste products.

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

Not Available

Routine monitoring and sampling for radiation, radioactive materials, and chemical substances on and off the Oak Ridge Reservation are used to document compliance with appropriate standards, identify undesirable trends, provide information for the public, and contribute to general environmental knowledge. Regional stations located at distances of up to 140 km (90 miles) from the ORR provide a basis for determining conditions beyond the range of potential influence of the three Oak Ridge installations. Stations within the Reservation, around the perimeters and within each plant site, and in residential and community areas document conditions in areas occupied and visited by themore » public and potentially affected by the Oak Ridge operations. In all, during 1985 some 115,000 analyses of environmental samples were completed as part of the Reservation-wide and regional monitoring program. Included were approxiately 61,000 air, 41,000 surface water, 8090 groundwater, 2400 wastewater, 80 fish, 231 soil, 132 grass, 36 pine needle, 360 sediment, and 80 external gamma analyses.« less

Waste treatability guidance program. User`s guide. Revision 0

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

Toth, C.

1995-12-21

DOE sites across the country generate and manage radioactive, hazardous, mixed, and sanitary wastes. It is necessary for each site to find the technologies and associated capacities required to manage its waste. One role of DOE HQ Office of Environmental Restoration and Waste Management is to facilitate the integration of the site- specific plans into coherent national plans. DOE has developed a standard methodology for defining and categorizing waste streams into treatability groups based on characteristic parameters that influence waste management technology needs. This Waste Treatability Guidance Program automates the Guidance Document for the categorization of waste information into treatabilitymore » groups; this application provides a consistent implementation of the methodology across the National TRU Program. This User`s Guide provides instructions on how to use the program, including installations instructions and program operation. This document satisfies the requirements of the Software Quality Assurance Plan.« less

NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA

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

U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION, NEVADA SITE OFFICE

This document establishes the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal. Mixed waste generated within the State of Nevada by NNSA/NSO activities is accepted for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Site for storage or disposal.

Documentation of the Ecological Risk Assessment Computer Model ECORSK.5

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

Anthony F. Gallegos; Gilbert J. Gonzales

1999-06-01

The FORTRAN77 ecological risk computer model--ECORSK.5--has been used to estimate the potential toxicity of surficial deposits of radioactive and non-radioactive contaminants to several threatened and endangered (T and E) species at the Los Alamos National Laboratory (LANL). These analyses to date include preliminary toxicity estimates for the Mexican spotted owl, the American peregrine falcon, the bald eagle, and the southwestern willow flycatcher. This work has been performed as required for the Record of Decision for the construction of the Dual Axis Radiographic Hydrodynamic Test (DARHT) Facility at LANL as part of the Environmental Impact Statement. The model is dependent onmore » the use of the geographic information system and associated software--ARC/INFO--and has been used in conjunction with LANL's Facility for Information Management and Display (FIMAD) contaminant database. The integration of FIMAD data and ARC/INFO using ECORSK.5 allows the generation of spatial information from a gridded area of potential exposure called an Ecological Exposure Unit. ECORSK.5 was used to simulate exposures using a modified Environmental Protection Agency Quotient Method. The model can handle a large number of contaminants within the home range of T and E species. This integration results in the production of hazard indices which, when compared to risk evaluation criteria, estimate the potential for impact from consumption of contaminants in food and ingestion of soil. The assessment is considered a Tier-2 type of analysis. This report summarizes and documents the ECORSK.5 code, the mathematical models used in the development of ECORSK.5, and the input and other requirements for its operation. Other auxiliary FORTRAN 77 codes used for processing and graphing output from ECORSK.5 are also discussed. The reader may refer to reports cited in the introduction to obtain greater detail on past applications of ECORSK.5 and assumptions used in deriving model parameters.« less

Geochemical Data Package for Performance Assessment Calculations Related to the Savannah River Site

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

Kaplan, Daniel I.

The Savannah River Site (SRS) disposes of low-level radioactive waste (LLW) and stabilizes high-level radioactive waste (HLW) tanks in the subsurface environment. Calculations used to establish the radiological limits of these facilities are referred to as Performance Assessments (PA), Special Analyses (SA), and Composite Analyses (CA). The objective of this document is to revise existing geochemical input values used for these calculations. This work builds on earlier compilations of geochemical data (2007, 2010), referred to a geochemical data packages. This work is being conducted as part of the on-going maintenance program of the SRS PA programs that periodically updates calculationsmore » and data packages when new information becomes available. Because application of values without full understanding of their original purpose may lead to misuse, this document also provides the geochemical conceptual model, the approach used for selecting the values, the justification for selecting data, and the assumptions made to assure that the conceptual and numerical geochemical models are reasonably conservative (i.e., bias the recommended input values to reflect conditions that will tend to predict the maximum risk to the hypothetical recipient). This document provides 1088 input parameters for geochemical parameters describing transport processes for 64 elements (>740 radioisotopes) potentially occurring within eight subsurface disposal or tank closure areas: Slit Trenches (ST), Engineered Trenches (ET), Low Activity Waste Vault (LAWV), Intermediate Level (ILV) Vaults, Naval Reactor Component Disposal Areas (NRCDA), Components-in-Grout (CIG) Trenches, Saltstone Facility, and Closed Liquid Waste Tanks. The geochemical parameters described here are the distribution coefficient, Kd value, apparent solubility concentration, k s value, and the cementitious leachate impact factor.« less

Cigarette smoke radioactivity and lung cancer risk.

PubMed

Karagueuzian, Hrayr S; White, Celia; Sayre, James; Norman, Amos

2012-01-01

To determine the tobacco industry's policy and action with respect to radioactive polonium 210 ((210)Po) in cigarette smoke and to assess the long-term risk of lung cancer caused by alpha particle deposits in the lungs of regular smokers. Analysis of major tobacco industries' internal secret documents on cigarette radioactivity made available online by the Master Settlement Agreement in 1998. The documents show that the industry was well aware of the presence of a radioactive substance in tobacco as early as 1959. Furthermore, the industry was not only cognizant of the potential "cancerous growth" in the lungs of regular smokers but also did quantitative radiobiological calculations to estimate the long-term (25 years) lung radiation absorption dose (rad) of ionizing alpha particles emitted from the cigarette smoke. Our own calculations of lung rad of alpha particles match closely the rad estimated by the industry. According to the Environmental Protection Agency, the industry's and our estimate of long-term lung rad of alpha particles causes 120-138 lung cancer deaths per year per 1,000 regular smokers. Acid wash was discovered in 1980 to be highly effectively in removing (210)Po from the tobacco leaves; however, the industry avoided its use for concerns that acid media would ionize nicotine converting it into a poorly absorbable form into the brain of smokers thus depriving them of the much sought after instant "nicotine kick" sensation. The evidence of lung cancer risk caused by cigarette smoke radioactivity is compelling enough to warrant its removal.

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

Workplan/RCRA Facility Investigation/Remedial Investigation Report for the Old Radioactive Waste Burial Ground 643-E, S01-S22 - Volume I - Text and Volume II - Appendices

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

Conner, K.R.

This document presents the assessment of environmental impacts resulting from releases of hazardous substances from the facilities in the Old Radioactive Waste Burial Ground 643-E, including Solvent Tanks 650-01E to 650-22E, also referred to as Solvent Tanks at the Savannah River Site, Aiken, South Carolina.

Groundwater Data Package for Hanford Assessments

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

Thorne, Paul D.; Bergeron, Marcel P.; Williams, Mark D.

2006-01-31

This report presents data and interpreted information that supports the groundwater module of the System Assessment Capability (SAC) used in Hanford Assessments. The objective of the groundwater module is to predict movement of radioactive and chemical contaminants through the aquifer to the Columbia River or other potential discharge locations. This data package is being revised as part of the deliverables under the Characterization of Systems Project (#49139) aimed at providing documentation for assessments being conducted under the Hanford Assessments Project (#47042). Both of these projects are components of the Groundwater Remediation and Closure Assessments Projects, managed by the Management andmore » Integration Project (#47043).« less

Tanks Focus Area site needs assessment FY 1998

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

NONE

This report documents the process used by the Tanks Focus Area (TFA) to analyze and develop responses to technology needs submitted by four major US Department of Energy (DOE) sites with radioactive tank waste problems, and the initial results of the analysis. The sites are the Hanford Site, Idaho National Engineering and Environmental Laboratory (INEEL), Oak Ridge Reservation (ORR), and Savannah River Site (SRS). This document describes the TFA`s process of collecting site needs, analyzing them, and creating technical responses to the sites. It also summarizes the information contained within the TFA needs database, portraying information provided by four majormore » DOE sites with tank waste problems. The overall TFA program objective is to deliver a tank technology program that reduces the current cost, and the operational and safety risks of tank remediation. The TFA`s continues to enjoy close, cooperative relationships with each site. During the past year, the TFA has fostered exchanges of technical information between sites. These exchanges have proven to be healthy for all concerned. The TFA recognizes that site technology needs often change, and the TFA must be prepared not only to amend its program in response, but to help the sites arrive at the best technical approach to solve revised site needs.« less

Data Collection Handbook to Support Modeling Impacts of Radioactive Material in Soil and Building Structures

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

Yu, Charley; Kamboj, Sunita; Wang, Cheng

2015-09-01

This handbook is an update of the 1993 version of the Data Collection Handbook and the Radionuclide Transfer Factors Report to support modeling the impact of radioactive material in soil. Many new parameters have been added to the RESRAD Family of Codes, and new measurement methodologies are available. A detailed review of available parameter databases was conducted in preparation of this new handbook. This handbook is a companion document to the user manuals when using the RESRAD (onsite) and RESRAD-OFFSITE code. It can also be used for RESRAD-BUILD code because some of the building-related parameters are included in this handbook.more » The RESRAD (onsite) has been developed for implementing U.S. Department of Energy Residual Radioactive Material Guidelines. Hydrogeological, meteorological, geochemical, geometrical (size, area, depth), crops and livestock, human intake, source characteristic, and building characteristic parameters are used in the RESRAD (onsite) code. The RESRAD-OFFSITE code is an extension of the RESRAD (onsite) code and can also model the transport of radionuclides to locations outside the footprint of the primary contamination. This handbook discusses parameter definitions, typical ranges, variations, and measurement methodologies. It also provides references for sources of additional information. Although this handbook was developed primarily to support the application of RESRAD Family of Codes, the discussions and values are valid for use of other pathway analysis models and codes.« less

Data Quality Objectives Supporting Radiological Air Emissions Monitoring for the PNNL Richland Campus

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

Snyder, Sandra F.; Moleta, Donna Grace L.; Meier, Kirsten M.

This is the second revision of the DQO Supporting Radiological Air Emissions Monitoring for the Pacific Northwest National Laboratory Richland Campus. In January 2017, the PNNL Richland Campus expanded to the north by 0.35 km 2 (85.6 acres). Under the requirements of Washington State Department of Health Radioactive Air Emissions License (RAEL)-005, the PNNL Campus operates and maintains a radiological air monitoring program. This revision documents and evaluates the newly acquired acreage while also removing recreational land at the southwest, and also re-examines all active radioactive emission units on the PNNL Campus. No buildings are located on this new Campusmore » land, which was transferred from the U.S. DOE Hanford Site. Additionally, this revision includes information regarding the background monitoring station PNL-5 in Benton City, Washington, which became active in October 2016. The key purpose of this revision is to determine the adequacy of the existing environmental surveillance stations to monitor radiological air emissions in light of this northern boundary change.« less

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

Not Available

The Southern States Energy Board (SSEB) is an interstate compact organization that serves 16 states and the commonwealth of Puerto Rico with information and analysis in energy and environmental matters. Nuclear waste management is a topic that has garnered considerable attention in the SSEB region in the last several years. Since 1985, SSEB has received support from the US Department of Energy for the regional analysis of high-level radioactive waste transportation issues. In the performance of its work in this area, SSEB formed the Advisory Committee on High-Level Radioactive Materials Transportation, which comprises representatives from impacted states and tribes. SSEBmore » meets with the committee semi-annually to provide issue updates to members and to solicit their views on activities impacting their respective states. Among the waste transportation issues considered by SSEB and the committee are shipment routing, the impacts of monitored retrievable storage, state liability in the event of an accident and emergency preparedness and response. This document addresses the latter by describing the radiological emergency response training courses and programs of the southern states, as well as federal courses available outside the southern region.« less

Inventory Data Package for Hanford Assessments

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

Kincaid, Charles T.; Eslinger, Paul W.; Aaberg, Rosanne L.

2006-06-01

This document presents the basis for a compilation of inventory for radioactive contaminants of interest by year for all potentially impactive waste sites on the Hanford Site for which inventory data exist in records or could be reasonably estimated. This document also includes discussions of the historical, current, and reasonably foreseeable (1944 to 2070) future radioactive waste and waste sites; the inventories of radionuclides that may have a potential for environmental impacts; a description of the method(s) for estimating inventories where records are inadequate; a description of the screening method(s) used to select those sites and contaminants that might makemore » a substantial contribution to impacts; a listing of the remedial actions and their completion dates for waste sites; and tables showing the best estimate inventories available for Hanford assessments.« less

Viscous Particle Breakup within a Cooling Nuclear Fireball

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

Wilkinson, J. T.; Knight, K. B.; Dai, Z.

2016-10-04

Following the surface detonation of a nuclear weapon, the Earth’s crust and immediate surroundings are drawn into the fireball and form melts. Fallout is formed as these melts incorporate radioactive material from the bomb vapor and cool rapidly. The resultant fallout plume and dispersion of radioactive contamination is a function of several factors including weather patterns and fallout particle shapes and size distributions. Accurate modeling of the size distributions of fallout forms an important data point for dispersion codes that calculate the aerial distribution of fallout. While morphological evidence for aggregation of molten droplets is well documented in fallout glassmore » populations, the breakup of these molten droplets has not been similarly studied. This study documents evidence that quenched fallout populations preserve evidence of molten breakup mechanisms.« less

Deep Borehole Field Test Requirements and Controlled Assumptions.

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

Hardin, Ernest

2015-07-01

This document presents design requirements and controlled assumptions intended for use in the engineering development and testing of: 1) prototype packages for radioactive waste disposal in deep boreholes; 2) a waste package surface handling system; and 3) a subsurface system for emplacing and retrieving packages in deep boreholes. Engineering development and testing is being performed as part of the Deep Borehole Field Test (DBFT; SNL 2014a). This document presents parallel sets of requirements for a waste disposal system and for the DBFT, showing the close relationship. In addition to design, it will also inform planning for drilling, construction, and scientificmore » characterization activities for the DBFT. The information presented here follows typical preparations for engineering design. It includes functional and operating requirements for handling and emplacement/retrieval equipment, waste package design and emplacement requirements, borehole construction requirements, sealing requirements, and performance criteria. Assumptions are included where they could impact engineering design. Design solutions are avoided in the requirements discussion. Deep Borehole Field Test Requirements and Controlled Assumptions July 21, 2015 iv ACKNOWLEDGEMENTS This set of requirements and assumptions has benefited greatly from reviews by Gordon Appel, Geoff Freeze, Kris Kuhlman, Bob MacKinnon, Steve Pye, David Sassani, Dave Sevougian, and Jiann Su.« less

Characterization, monitoring, and sensor technology catalogue

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

Matalucci, R.V.; Esparza-Baca, C.; Jimenez, R.D.

1995-12-01

This document represents a summary of 58 technologies that are being developed by the Department of Energy`s (DOE`s) Office of Science and Technology (OST) to provide site, waste, and process characterization and monitoring solutions to the DOE weapons complex. The information was compiled to provide performance data on OST-developed technologies to scientists and engineers responsible for preparing Remedial Investigation/Feasibility Studies (RI/FSs) and preparing plans and compliance documents for DOE cleanup and waste management programs. The information may also be used to identify opportunities for partnering and commercialization with industry, DOE laboratories, other federal and state agencies, and the academic community.more » Each technology is featured in a format that provides: (1) a description, (2) technical performance data, (3) applicability, (4) development status, (5) regulatory considerations, (6) potential commercial applications, (7) intellectual property, and (8) points-of-contact. Technologies are categorized into the following areas: (1) Bioremediation Monitoring, (2) Decontamination and Decommissioning, (3) Field Analytical Laboratories, (4) Geophysical and Hydrologic Characterization, (5) Hazardous Inorganic Contaminant Analysis, (6) Hazardous Organic Contaminant Analysis, (7) Mixed Waste, (8) Radioactive Contaminant Analysis, (9) Remote Sensing,(10)Sampling and Drilling, (11) Statistically Guided Sampling, and (12) Tank Waste.« less

Los Alamos National Laboratory emergency management plan. Revision 1

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

Ramsey, G.F.

1998-07-15

The Laboratory has developed this Emergency Management Plan (EMP) to assist in emergency planning, preparedness, and response to anticipated and actual emergencies. The Plan establishes guidance for ensuring safe Laboratory operation, protection of the environment, and safeguarding Department of Energy (DOE) property. Detailed information and specific instructions required by emergency response personnel to implement the EMP are contained in the Emergency Management Plan Implementing Procedure (EMPIP) document, which consists of individual EMPIPs. The EMP and EMPIPs may be used to assist in resolving emergencies including but not limited to fires, high-energy accidents, hazardous material releases (radioactive and nonradioactive), security incidents,more » transportation accidents, electrical accidents, and natural disasters.« less

Handbook explaining the fundamentals of nuclear and atomic physics

NASA Technical Reports Server (NTRS)

Hanlen, D. F.; Morse, W. J.

1969-01-01

Indoctrination document presents nuclear, reactor, and atomic physics in an easy, straightforward manner. The entire subject of nuclear physics including atomic structure ionization, isotopes, radioactivity, and reactor dynamics is discussed.

Development of a reliable estimation procedure of radioactivity inventory in a BWR plant due to neutron irradiation for decommissioning

NASA Astrophysics Data System (ADS)

Tanaka, Ken-ichi; Ueno, Jun

2017-09-01

Reliable information of radioactivity inventory resulted from the radiological characterization is important in order to plan decommissioning planning and is also crucial in order to promote decommissioning in effectiveness and in safe. The information is referred to by planning of decommissioning strategy and by an application to regulator. Reliable information of radioactivity inventory can be used to optimize the decommissioning processes. In order to perform the radiological characterization reliably, we improved a procedure of an evaluation of neutron-activated materials for a Boiling Water Reactor (BWR). Neutron-activated materials are calculated with calculation codes and their validity should be verified with measurements. The evaluation of neutron-activated materials can be divided into two processes. One is a distribution calculation of neutron-flux. Another is an activation calculation of materials. The distribution calculation of neutron-flux is performed with neutron transport calculation codes with appropriate cross section library to simulate neutron transport phenomena well. Using the distribution of neutron-flux, we perform distribution calculations of radioactivity concentration. We also estimate a time dependent distribution of radioactivity classification and a radioactive-waste classification. The information obtained from the evaluation is utilized by other tasks in the preparatory tasks to make the decommissioning plan and the activity safe and rational.

Waking a sleeping giant: the tobacco industry's response to the polonium-210 issue.

PubMed

Muggli, Monique E; Ebbert, Jon O; Robertson, Channing; Hurt, Richard D

2008-09-01

The major tobacco manufacturers discovered that polonium was part of tobacco and tobacco smoke more than 40 years ago and attempted, but failed, to remove this radioactive substance from their products. Internal tobacco industry documents reveal that the companies suppressed publication of their own internal research to avoid heightening the public's awareness of radioactivity in cigarettes. Tobacco companies continue to minimize their knowledge about polonium-210 in cigarettes in smoking and health litigation. Cigarette packs should carry a radiation-exposure warning label.

Composite analysis E-area vaults and saltstone disposal facilities

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

Cook, J.R.

1997-09-01

This report documents the Composite Analysis (CA) performed on the two active Savannah River Site (SRS) low-level radioactive waste (LLW) disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults (EAV) Disposal Facility. The analysis calculated potential releases to the environment from all sources of residual radioactive material expected to remain in the General Separations Area (GSA). The GSA is the central part of SRS and contains all of the waste disposal facilities, chemical separations facilities and associated high-level waste storage facilities as well as numerous other sources of radioactive material. The analysis considered 114 potentialmore » sources of radioactive material containing 115 radionuclides. The results of the CA clearly indicate that continued disposal of low-level waste in the saltstone and EAV facilities, consistent with their respective radiological performance assessments, will have no adverse impact on future members of the public.« less

Geoscience parameter data base handbook: granites and basalts

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

Not Available

1979-12-01

The Department of Energy has the responsibility for selecting and constructing Federal repositories for radioactive waste. The Nuclear Regulatory Commission must license such repositories prior to construction. The basic requirement in the geologic disposal of radioactive waste is stated as: placement in a geologic host whereby the radioactive waste is not in mechanical, thermal or chemical equilibrium with the object of preventing physical or chemical migration of radionuclides into the biosphere or hydrosphere in hazardous concentration (USGS, 1977). The object of this report is to document the known geologic parameters of large granite and basalt occurrences in the coterminous Unitedmore » States, for future evaluation in the selection and licensing of radioactive waste repositories. The description of the characteristics of certain potential igneous hosts has been limited to existing data pertaining to the general geologic character, geomechanics, and hydrology of identified occurrences. A description of the geochemistry is the subject of a separate report.« less

Mineral resource potential map of the Bighorn Mountains Wilderness Study Area (CDCA-217), San Bernardino County, California

USGS Publications Warehouse

Matti, Jonathan C.; Cox, Brett F.; Rodriguez, Eduardo A.; Obi, Curtis M.; Powell, Robert E.; Hinkle, Margaret E.; Griscom, Andrew; Sabine, Charles; Cwick, Gary J.

1982-01-01

Geological, geochemical, and geophysical evidence, together with a review of historical mining and prospecting activities, suggests that most of the Bighorn Mountains Wilderness Study Area has low potential for the discovery of all types of mineral and energy resources-including precious and base metals, building stone and aggregate, fossil fuels, radioactive-mineral resources, and geothermal resources. Low-grade mineralization has been documented in one small area near Rattlesnake Canyon, and this area has low to moderate potential for future small-scale exploration and development of precious and base metals. Thorium and uranium enrichment have been documented in two small areas in the eastern part of the wilderness study area; these two areas have low to moderate potential for future small-scale exploration and development of radioactive-mineral resources.

Radioactive waste management and practice in Bangladesh

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

Mollah, A.S.; Rahman, M.M.

1993-12-31

A large amount of low- and medium-level radioactive wastes are being generated in different parts of Bangladesh. The solid wastes are being collected in steel containers and liquid wastes are collected in plastic carboys and drums. Gaseous Ar-41 is discharged into the atmosphere through the 25 m height stack under controlled conditions after proper monitoring. The solid radioactive wastes collected are approximately 5 m{sup 3} (1988--1992) with gross beta-gamma surface dose rates from 0.30 {micro}Sv/h to 250 {micro}Sv/h. The liquid radioactive wastes are approximately 200 liters (1988--1992) with gross-beta-gamma surface dose rates from 0.30 {micro}Sv/h to 1 mSv/h. The solidmore » and liquid wastes presently being collected are mostly short lived and low level and safely stored according to international safety codes of practice. Radioactive waste packages collected during the 5-yrs study totaled 16, representing a collective volume of {approximately} 7.5 m{sup 3}. The problem of management of radioactive waste in Bangladesh is not so serious at present because the wastes arising are small now. A computerized data base has been developed to document inventory of all radioactive waste arising in the country. The current practices of collection, handling, safe storage and management of the radioactive wastes are reported in this paper.« less

Integrated data base report--1996: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

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

NONE

1997-12-01

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and commercial and U.S. government-owned radioactive wastes. Inventories of most of these materials are reported as of the end of fiscal year (FY) 1996, which is September 30, 1996. Commercial SNF and commercial uranium mill tailings inventories are reported on an end-of-calendar year (CY) basis. All SNF and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecastedmore » is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are SNF, high-level waste, transuranic waste, low-level waste, uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, naturally occurring and accelerator-produced radioactive material, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through FY 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.« less

Hanford Site annual dangerous waste report: Volume 2, Generator dangerous waste report, radioactive mixed waste

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

NONE

1994-12-31

This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, waste designation, weight, and waste designation.

LANL Environmental ALARA Program Status Report for CY 2016

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

Whicker, Jeffrey Jay; Mcnaughton, Michael; Ruedig, Elizabeth

2017-02-24

Los Alamos National Laboratory (LANL) ensures that radiation exposures to members of the public and the environment from LANL operations, past and present, are below regulatory thresholds and are as low as reasonably achievable (ALARA) through compliance with DOE Order 458.1 Radiation Protection for the Public and the Environment, and LANL Policy 412 Environmental Radiation Protection (LANL2016a). In 2007, a finding (RL.2-F-1) and observation (RL.2-0-1) in the NNSA/ LASO report, September 2007, Release of Property (Land) Containing Residual Radioactive Material Self-Assessment Report, indicated that LANL had no policy or documented process in place for the release of property containing residualmore » radioactive material. In response, LANL developed PD410, Los Alamos National Laboratory Environmental ALARA Program. The most recent version of this document became effective in 2014 (LANL 2014a). The document provides program authorities, responsibilities, descriptions, processes, and thresholds for conducting qualitative and quantitative ALARA analyses for prospective and actual radiation exposures to the public and t o the environment resulting from DOE activities conducted on the LANL site.« less

Initial Radionuclide Inventories

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

Miller, H

The purpose of this analysis is to provide an initial radionuclide inventory (in grams per waste package) and associated uncertainty distributions for use in the Total System Performance Assessment for the License Application (TSPA-LA) in support of the license application for the repository at Yucca Mountain, Nevada. This document is intended for use in postclosure analysis only. Bounding waste stream information and data were collected that capture probable limits. For commercially generated waste, this analysis considers alternative waste stream projections to bound the characteristics of wastes likely to be encountered using arrival scenarios that potentially impact the commercial spent nuclearmore » fuel (CSNF) waste stream. For TSPA-LA, this radionuclide inventory analysis considers U.S. Department of Energy (DOE) high-level radioactive waste (DHLW) glass and two types of spent nuclear fuel (SNF): CSNF and DOE-owned (DSNF). These wastes are placed in two groups of waste packages: the CSNF waste package and the codisposal waste package (CDSP), which are designated to contain DHLW glass and DSNF, or DHLW glass only. The radionuclide inventory for naval SNF is provided separately in the classified ''Naval Nuclear Propulsion Program Technical Support Document'' for the License Application. As noted previously, the radionuclide inventory data presented here is intended only for TSPA-LA postclosure calculations. It is not applicable to preclosure safety calculations. Safe storage, transportation, and ultimate disposal of these wastes require safety analyses to support the design and licensing of repository equipment and facilities. These analyses will require radionuclide inventories to represent the radioactive source term that must be accommodated during handling, storage and disposition of these wastes. This analysis uses the best available information to identify the radionuclide inventory that is expected at the last year of last emplacement, currently identified as 2030 and 2033, depending on the type of waste. TSPA-LA uses the results of this analysis to decay the inventory to the year of repository closure projected for the year of 2060.« less

The radioactive waste management policy and practice in the Czech Republic

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

Kucerka, M.

1996-12-31

In recent period, the new Czech Atomic Law is in the final stage of preparation, and the author expects that Parliament of the Czech Republic will approve it in the first half of the year 1996. Partly the law deals with new distribution of responsibilities among bodies involved in utilization of nuclear energy and ionizing radiation, the state and local authorities. The new provisions include also radioactive waste management activities. These provisions clarify the relations between radioactive waste generators and state, and define explicitly duties of waste generators. One of the most important duties is to cover all expenses formore » radioactive waste management now and in the future, including radioactive waste disposal and decommissioning of nuclear facilities. The law establishes radioactive waste management and decommissioning funds and the new, on waste generators independent radioactive waste management organization, controlled by state, to ensure the safety of inhabitants and the environment, and a optimization of expenses. Parallel to the preparation of the law, the Ministry of Industry and Trade prepares drafts of a statute of the radioactive waste management organization and its control board, and of the methodology and rules of management the radioactive waste fund. First drafts of these documents are expected to be complete in January 1996. The paper will describe recent practice and policy of the radioactive waste management including uranium mining and milling tailings, amounts of waste and its activities, economical background, and safety. A special attention will be paid to description of expected changes in connection with the new Atomic Law and expected steps and time schedule of reorganization of the radioactive waste management structure in the Czech Republic.« less

Federal Guidance Report No. 10: The Radioactivity Concentration Guides

EPA Pesticide Factsheets

This document provides the calculation of derived limits for the 1960 Radiation Protection Guides reflecting updated models for dosimetry and biological transport. This report has been superseded by Federal Guidance Report No. 11.

Thirty-year solid waste generation forecast for facilities at SRS

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

Not Available

1994-07-01

The information supplied by this 30-year solid waste forecast has been compiled as a source document to the Waste Management Environmental Impact Statement (WMEIS). The WMEIS will help to select a sitewide strategic approach to managing present and future Savannah River Site (SRS) waste generated from ongoing operations, environmental restoration (ER) activities, transition from nuclear production to other missions, and decontamination and decommissioning (D&D) programs. The EIS will support project-level decisions on the operation of specific treatment, storage, and disposal facilities within the near term (10 years or less). In addition, the EIS will provide a baseline for analysis ofmore » future waste management activities and a basis for the evaluation of the specific waste management alternatives. This 30-year solid waste forecast will be used as the initial basis for the EIS decision-making process. The Site generates and manages many types and categories of waste. With a few exceptions, waste types are divided into two broad groups-high-level waste and solid waste. High-level waste consists primarily of liquid radioactive waste, which is addressed in a separate forecast and is not discussed further in this document. The waste types discussed in this solid waste forecast are sanitary waste, hazardous waste, low-level mixed waste, low-level radioactive waste, and transuranic waste. As activities at SRS change from primarily production to primarily decontamination and decommissioning and environmental restoration, the volume of each waste s being managed will change significantly. This report acknowledges the changes in Site Missions when developing the 30-year solid waste forecast.« less

A review of radioactive isotopes and other residence time tracers in understanding groundwater recharge: Possibilities, challenges, and limitations

NASA Astrophysics Data System (ADS)

Cartwright, Ian; Cendón, Dioni; Currell, Matthew; Meredith, Karina

2017-12-01

Documenting the location and magnitude of groundwater recharge is critical for understanding groundwater flow systems. Radioactive tracers, notably 14C, 3H, 36Cl, and the noble gases, together with other tracers whose concentrations vary over time, such as the chlorofluorocarbons or sulfur hexafluoride, are commonly used to estimate recharge rates. This review discusses some of the advantages and problems of using these tracers to estimate recharge rates. The suite of tracers allows recharge to be estimated over timescales ranging from a few years to several hundred thousand years, which allows both the long-term and modern behaviour of groundwater systems to be documented. All tracers record mean residence times and mean recharge rates rather than a specific age and date of recharge. The timescale over which recharge rates are averaged increases with the mean residence time. This is an advantage in providing representative recharge rates but presents a problem in comparing recharge rates derived from these tracers with those from other techniques, such as water table fluctuations or lysimeters. In addition to issues relating to the sampling and interpretation of specific tracers, macroscopic dispersion and mixing in groundwater flow systems limit how precisely groundwater residence times and recharge rates may be estimated. Additionally, many recharge studies have utilised existing infrastructure that may not be ideal for this purpose (e.g., wells with long screens that sample groundwater several kilometres from the recharge area). Ideal recharge studies would collect sufficient information to optimise the use of specific tracers and minimise the problems of mixing and dispersion.

Waste certification program plan for Oak Ridge National Laboratory. Revision 2

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

Not Available

1997-09-01

This document defines the waste certification program (WCP) developed for implementation at Oak Ridge National Laboratory (ORNL). The document describes the program structure, logic, and methodology for certification of ORNL wastes. The purpose of the WCP is to provide assurance that wastes are properly characterized and that the Waste Acceptance Criteria (WAC) for receiving facilities are met. The program meets the waste certification requirements for mixed (both radioactive and hazardous) and hazardous [including polychlorinated biphenyls (PCB)] waste. Program activities will be conducted according to ORNL Level 1 document requirements.

Packaging and transportation of radioactive materials

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

None

1978-01-01

The presentations made at the Symposium on Packaging and Transportation of Radioactive Materials are included. The purpose of the meeting was for the interchange of information on the technology and politics of radioactive material transportation. Separate abstracts were prepared for individual items. (DC)

78 FR 79561 - Information Collection Activities

Federal Register 2010, 2011, 2012, 2013, 2014

2013-12-30

... collection provisions in the HMR involving the transportation of radioactive materials in commerce... requirements help to establish that proper packages are used for the type of radioactive material being..., and emergency responders. Affected Public: Shippers and carriers of radioactive materials in commerce...

Final safety analysis report for the Galileo mission: Volume 3 (Book 2), Nuclear risk analysis document: Appendices: Revision 1

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

Not Available

1989-01-25

It is the purpose of the NRAD to provide an analysis of the range of potential consequences of accidents which have been identified that are associated with the launching and deployment of the Galileo mission spacecraft. The specific consequences analyzed are those associated with the possible release of radioactive material (fuel) of the Radioisotope Thermoelectric Generators (RTGs). They are in terms of radiation doses to people and areas of deposition of radioactive material. These consequence analyses can be used in several ways. One way is to identify the potential range of consequences which might have to be dealt with ifmore » there were to be an accident with a release of fuel, so as to assure that, given such an accident, the health and safety of the public will be reasonably protected. Another use of the information, in conjunction with accident and release probabilities, is to estimate the risks associated with the mission. That is, most space launches occur without incident. Given an accident, the most probable result relative to the RTGs is complete containment of the radioactive material. Only a small fraction of accidents might result in a release of fuel and subsequent radiological consequences. The combination of probability with consequence is risk, which can be compared to other human and societal risks to assure that no undue risks are implied by undertaking the mission. Book 2 contains eight appendices.« less

Safety analysis report for the Galileo Mission. Volume 3, book 2: Nuclear risk analysis document. Appendices, revision 1

NASA Astrophysics Data System (ADS)

1989-01-01

It is the purpose of the NRAD to provide an analysis of the range of potential consequences of accidents which have been identified that are associated with the launching and deployment of the Galileo mission spacecraft. The specific consequences analyzed are those associated with the possible release of radioactive material (fuel) of the Radioisotope Thermoelectric Generators (RTGs). They are in terms of radiation doses to people and areas of deposition of radioactive material. These consequence analyses can be used in several ways. One way is to identify the potential range of consequences which might have to be dealt with if there were to be an accident with a release of fuel, so as to assure that, given such an accident, the health and safety of the public will be reasonably protected. Another use of the information, in conjunction with accident and release probabilities, is to estimate the risks associated with the mission. That is, most space launches occur without incident. Given an accident, the most probable result relative to the RTGs is complete containment of the radioactive material. Only a small fraction of accidents might result in a release of fuel and subsequent radiological consequences. The combination of probability with consequence is risk, which can be compared to other human and societal risks to assure that no undue risks are implied by undertaking the mission. Book 2 contains eight appendices.

An overview of radioactive waste disposal procedures of a nuclear medicine department

PubMed Central

Ravichandran, R.; Binukumar, J. P.; Sreeram, Rajan; Arunkumar, L. S.

2011-01-01

Radioactive wastes from hospitals form one of the various types of urban wastes, which are managed in developed countries in a safe and organized way. In countries where growth of nuclear medicine services are envisaged, implementations of existing regulatory policies and guidelines in hospitals in terms of handling of radioactive materials used in the treatment of patients need a good model. To address this issue, a brief description of the methods is presented. A designed prototype waste storage trolley is found to be of great help in decaying the I-131 solid wastes from wards before releasing to waste treatment plant of the city. Two delay tanks with collection time of about 2 months and delay time of 2 months alternately result in 6 releases of urine toilet effluents to the sewage treatment plant (STP) of the hospital annually. Samples of effluents collected at releasing time documented radioactive releases of I-131 much below recommended levels of bi-monthly release. External counting of samples showed good statistical correlation with calculated values. An overview of safe procedures for radioactive waste disposal is presented. PMID:21731225

An overview of radioactive waste disposal procedures of a nuclear medicine department.

PubMed

Ravichandran, R; Binukumar, J P; Sreeram, Rajan; Arunkumar, L S

2011-04-01

Radioactive wastes from hospitals form one of the various types of urban wastes, which are managed in developed countries in a safe and organized way. In countries where growth of nuclear medicine services are envisaged, implementations of existing regulatory policies and guidelines in hospitals in terms of handling of radioactive materials used in the treatment of patients need a good model. To address this issue, a brief description of the methods is presented. A designed prototype waste storage trolley is found to be of great help in decaying the I-131 solid wastes from wards before releasing to waste treatment plant of the city. Two delay tanks with collection time of about 2 months and delay time of 2 months alternately result in 6 releases of urine toilet effluents to the sewage treatment plant (STP) of the hospital annually. Samples of effluents collected at releasing time documented radioactive releases of I-131 much below recommended levels of bi-monthly release. External counting of samples showed good statistical correlation with calculated values. An overview of safe procedures for radioactive waste disposal is presented.

Hanford Site annual dangerous waste report: Volume 4, Waste Management Facility report, Radioactive mixed waste

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

NONE

1994-12-31

This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, handling method and containment vessel, waste number, waste designation and amount of waste.

2011 Radioactive Materials Usage Survey for Unmonitored Point Sources

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

Sturgeon, Richard W.

This report provides the results of the 2011 Radioactive Materials Usage Survey for Unmonitored Point Sources (RMUS), which was updated by the Environmental Protection (ENV) Division's Environmental Stewardship (ES) at Los Alamos National Laboratory (LANL). ES classifies LANL emission sources into one of four Tiers, based on the potential effective dose equivalent (PEDE) calculated for each point source. Detailed descriptions of these tiers are provided in Section 3. The usage survey is conducted annually; in odd-numbered years the survey addresses all monitored and unmonitored point sources and in even-numbered years it addresses all Tier III and various selected other sources.more » This graded approach was designed to ensure that the appropriate emphasis is placed on point sources that have higher potential emissions to the environment. For calendar year (CY) 2011, ES has divided the usage survey into two distinct reports, one covering the monitored point sources (to be completed later this year) and this report covering all unmonitored point sources. This usage survey includes the following release points: (1) all unmonitored sources identified in the 2010 usage survey, (2) any new release points identified through the new project review (NPR) process, and (3) other release points as designated by the Rad-NESHAP Team Leader. Data for all unmonitored point sources at LANL is stored in the survey files at ES. LANL uses this survey data to help demonstrate compliance with Clean Air Act radioactive air emissions regulations (40 CFR 61, Subpart H). The remainder of this introduction provides a brief description of the information contained in each section. Section 2 of this report describes the methods that were employed for gathering usage survey data and for calculating usage, emissions, and dose for these point sources. It also references the appropriate ES procedures for further information. Section 3 describes the RMUS and explains how the survey results are organized. The RMUS Interview Form with the attached RMUS Process Form(s) provides the radioactive materials survey data by technical area (TA) and building number. The survey data for each release point includes information such as: exhaust stack identification number, room number, radioactive material source type (i.e., potential source or future potential source of air emissions), radionuclide, usage (in curies) and usage basis, physical state (gas, liquid, particulate, solid, or custom), release fraction (from Appendix D to 40 CFR 61, Subpart H), and process descriptions. In addition, the interview form also calculates emissions (in curies), lists mrem/Ci factors, calculates PEDEs, and states the location of the critical receptor for that release point. [The critical receptor is the maximum exposed off-site member of the public, specific to each individual facility.] Each of these data fields is described in this section. The Tier classification of release points, which was first introduced with the 1999 usage survey, is also described in detail in this section. Section 4 includes a brief discussion of the dose estimate methodology, and includes a discussion of several release points of particular interest in the CY 2011 usage survey report. It also includes a table of the calculated PEDEs for each release point at its critical receptor. Section 5 describes ES's approach to Quality Assurance (QA) for the usage survey. Satisfactory completion of the survey requires that team members responsible for Rad-NESHAP (National Emissions Standard for Hazardous Air Pollutants) compliance accurately collect and process several types of information, including radioactive materials usage data, process information, and supporting information. They must also perform and document the QA reviews outlined in Section 5.2.6 (Process Verification and Peer Review) of ES-RN, 'Quality Assurance Project Plan for the Rad-NESHAP Compliance Project' to verify that all information is complete and correct.« less

Facility effluent monitoring plan for the plutonium uranium extraction facility

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

Wiegand, D.L.

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of themore » effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years.« less

Guidelines for generators to meet HWHF acceptance requirements for hazardous, radioactive, and mixed wastes at Berkeley Lab. Revision 3

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

Albert, R.

1996-06-01

This document provides performance standards that one, as a generator of hazardous chemical, radioactive, or mixed wastes at the Berkeley Lab, must meet to manage their waste to protect Berkeley Lab staff and the environment, comply with waste regulations and ensure the continued safe operation of the workplace, have the waste transferred to the correct Waste Handling Facility, and enable the Environment, Health and Safety (EH and S) Division to properly pick up, manage, and ultimately send the waste off site for recycling, treatment, or disposal. If one uses and generates any of these wastes, one must establish a Satellitemore » Accumulation Area and follow the guidelines in the appropriate section of this document. Topics include minimization of wastes, characterization of the wastes, containers, segregation, labeling, empty containers, and spill cleanup and reporting.« less

Natural radioactivity in commercial granites extracted near old uranium mines: scientific, economic and social impact of disinformation.

NASA Astrophysics Data System (ADS)

Pereira, Dolores; Pereira, Alcides; Neves, Luis

2015-04-01

The study of radioactivity in natural stones is a subject of great interest from different points of view: scientific, social and economic. Several previous studies have demonstrated that the radioactivity is dependent, not only on the uranium content, but also on the structures, textures, minerals containing the uranium and degree of weathering of the natural stone. Villavieja granite is extracted in a village where uranium mining was an important activity during the 20th century. Today the mine is closed but the granite is still extracted. Incorrect information about natural radioactivity given to natural stone users, policy makers, construction managers and the general public has caused turmoil in the media for many years. This paper considers problems associated with the communication of reliable information, as well as uncertainties, on natural radioactivity to these audiences.

Waking a Sleeping Giant: The Tobacco Industry’s Response to the Polonium-210 Issue

PubMed Central

Muggli, Monique E.; Ebbert, Jon O.; Robertson, Channing; Hurt, Richard D.

2008-01-01

The major tobacco manufacturers discovered that polonium was part of tobacco and tobacco smoke more than 40 years ago and attempted, but failed, to remove this radioactive substance from their products. Internal tobacco industry documents reveal that the companies suppressed publication of their own internal research to avoid heightening the public’s awareness of radioactivity in cigarettes. Tobacco companies continue to minimize their knowledge about polonium-210 in cigarettes in smoking and health litigation. Cigarette packs should carry a radiation-exposure warning label. PMID:18633078

Feasibility of Using Radioactive Tracers for Studies of Permeation of Chemicals through Protective Clothing Materials

DTIC Science & Technology

1991-10-01

minutes, 100x and 1000x magnification. letflon Coated Nomex, Methylene chloride 15 MINm ea p D ~ecant Freda 113 10 N2 70 d %~ C (gg / 󈧒 v 2 10 a. 11 56...Report No. CG- D -10-91 AD-A246 192 Feasibility of Using Radioactive Tracers for Studies of Permeation of Chemicals Through Protective Clothing...Connecticut 06340-6096 ii Technical Report Documentation Page 1. Report No. 2. Government Accession No. 3. Recipient’s Catalog No. CG- D -10-91 I 4

Methods and Data Used to Investigate Polonium-210 as a Source of Excess Gross-Alpha Radioactivity in Ground Water, Churchill County, Nevada

USGS Publications Warehouse

Seiler, Ralph L.

2007-01-01

Ground water is the major source of drinking water in the Carson River Basin, California and Nevada. Previous studies have shown that uranium and gross-alpha radioactivities in ground water can be greater than U.S. Environmental Protection Agency Maximum Contaminant Levels, particularly in the Carson Desert, Churchill County, Nevada. Studies also have shown that the primary source of the gross-alpha radioactivity and alpha-emitting radionuclides in ground water is the dissolution of uranium-rich granitic rocks and basin-fill sediments that have their origins in the Sierra Nevada. However, ground water sampled from some wells in the Carson Desert had gross-alpha radioactivities greater than could be accounted for by the decay of dissolved uranium. The occurrence of polonium-210 (Po-210) was hypothesized to explain the higher than expected gross-alpha radioactivities. This report documents and describes the study design, field and analytical methods, and data used to determine whether Po-210 is the source of excess gross-alpha radioactivity in ground water underlying the Carson Desert in and around Fallon, Nevada. Specifically, this report presents: 1) gross alpha and uranium radioactivities for 100 wells sampled from June to September 2001; and 2) pH, dissolved oxygen, specific conductance, and Po-210 radioactivity for 25 wells sampled in April and June 2007. Results of quality-control samples for the 2007 dataset are also presented.

Lincoln County nuclear waste project. Quarterly progress report, October 1, 1991--December 31, 1991

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

NONE

1996-03-01

This document included the following three progress reports to the Yucca Mountain Project Office on radioactive waste storage in Lincoln County, Nevada: financial status report; federal cash transactions report; and technical progress report.

Lincoln County nuclear waste project. Quarterly progress report, January 1, 1992--March 31, 1992

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

NONE

1996-03-01

This document included the following three progress reports to the Yucca Mountain Project Office on radioactive waste storage in Lincoln County, Nevada: financial status report; federal cash transactions report; and technical progress report.

Lincoln County nuclear waste project quarterly progress report, April 1, 1992--June 30, 1992

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

NONE

1996-03-01

This document included the following three progress reports to the Yucca Mountain Project Office on radioactive waste storage in Lincoln County, Nevada: financial status report; federal cash transactions report; and technical progress report.

Environmental Characteristics of EPA, NRC, and DOE Sites Contaminated with Radioactive Substances

EPA Pesticide Factsheets

This report is one of several documents developed cooperatively by the Interagency Environmental Pathway Modeling Workgroup to help bring a uniform approach to solving environmental modeling problems common to site remediation and restoration efforts.

Nuclear Waste: Increasing Scale and Sociopolitical Impacts

ERIC Educational Resources Information Center

La Porte, Todd R.

1978-01-01

Discusses the impact of radioactive waste management system on social and political development. The article also presents (1) types of information necessary to estimate the costs and consequences of radioactive waste management; and (2) an index of radioactive hazards to improve the basis for policy decisions. (HM)

Radioactive Wastes. Revised.

ERIC Educational Resources Information Center

Fox, Charles H.

This publication is one of a series of information booklets for the general public published by the United States Atomic Energy Commission. This booklet deals with the handling, processing and disposal of radioactive wastes. Among the topics discussed are: The Nature of Radioactive Wastes; Waste Management; and Research and Development. There are…

Histologic Findings and Cytological Alterations in Thyroid Nodules After Radioactive Iodine Treatment for Graves' Disease: A Diagnostic Dilemma.

PubMed

El Hussein, Siba; Omarzai, Yumna

2017-06-01

Unlike the well-documented relation between radiation to the neck and development of papillary thyroid carcinoma, a causal association between radioactive iodine treatment for Graves' disease and development of thyroid malignancy is less defined. However, patients with a background of thyroid dysfunction presenting with clinically palpable thyroid nodules are followed more closely than the average population, and fine needle aspiration is recommended in such circumstances. Cytological examination of aspirates, and histologic examination of tissue provided from patients with a known history of Graves' disease, managed by radioactive iodine therapy can create a diagnostic dilemma, as the distinction between radiation effect and a malignant primary thyroid neoplasm can be very challenging. Thus, pathologists should be aware of the existence of these changes in the setting of radiation therapy for Graves' disease. Providing pathologists with appropriate clinical history of Graves' disease treated with radioactive iodine is of paramount importance in order to prevent an overdiagnosis of malignancy.

10 CFR 72.24 - Contents of application: Technical information.

Code of Federal Regulations, 2011 CFR

2011-01-01

... STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C... radioactive waste, and/or reactor-related GTCC waste as appropriate, including how the ISFSI or MRS will be... of spent fuel, high-level radioactive waste, and/or reactor-related GTCC waste as appropriate for...

Transporting Radioactive Waste: An Engineering Activity. Grades 5-12.

ERIC Educational Resources Information Center

HAZWRAP, The Hazardous Waste Remedial Actions Program.

This brochure contains an engineering activity for upper elementary, middle school, and high school students that examines the transportation of radioactive waste. The activity is designed to inform students about the existence of radioactive waste and its transportation to disposal sites. Students experiment with methods to contain the waste and…

Applications of nuclear techniques relevant for civil security

NASA Astrophysics Data System (ADS)

Valkovi, Vlado

2006-05-01

The list of materials which are subject to inspection with the aim of reducing the acts of terrorism includes explosives, narcotics, chemical weapons, hazardous chemicals and radioactive materials. To this we should add also illicit trafficking with human beings. The risk of nuclear terrorism carried out by sub-national groups is considered not only in construction and/or use of nuclear device, but also in possible radioactive contamination of large urban areas. Modern personnel, parcel, vehicle and cargo inspection systems are non-invasive imaging techniques based on the use of nuclear analytical techniques. The inspection systems use penetrating radiations: hard x-rays (300 keV or more) or gamma-rays from radioactive sources (137Cs and 60Co with energies from 600 to 1300 keV) that produce a high resolution radiograph of the load. Unfortunately, this information is ''non-specific'' in that it gives no information on the nature of objects that do not match the travel documents and are not recognized by a visual analysis of the radiographic picture. Moreover, there are regions of the container where x and gamma-ray systems are ''blind'' due to the high average atomic number of the objects irradiated that appear as black spots in the radiographic image. Contrary to that is the use of neutrons; as results of the bombardment, nuclear reactions occur and a variety of nuclear particles, gamma and x-ray radiation is emitted, specific for each element in the bombarded material. The problem of material (explosive, drugs, chemicals, etc.) identification can be reduced to the problem of measuring elemental concentrations. Neutron scanning technology offers capabilities far beyond those of conventional inspection systems. The unique automatic, material specific detection of terrorist threats can significantly increase the security at ports, border-crossing stations, airports, and even within the domestic transportation infrastructure of potential urban targets as well as protecting armed forces and infrastructure.

10 CFR 71.75 - Qualification of special form radioactive material.

Code of Federal Regulations, 2010 CFR

2010-01-01

... temperature of 30°C (86°F) or greater; (v) The process in paragraph (c)(2)(i), (ii), and (iii) of this section... test specified in the International Organization for Standardization document ISO 2919-1980(e), “Sealed...

[Microbiological Aspects of Radioactive Waste Storage].

PubMed

Safonov, A V; Gorbunova, O A; German, K E; Zakharova, E V; Tregubova, V E; Ershov, B G; Nazina, T N

2015-01-01

The article gives information about the microorganisms inhabiting in surface storages of solid radioactive waste and deep disposal sites of liquid radioactive waste. It was shown that intensification of microbial processes can lead to significant changes in the chemical composition and physical state of the radioactive waste. It was concluded that the biogeochemical processes can have both a positive effect on the safety of radioactive waste storages (immobilization of RW macrocomponents, a decreased migration ability of radionuclides) and a negative one (biogenic gas production in subterranean formations and destruction of cement matrix).

Seeds in Chernobyl: the database on proteome response on radioactive environment

PubMed Central

Klubicová, Katarína; Vesel, Martin; Rashydov, Namik M.; Hajduch, Martin

2012-01-01

Two serious nuclear accidents during the last quarter century (Chernobyl, 1986 and Fukushima, 2011) contaminated large agricultural areas with radioactivity. The database “Seeds in Chernobyl” (http://www.chernobylproteomics.sav.sk) contains the information about the abundances of hundreds of proteins from on-going investigation of mature and developing seed harvested from plants grown in radioactive Chernobyl area. This database provides a useful source of information concerning the response of the seed proteome to permanently increased level of ionizing radiation in a user-friendly format. PMID:23087698

Portsmouth Gaseous Diffusion Plant environmental report for 1989

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

Turner, J.W.

1990-10-01

This calendar year 1989 annual report on environmental surveillance of the US Department of Energy's (DOE) Portsmouth Gaseous Diffusion Plant (PORTS) and its environs consists of two parts: the Summary, Discussion, and Conclusions (Part 1) and the Data Presentation (Part 2). The objectives of this report are the following: report 1989 monitoring data for the installation and its environs that may have been affected by operations on the plant site, provide reasonably detailed information about the plant site and plant operations, provide detailed information on input and assumptions used in all calculations, provide trend analyses (where appropriate) to indicate increasesmore » and decreases in environmental impact, and provide general information on plant quality assurance. Routine monitoring and sampling for radiation, radioactive materials, and chemical substances on and off the DOE site are used to document compliance with appropriate standards, to identify trends, to provide information for the public, and to contribute to general environmental knowledge. The surveillance program assists in fulfilling the DOE policy of protecting the public, employees, and environment from harm that could be caused by its activities and reducing negative environmental impacts to the greatest degree practicable. Environmental-monitoring information complements data on specific releases, trends, and summaries. 26 refs.« less

Best Practices for the Security of Radioactive Materials

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

Coulter, D.T.; Musolino, S.

2009-05-01

This work is funded under a grant provided by the US Department of Health and Human Services, Centers for Disease Control. The Department of Health and Mental Hygiene (DOHMH) awarded a contract to Brookhaven National Laboratory (BNL) to develop best practices guidance for Office of Radiological Health (ORH) licensees to increase on-site security to deter and prevent theft of radioactive materials (RAM). The purpose of this document is to describe best practices available to manage the security of radioactive materials in medical centers, hospitals, and research facilities. There are thousands of such facilities in the United States, and recent studiesmore » suggest that these materials may be vulnerable to theft or sabotage. Their malevolent use in a radiological-dispersion device (RDD), viz., a dirty bomb, can have severe environmental- and economic- impacts, the associated area denial, and potentially large cleanup costs, as well as other effects on the licensees and the public. These issues are important to all Nuclear Regulatory Commission and Agreement State licensees, and to the general public. This document outlines approaches for the licensees possessing these materials to undertake security audits to identify vulnerabilities in how these materials are stored or used, and to describe best practices to upgrade or enhance their security. Best practices can be described as the most efficient (least amount of effort/cost) and effective (best results) way of accomplishing a task and meeting an objective, based on repeatable procedures that have proven themselves over time for many people and circumstances. Best practices within the security industry include information security, personnel security, administrative security, and physical security. Each discipline within the security industry has its own 'best practices' that have evolved over time into common ones. With respect to radiological devices and radioactive-materials security, industry best practices encompass both physical security (hardware and engineering) and administrative procedures. Security regimes for these devices and materials typically use a defense-in-depth- or layered-security approach to eliminate single points of failure. The Department of Energy, the Department of Homeland Security, the Department of Defense, the American Society of Industrial Security (ASIS), the Security Industry Association (SIA) and Underwriters Laboratory (UL) all rovide design guidance and hardware specifications. With a graded approach, a physical-security specialist can tailor an integrated security-management system in the most appropriate cost-effective manner to meet the regulatory and non-regulatory requirements of the licensee or client.« less

76 FR 54808 - Agency Information Collection Activities: Submission for the Office of Management and Budget (OMB...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-09-02

... the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste and Reactor-Related... receive, transfer, package and possess power reactor spent fuel, high-level waste, and other radioactive..., package, and possess power reactor spent fuel and high-level radioactive waste, and other associated...

10 CFR 62.12 - Contents of a request for emergency access: General information.

Code of Federal Regulations, 2010 CFR

2010-01-01

... EMERGENCY ACCESS TO NON-FEDERAL AND REGIONAL LOW-LEVEL WASTE DISPOSAL FACILITIES Request for a Commission... the person(s) or company(ies) generating the low-level radioactive waste for which the determination...) Certification that the radioactive waste for which emergency access is requested is low-level radioactive waste...

76 FR 35137 - Vulnerability and Threat Information for Facilities Storing Spent Nuclear Fuel and High-Level...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-06-16

... High-Level Radioactive Waste AGENCY: U.S. Nuclear Regulatory Commission. ACTION: Public meeting... Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste,'' and 73... Spent Nuclear Fuel (SNF) and High-Level Radioactive Waste (HLW) storage facilities. The draft regulatory...

10 CFR 2.1009 - Procedures.

Code of Federal Regulations, 2011 CFR

2011-01-01

... Applicable to Proceedings for the Issuance of Licenses for the Receipt of High-Level Radioactive Waste at a... to provide electronic files of documentary material ; (2) Establish procedures to implement the... responsibility to provide electronic files of documentary material; (4) Ensure that all documents carry the...

10 CFR 2.1009 - Procedures.

Code of Federal Regulations, 2010 CFR

2010-01-01

... Applicable to Proceedings for the Issuance of Licenses for the Receipt of High-Level Radioactive Waste at a... to provide electronic files of documentary material ; (2) Establish procedures to implement the... responsibility to provide electronic files of documentary material; (4) Ensure that all documents carry the...

10 CFR 2.1009 - Procedures.

Code of Federal Regulations, 2012 CFR

2012-01-01

... Applicable to Proceedings for the Issuance of Licenses for the Receipt of High-Level Radioactive Waste at a... to provide electronic files of documentary material ; (2) Establish procedures to implement the... responsibility to provide electronic files of documentary material; (4) Ensure that all documents carry the...

Fact Sheet: Documenting Ground-Water Models Selection at Site Contaminated with Radioactive Substance

EPA Pesticide Factsheets

This fact sheet summarizes the report by a joint Interagency Environmental Pathway Modeling Working Group. It was designed to be used by technical staff responsible for identifying and implementing flow and transport models to support cleanup decisions.

10 CFR 71.1 - Communications and records.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Communications and records. 71.1 Section 71.1 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL General... addressed: ATTN: Document Control Desk, Director, Spent Fuel Project Office, Office of Nuclear Material...

10 CFR 830.204 - Documented safety analysis.

Code of Federal Regulations, 2011 CFR

2011-01-01

..., and accident conditions, including consideration of natural and man-made external events... radioactive and other hazardous materials, and consideration of the need for analysis of accidents which may... preparedness, fire protection, waste management, and radiation protection; and (6) With respect to a nonreactor...

10 CFR 830.204 - Documented safety analysis.

Code of Federal Regulations, 2014 CFR

2014-01-01

..., and accident conditions, including consideration of natural and man-made external events... radioactive and other hazardous materials, and consideration of the need for analysis of accidents which may... preparedness, fire protection, waste management, and radiation protection; and (6) With respect to a nonreactor...

10 CFR 830.204 - Documented safety analysis.

Code of Federal Regulations, 2013 CFR

2013-01-01

..., and accident conditions, including consideration of natural and man-made external events... radioactive and other hazardous materials, and consideration of the need for analysis of accidents which may... preparedness, fire protection, waste management, and radiation protection; and (6) With respect to a nonreactor...

10 CFR 830.204 - Documented safety analysis.

Code of Federal Regulations, 2012 CFR

2012-01-01

..., and accident conditions, including consideration of natural and man-made external events... radioactive and other hazardous materials, and consideration of the need for analysis of accidents which may... preparedness, fire protection, waste management, and radiation protection; and (6) With respect to a nonreactor...

RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT

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

KOZLOWSKI, S.D.

2007-05-30

This technical basis document was developed to support RPP-23429, Preliminary Documented Safety Analysis for the Demonstration Bulk Vitrification System (PDSA) and RPP-23479, Preliminary Documented Safety Analysis for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Facility. The main document describes the risk binning process and the technical basis for assigning risk bins to the representative accidents involving the release of dried radioactive waste materials from the Demonstration Bulk Vitrification System (DBVS) and to the associated represented hazardous conditions. Appendices D through F provide the technical basis for assigning risk bins to the representative dried waste release accident and associated represented hazardous conditionsmore » for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Packaging Unit (WPU). The risk binning process uses an evaluation of the frequency and consequence of a given representative accident or represented hazardous condition to determine the need for safety structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls. A representative accident or a represented hazardous condition is assigned to a risk bin based on the potential radiological and toxicological consequences to the public and the collocated worker. Note that the risk binning process is not applied to facility workers because credible hazardous conditions with the potential for significant facility worker consequences are considered for safety-significant SSCs and/or TSR-level controls regardless of their estimated frequency. The controls for protection of the facility workers are described in RPP-23429 and RPP-23479. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as described below.« less

Data Quality Objectives for Regulatory Requirements for Hazardous and Radioactive Air Emissions Sampling and Analysis

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

MULKEY, C.H.

1999-07-06

This document describes the results of the data quality objective (DQO) process undertaken to define data needs for state and federal requirements associated with toxic, hazardous, and/or radiological air emissions under the jurisdiction of the River Protection Project (RPP). Hereafter, this document is referred to as the Air DQO. The primary drivers for characterization under this DQO are the regulatory requirements pursuant to Washington State regulations, that may require sampling and analysis. The federal regulations concerning air emissions are incorporated into the Washington State regulations. Data needs exist for nonradioactive and radioactive waste constituents and characteristics as identified through themore » DQO process described in this document. The purpose is to identify current data needs for complying with regulatory drivers for the measurement of air emissions from RPP facilities in support of air permitting. These drivers include best management practices; similar analyses may have more than one regulatory driver. This document should not be used for determining overall compliance with regulations because the regulations are in constant change, and this document may not reflect the latest regulatory requirements. Regulatory requirements are also expected to change as various permits are issued. Data needs require samples for both radionuclides and nonradionuclide analytes of air emissions from tanks and stored waste containers. The collection of data is to support environmental permitting and compliance, not for health and safety issues. This document does not address health or safety regulations or requirements (those of the Occupational Safety and Health Administration or the National Institute of Occupational Safety and Health) or continuous emission monitoring systems. This DQO is applicable to all equipment, facilities, and operations under the jurisdiction of RPP that emit or have the potential to emit regulated air pollutants.« less

RADIOACTIVE CONTAMINATION OF FOOD

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

Setter, L.R.

The environment and, consequently, food contains measurable amounts of radionuclides arising primarily from the distribution of nuclear bomb debris over the entire earth's surface. This radioactivity is in addition to natural radioactivity which exists in thc environment. A wealth of information has been gathered on the artificial radioactivity in air, water, vegetation, and soil; on physical and chemical mechanisms of radioaetive movement in the biosphere; and on the biologic behavior of radionuclide uptake by animals and human beings and their distribution in excretions and secretions. Collection of additional information under more carefully designed and executed studies is under way. Theremore » remains the task of marshalling and reviewing the data obtained during active fall-out up to the summer of 1959. With later information collected during a period of substantially no fall-out, the interpretation of these data hopefully will indicate the relative magnitude of physical, chemical, and biologic factors influencing levels in plants and animals, provide a means of predicting future levels, and, most important, permit some evaluation of the effects of nuclear radiation from ingestion of contaminated food as a part of the total effects from fall-out and from natural radioactivity. (auth)« less

Evaluation of Radiation Doses Due to Consumption of Contaminated Food Items and Calculation of Food Class-Specific Derived Intervention Levels

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

Heinzelman, K M; Mansfield, W G

This document evaluates the expected radiation dose due to the consumption of several specific food classes (dairy, meat, produce, etc.) contaminated with specific radionuclides, and relates concentration levels in food to the detection abilities of typical aboratory analysis/measurement methods. The attached charts present the limiting organ dose as a function of the radionuclide concentration in a particular food class, and allow the user to compare these concentrations and doses to typical analytical detection apabilities. The expected radiation dose depends on several factors: the age of the individual; the radionuclide present in the food; the concentration of the radionuclide in themore » food; and the amount of food consumed. Food consumption rates for individuals of various ges were taken from the 1998 United States Food and Drug Administration (FDA) document, Accidental Radioactive Contamination of HUman Food and Animal Feeds: Recommendations for State and Local Agencies. In that document, the FDA defines the erived Intervention Level (DIL), which is the concentration of a particular radionuclide in food that if consumed could result in an individual receiving a radiation dose exceeding the Protection Action Guide (PAG) thresholds for intervention. This document also resents odified, food class specific DIL, which is calculated using a somewhat modified version of the FDA's procedure. This document begins with an overview of the FDA's DIL calculation, followed by a description of the food class specific DIL calculations, and finally charts of the radiation dose per radioactivity concentration for several food class/radionuclide combinations.« less

Implementation of the Regulatory Authority Information System in Egypt

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

Carson, S.D.; Schetnan, R.; Hasan, A.

2006-07-01

As part of the implementation of a bar-code-based system to track radioactive sealed sources (RSS) in Egypt, the Regulatory Authority Information System Personal Digital Assistant (RAIS PDA) Application was developed to extend the functionality of the International Atomic Energy Agency's (IAEA's) RAIS database by allowing users to download RSS data from the database to a portable PDA equipped with a bar-code scanner. [1, 4] The system allows users in the field to verify radioactive sealed source data, gather radioactive sealed source audit information, and upload that data to the RAIS database. This paper describes the development of the RAIS PDAmore » Application, its features, and how it will be implemented in Egypt. (authors)« less

Technical Basis Document for Internal Dosimetry at Sandia National Laboratories Revision 2.

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

Potter, Charles A.

2014-09-01

The RPID Project will be implemented at all SNL facilities for activities involving the processing and/or storing of radioactive materials. This project includes activities at the Tech Area (TA) I, TA II, TA III, TA IV, TA V, Coyote Test Field, and environmental restoration sites at SNL, located in Albuquerque, New Mexico, and the Kauai Test Facility(SNL/KTF). Reference to SNL throughout this document includes facilities and activities at the Albuquerque location and at SNL/KTF.

76 FR 14386 - Environmental Management Site-Specific Advisory Board, Hanford

Federal Register 2010, 2011, 2012, 2013, 2014

2011-03-16

...: Red Lion Hotel on the River, Jantzen Beach, 909 North Hayden Island Drive, Portland, Oregon 97217... Committee; Public Involvement Committee; and Budgets and Contracts Committee Potential Board Advice [cir] 2011-2013 Budget [cir] Regulatory document timelines/review [cir] Radioactive solid waste burial...

Low-level radioactive waste management: transitioning to off-site disposal at Los Alamos National Laboratory

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

Dorries, Alison M

2010-11-09

Facing the closure of nearly all on-site management and disposal capability for low-level radioactive waste (LLW), Los Alamos National Laboratory (LANL) is making ready to ship the majority of LLW off-site. In order to ship off-site, waste must meet the Treatment, Storage, and Disposal Facility's (TSDF) Waste Acceptance Criteria (WAC). In preparation, LANL's waste management organization must ensure LANL waste generators characterize and package waste compliantly and waste characterization documentation is complete and accurate. Key challenges that must be addressed to successfully make the shift to off-site disposal of LLW include improving the detail, accuracy, and quality of process knowledgemore » (PK) and acceptable knowledge (AK) documentation, training waste generators and waste management staff on the higher standard of data quality and expectations, improved WAC compliance for off-site facilities, and enhanced quality assurance throughout the process. Certification of LANL generators will allow direct off-site shipping of LLW from their facilities.« less

Openness initiative

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

Duncan, S.S.

1995-12-31

Although antinuclear campaigns seem to be effective, public communication and education efforts on low-level radioactive waste have mixed results. Attempts at public information programs on low-level radioactive waste still focus on influencing public opinion. A question then is: {open_quotes}Is it preferable to have a program focus on public education that will empower individuals to make informed decisions rather than trying to influence them in their decisions?{close_quotes} To address this question, a case study with both quantitative and qualitative data will be used. The Ohio Low-Level Radioactive Waste Education Program has a goal to provide people with information they want/need tomore » make their own decisions. The program initiated its efforts by conducting a statewide survey to determine information needed by people and where they turned for that information. This presentation reports data from the survey and then explores the program development process in which programs were designed and presented using the information. Pre and post data from the programs reveal attitude and knowledge shifts.« less

A summary description of the flammable gas tank safety program

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

Johnson, G.D.; Sherwood, D.J.

1994-10-01

Radioactive liquid waste may produce hydrogen as result of the interaction of gamma radiation and water. If the waste contains organic chelating agents, additional hydrogen as well as nitrous oxide and ammonia may be produced by thermal and radiolytic decomposition of these organics. Several high-level radioactive liquid waste storage tanks, located underground at the Hanford Site in Washington State, are on a Flammable Gas Watch List. Some contain waste that produces and retains gases until large quantities of gas are released rapidly to the tank vapor space. Tanks nearly-filled to capacity have relatively little vapor space; therefore if the wastemore » suddenly releases a large amount of hydrogen and nitrous oxide, a flammable gas mixture could result. The most notable example of a Hanford waste tank with a flammable gas problem is tank 241-SY-101. Upon occasion waste stored in this tank has released enough flammable gas to burn if an ignition source had been present inside of the tank. Several, other Hanford waste tanks exhibit similar behavior although to a lesser magnitude. Because this behavior was hot adequately-addressed in safety analysis reports for the Hanford Tank Farms, an unreviewed safety question was declared, and in 1990 the Flammable Gas Tank Safety Program was established to address this problem. The purposes of the program are a follows: (1) Provide safety documents to fill gaps in the safety analysis reports, and (2) Resolve the safety issue by acquiring knowledge about gas retention and release from radioactive liquid waste and developing mitigation technology. This document provides the general logic and work activities required to resolve the unreviewed safety question and the safety issue of flammable gas mixtures in radioactive liquid waste storage tanks.« less

Toxic Substances Control Act (TSCA) Polychlorinated Biphenyl (PCB)/Radioactive Waste Annual Inventory for Calendar Year 2013

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

no author on report

2014-06-01

The Toxic Substances Control Act, 40 CFR 761.65(a)(1) provides an exemption from the one year storage time limit for PCB/radioactive waste. PCB/radioactive waste may exceed the one year time limit provided that the provisions at 40 CFR 761.65(a)(2)(ii) and 40 CFR 761.65(a)(2)(iii) are followed. These two subsections require, (ii) "A written record documenting all continuing attempts to secure disposal is maintained until the waste is disposed of" and (iii) "The written record required by subsection (ii) of this section is available for inspection or submission if requested by EPA." EPA Region 10 has requested the Department of Energy (DOE) tomore » submit an inventory of radioactive-contaminated PCB waste in storage at the Idaho National Laboratory (INL) for the previous calendar year. The annual inventory is separated into two parts, INL without Advanced Mixed Waste Treatment Project (AMWTP) (this includes Battelle Energy Alliance, LLC, CH2M-WG Idaho, LLC, and the Naval Reactors Facility), and AMWTP.« less

Safety and Security of Radioactive Sealed and Disused/Orphan Sources in Ukraine - German Contribution - 13359

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

Brasser, Thomas; Hertes, Uwe; Meyer, Thorsten

2013-07-01

Within the scope of 'Nuclear Security of Radioactive Sources', the German government implemented the modernization of Ukrainian State Production Company's transport and storage facility for radioactive sources (TSF) in Kiev. The overall management of optimizing the physical protection of the storage facility (including the construction of a hot cell for handling the radioactive sources) is currently carried out by the German Federal Foreign Office (AA). AA jointly have assigned Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Germany's leading expert institution in the area of nuclear safety and waste management, to implement the project and to ensure transparency by financial andmore » technical monitoring. Sealed radioactive sources are widely used in industry, medicine and research. Their life cycle starts with the production and finally ends with the interim/long-term storage of the disused sources. In Ukraine, IZOTOP is responsible for all radioactive sources throughout their life cycle. IZOTOP's transport and storage facility (TSF) is the only Ukrainian storage facility for factory-fresh radioactive sources up to an activity of about 1 million Ci (3.7 1016 Bq). The TSF is specially designed for the storage and handling of radioactive sources. Storage began in 1968, and is licensed by the Ukrainian state authorities. Beside the outdated state of TSF's physical protection and the vulnerability of the facility linked with it, the lack of a hot cell for handling and repacking radioactive sources on the site itself represents an additional potential hazard. The project, financed by the German Federal Foreign Office, aims to significantly improve the security of radioactive sources during their storage and handling at the TSF site. Main tasks of the project are a) the modernization of the physical protection of the TSF itself in order to prevent any unauthorized access to radioactive sources as well as b) the construction of a hot cell to reduce the number of transports of radioactive sources within the city of Kiev. In future, the new established hot cell at IZOTOP's transport and storage facility will be useful for identification and characterization of orphan/disused radioactive sources. The projects implemented are performed in accordance with international recommendations (e. g. IAEA) and national normative documents and will make a crucial contribution towards an improved safety and security management of radioactive sources in Ukraine. (authors)« less

Characterization of Class A low-level radioactive waste 1986--1990. Volume 6: Appendices G--J

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

Dehmel, J.C.; Loomis, D.; Mauro, J.

1994-01-01

Under contract to the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, the firms of S. Cohen & Associates, Inc. (SC&A) and Eastern Research Group (ERG) have compiled a report that describes the physical, chemical, and radiological properties of Class-A low-level radioactive waste. The report also presents information characterizing various methods and facilities used to treat and dispose non-radioactive waste. A database management program was developed for use in accessing, sorting, analyzing, and displaying the electronic data provided by EG&G. The program was used to present and aggregate data characterizing the radiological, physical, and chemical properties of the wastemore » from descriptions contained in shipping manifests. The data thus retrieved are summarized in tables, histograms, and cumulative distribution curves presenting radionuclide concentration distributions in Class-A waste as a function of waste streams, by category of waste generators, and regions of the United States. The report also provides information characterizing methods and facilities used to treat and dispose non-radioactive waste, including industrial, municipal, and hazardous waste regulated under Subparts C and D of the Resource Conservation and Recovery Act (RCRA). The information includes a list of disposal options, the geographical locations of the processing and disposal facilities, and a description of the characteristics of such processing and disposal facilities. Volume 1 contains the Executive Summary, Volume 2 presents the Class-A waste database, Volume 3 presents the information characterizing non-radioactive waste management practices and facilities, and Volumes 4 through 7 contain Appendices A through P with supporting information.« less

International Approaches for Nuclear Waste Disposal in Geological Formations: Geological Challenges in Radioactive Waste Isolation—Fifth Worldwide Review

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

Faybishenko, Boris; Birkholzer, Jens; Sassani, David

The overall objective of the Fifth Worldwide Review (WWR-5) is to document the current state-of-the-art of major developments in a number of nations throughout the World pursuing geological disposal programs, and to summarize challenging problems and experience that have been obtained in siting, preparing and reviewing cases for the operational and long-term safety of proposed and operating nuclear waste repositories. The scope of the Review is to address current specific technical issues and challenges in safety case development along with the interplay of technical feasibility, siting, engineering design issues, and operational and post-closure safety. In particular, the chapters included inmore » the report present the following types of information: the current status of the deep geological repository programs for high level nuclear waste and low- and intermediate level nuclear waste in each country, concepts of siting and radioactive waste and spent nuclear fuel management in different countries (with the emphasis of nuclear waste disposal under different climatic conditions and different geological formations), progress in repository site selection and site characterization, technology development, buffer/backfill materials studies and testing, support activities, programs, and projects, international cooperation, and future plans, as well as regulatory issues and transboundary problems.« less

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

McCone, John A.

The document represents the first annual reporting versus semiannual reporting of the Atomic Energy Commission (AEC) to Congress. The report consists of three parts: Part One, The Atomic Energy Industry in 1959 and Related Activities; Part Two, Major Activities in Atomic Energy Programs; and Part Three, Management of Radioactive Wastes. Nineteen appendices are also included.

Science, Society, and America's Nuclear Waste: Ionizing Radiation, Unit 2. Teacher Guide. Second Edition.

ERIC Educational Resources Information Center

Department of Energy, Washington, DC. Office of Civilian Radioactive Waste Management, Washington, DC.

This guide is Unit 2 of the four-part series, Science, Society, and America's Nuclear Waste, produced by the U.S. Department of Energy's Office of Civilian Radioactive Waste Management. The goal of this unit is to convey factual information relevant to radioactivity and radiation and relate that information both to the personal lives of students…

WASTE TREATMENT PLANT (WTP) LIQUID EFFLUENT TREATABILITY EVALUATION

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

LUECK, K.J.

2004-10-18

A forecast of the radioactive, dangerous liquid effluents expected to be produced by the Waste Treatment Plant (WTP) was provided by Bechtel National, Inc. (BNI 2004). The forecast represents the liquid effluents generated from the processing of Tank Farm waste through the end-of-mission for the WTP. The WTP forecast is provided in the Appendices. The WTP liquid effluents will be stored, treated, and disposed of in the Liquid Effluent Retention Facility (LERF) and the Effluent Treatment Facility (ETF). Both facilities are located in the 200 East Area and are operated by Fluor Hanford, Inc. (FH) for the US. Department ofmore » Energy (DOE). The treatability of the WTP liquid effluents in the LERF/ETF was evaluated. The evaluation was conducted by comparing the forecast to the LERF/ETF treatability envelope (Aromi 1997), which provides information on the items which determine if a liquid effluent is acceptable for receipt and treatment at the LERF/ETF. The format of the evaluation corresponds directly to the outline of the treatability envelope document. Except where noted, the maximum annual average concentrations over the range of the 27 year forecast was evaluated against the treatability envelope. This is an acceptable approach because the volume capacity in the LERF Basin will equalize the minimum and maximum peaks. Background information on the LERF/ETF design basis is provided in the treatability envelope document.« less

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

Radioactive Waste Management Complex low-level waste radiological performance assessment

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

Maheras, S.J.; Rood, A.S.; Magnuson, S.O.

This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsitemore » receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected.« less

Current situation and future plans in radioactive waste management in Mexico

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

Lopez, H.; Jimenez, M.

1992-01-01

A brief introduction is offered in this document in order to explain the importance which is given in Mexico to the safe management of radioactive wastes. The Secretaria de Energia, Minas e Industria Paraestatal is the organization responsible for this issue. Also, a brief historical background is offered so as to understand the evolution of these activities since they were originated. This background allows us to describe the present situation, which consists in a substantial change in the volume of produced radioactive wastes; in other words, before the present situation only the, nuclear wastes from the application of radioisotopes weremore » generated whereas currently, with the starting of commercial operation of the first unit of Laguna Verde Nuclear Power Plant (LVNPP), large volumes of industrial radioactive wastes are being generated. A mention is given as well of the acquired experience during more than 20 years of waste management and of the technologies which have been applied or practiced in the use and disposal of such wastes. Finally, some general trends in relation to the future planning are indicated, which essentially consist in the siting and characterization of a site so as to, design and construct a permanent disposal facility in order to dispose the operational radioactive wastes from LVNPP.« less

Radiological impact of 2016 operations at the Savannah River Site

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

Minter, K. L.; Jannik, G. T.; Dixon, K. M.

This report presents the environmental dose assessment methods and the estimated potential doses to the offsite public from 2016 Savannah River Site (SRS) air and liquid radioactive releases. Also documented are potential doses from special-case exposure scenarios, such as the consumption of wildlife or goat milk.

OFFSITE ENVIRONMENTAL MONITORING REPORT. RADIATION MONITORING AROUND UNITED STATES NUCLEAR TEST AREAS, CALENDAR YEAR 1982

EPA Science Inventory

A principal activity of the Offsite Radiological Safety Program is routine environmental monitoring for radioactive materials in various media and for radiation in areas which may be affected by nuclear tests. It is conducted to document compliance with standards, to identify tre...

Nevada Test Site Waste Acceptance Criteria (NTSWAC)

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

NNSA /NSO Waste Management Project

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal.

Nuclear waste management. Semiannual progress report, October 1982-March 1983

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

Chikalla, T.D.; Powell, J.A.

1983-06-01

This document is one of a series of technical progress reports designed to report radioactive waste management programs at the Pacific Northwest Laboratory. Accomplishments in the following programs are reported: waste stabilization; Materials Characterization Center; waste isolation; low-level waste management; remedial action; and supporting studies.

Cleanup Verification Package for the 100-F-20, Pacific Northwest Laboratory Parallel Pits

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

M. J. Appel

2007-01-22

This cleanup verification package documents completion of remedial action for the 100-F-20, Pacific Northwest Laboratory Parallel Pits waste site. This waste site consisted of two earthen trenches thought to have received both radioactive and nonradioactive material related to the 100-F Experimental Animal Farm.

Radiological effluents released from US continental tests, 1961 through 1992. Revision 1

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

Schoengold, C.R.; DeMarre, M.E.; Kirkwood, E.M.

1996-08-01

This report documents all continental tests from September 15, 1961, through September 23, 1992, from which radioactive effluents were released. The report includes both updated information previously published in the publicly available May, 1990 report, DOE/NV-317, ``Radiological Effluents Released from Announced US Continental Tests 1961 through 1988``, and effluent release information on formerly unannounced tests. General information provided for each test includes the date, time, location, type of test, sponsoring laboratory and/or agency or other sponsor, depth of burial, purpose, yield or yield range, extent of release (onsite only or offsite), and category of release (detonation-time versus post-test operations). Wheremore » a test with simultaneous detonations is listed, location, depth of burial and yield information are given for each detonation if applicable, as well as the specific source of the release. A summary of each release incident by type of release is included. For a detonation-time release, the effluent curies are expressed at R+12 hours. For a controlled releases from tunnel-tests, the effluent curies are expressed at both time of release and at R+12 hours. All other types are listed at the time of the release. In addition, a qualitative statement of the isotopes in the effluent is included for detonation-time and controlled releases and a quantitative listing is included for all other types. Offsite release information includes the cloud direction, the maximum activity detected in the air offsite, the maximum gamma exposure rate detected offsite, the maximum iodine level detected offsite, and the maximum distance radiation was detected offsite. A release summary incudes whatever other pertinent information is available for each release incident. This document includes effluent release information for 433 tests, some of which have simultaneous detonations. However, only 52 of these are designated as having offsite releases.« less

Therapeutic applications of radioactive (131)iodine: Procedures and incidents with capsules.

PubMed

Al Aamri, Marwa; Ravichandran, Ramamoorthy; Binukumar, John Pichy; Al Balushi, Naima

2016-01-01

Treatments for thyrotoxicosis and carcinoma thyroid are carried out by oral administration of radioactive iodine ((131)I) in the form of liquid or capsules. The liquid form of (131)I has higher risk factors such as vapourization, spillage and need for management of higher activity wastes. Use of (131)I in capsule form simplify procedures of handling compared to liquid form of (131)I. The guidelines of safe handling and quality assurance aspects for therapeutic use (131)I are well outlined by International Atomic Energy Agency (IAEA) reports. A few unusual incidents with I-131 capsules encountered in the past need to be highlighted from health physics point of view. In Royal Hospital, Oman, I-131 is imported in capsules, and the total activity handled/year steadily increased over 10 years. Discrete activities range from 185 MBq (5 mCi) up to 7.4 GBq (200 mCi). In four incidents deviations in standard operational procedures were recorded. Nature of incidents is described as follows: (1) After assay of activity, the capsule was directly put in the lead container with missing of inner cap. (2) Patient poured water in the Perspex tube, when the capsule was handed over to her, making an emergency situation. (3) In 3 high activity capsules (2 nos 2.96 GBq, 1 no. 4.26 GBq), observed sticky behavior in capsule holder on the 2(nd) day post receipt, which were in order on the 1(st) day. (4) A capsule could not be swallowed by a patient, which was taken back from the mouth. Monitoring of patient later did not show residual ingested activity. The report documents some of the unusual incidents for information to other centers engaged in such radioactive administrations.

Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Waste Disposal Facility

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

Ansley, Shannon Leigh

2002-02-01

The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering andmore » Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist.« less

78 FR 64049 - Information Collection Activities

Federal Register 2010, 2011, 2012, 2013, 2014

2013-10-25

... radioactive material being transported; external radiation levels do not exceed prescribed limits; and... radioactive materials in commerce. Annual Reporting and Recordkeeping Burden: Number of Respondents: 3,817... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No...

Nuclear waste disposal: Gambling on Yucca Mountain

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

Ginsburg, S.

1995-05-01

This document describes the historical aspects of nuclear energy ,nuclear weapons usage, and development of the nuclear bureaucracy in the United States, and discusses the selection and siting of Yucca Mountain, Nevada for a federal nuclear waste repository. Litigation regarding the site selection and resulting battles in the political arena and in the Nevada State Legislature are also presented. Alternative radioactive waste disposal options, risk assessments of the Yucca Mountain site, and logistics regarding the transportation and storage of nuclear waste are also presented. This document also contains an extensive bibliography.

Eleventh international CODATA conference, scientific and technical data in a new era, Karlsruhe, Federal Republic of Germany, 26--29 September 1988: Foreign trip report

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

Tichler, J.L.

Information on release of radioactive materials in airborne and liquid effluents, solid waste shipments and selected operating information from commercial nuclear power plants in the United States is maintained in a computer data base at Brookhaven National Laboratory (BNL) for the United States Nuclear Regulatory Commission (USNRC). The information entered into the data base is obtained from semiannual reports submitted by the operators of the plants to the USNRC in compliance with the USNRC Regulatory Guide 1.21, ''Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants.''more » The data on releases in the calendar year 1986 include information from 69 plants representing 87 reactors and contain approximately 19,000 entries. Since all the information is contained in a computer data base management system, entry and rapidly respond to inquiries about the data set and to generate computer readable subsets of the data. Such a subset is used as input to the computer program which generates the annual report, ''Population Dose Commitments Due to Radioactive Releases from Nuclear Power Plant Sites,'' prepared by Pacific Northwest Laboratory for the USNRC. BNL began maintaining this data base for the USNRC with the 1978 information and has added information to the data base for each succeeding year. An annual report summarizing the information for each year, prepared by BNL, and published by the USNRC, is available to the general public. Prior to 1978, annual reports were prepared by the USNRC and are available for the years 1972--1977; however, the information for these years is not in a computer accessible data base.« less

Nevada Applied Ecology Information Center: a review of technical information support provided to the Nevada Applied Ecology Group

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

Fore, C.S.; Pfuderer, H.A.

The Nevada Applied Ecology Information Center (NAEIC) was established in January 1972 to serve the needs of the Nevada Applied Ecology Group (NAEG) by identifying, collecting, analyzing, and disseminating technical information relevant to NAEG programs. Since its inception, the NAEIC has been active in providing specialized information support to NAEG staff in the following research areas: (1) environmental aspects of the transuranics; (2) historic literature (pre-1962) on plutonium and uranium; (3) cleanup and treatment of radioactively contaminated land; (4) bioenvironmental aspects of europium and rhodium; (5) NAEG contractor reports; and (6) uptake of radioactivity by food crops.

Transportation legislative data base : state radioactive materials transportation statute compilation, 1989-1993

DOT National Transportation Integrated Search

1994-04-30

The Transportation Legislative Data Base (TLDB) is a computer-based information service containing summaries of federal, state and certain local government statutes and regulations relating to the transportation of radioactive materials in the United...

Improved low-level radioactive waste management practices for hospitals and research institutions

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

Not Available

1983-07-01

This report provides a general overview and a compendium of source material on low-level radioactive waste management practices in the institutional sector. Institutional sector refers to hospitals, universities, clinics, and research facilities that use radioactive materials in scientific research and the practice of medicine, and the manufacturers of radiopharmaceuticals and radiography devices. This report provides information on effective waste management practices for institutional waste to state policymakers, regulatory agency officials, and waste generators. It is not intended to be a handbook for actual waste management, but rather a sourcebook of general information, as well as a survey of the moremore » detailed analysis.« less

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

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

Jo, J.

This document is a report of the analytical results for samples collected from the radioactive wastes in Tank 241-U-202 at the Hanford Reservation. Core samples were collected from the solid wastes in the tank and underwent safety screening analyses including differential scanning calorimetry, thermogravimetric analysis, and total alpha analysis. Results indicate that no safety screening notification limits were exceeded.

76 FR 40352 - National Nuclear Security Administration; Amended Record of Decision: Site-Wide Environmental...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-07-08

... similar to those estimated for transportation of radioactive material in other DOE NEPA documents. The air... radiological materials located at civilian sites worldwide. Part of the GTRI mission is implemented through... specific actions analyzed in DOE/EIS-0380-SA-02 include packaging the sealed sources (sometimes with a part...

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM- 2007

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

West, B; Ruel Waltz, R

2008-06-05

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. The 2007 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. A very small amount of material had seeped from Tank 12 from a previously identified leaksite. The material observed had dried on the tank wall and did not reach the annulus floor. A total of 5945 photographs were made and 1221 visual and video inspections were performed during 2007. Additionally, ultrasonic testing was performed on four Waste Tanksmore » (15, 36, 37 and 38) in accordance with approved inspection plans that met the requirements of WSRC-TR-2002- 00061, Revision 2 'In-Service Inspection Program for High Level Waste Tanks'. The Ultrasonic Testing (UT) In-Service Inspections (ISI) are documented in a separate report that is prepared by the ISI programmatic Level III UT Analyst. Tanks 15, 36, 37 and 38 are documented in 'Tank Inspection NDE Results for Fiscal Year 2007'; WSRC-TR-2007-00064.« less

10 CFR 60.71 - Records and reports.

Code of Federal Regulations, 2010 CFR

2010-01-01

... REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN GEOLOGIC REPOSITORIES Records... the Energy Reorganization Act. (b) Records of the receipt, handling, and disposition of radioactive waste at a geologic repository operations area shall contain sufficient information to provide a...

In Brief

ERIC Educational Resources Information Center

Journal of College Science Teaching, 1976

1976-01-01

Presents information on storage of radioactive wastes, the AAAS February meeting, an NSF publication on doctoral scientists and engineers, the Research Associateship programs of the National Research Council, the international congress on cybernetics, the effects of nuclear war on noncombatants, radioactivity in drinking water, and computer based…

10 CFR 61.11 - General information.

Code of Federal Regulations, 2010 CFR

2010-01-01

... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61...) Plans for use of the land disposal facility for purposes other than disposal of radioactive wastes; and..., and first emplacement of waste at the proposed land disposal facility. ...

10 CFR 61.11 - General information.

Code of Federal Regulations, 2012 CFR

2012-01-01

... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61...) Plans for use of the land disposal facility for purposes other than disposal of radioactive wastes; and..., and first emplacement of waste at the proposed land disposal facility. ...

10 CFR 61.11 - General information.

Code of Federal Regulations, 2011 CFR

2011-01-01

... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61...) Plans for use of the land disposal facility for purposes other than disposal of radioactive wastes; and..., and first emplacement of waste at the proposed land disposal facility. ...

10 CFR 61.11 - General information.

Code of Federal Regulations, 2013 CFR

2013-01-01

... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61...) Plans for use of the land disposal facility for purposes other than disposal of radioactive wastes; and..., and first emplacement of waste at the proposed land disposal facility. ...

10 CFR 61.11 - General information.

Code of Federal Regulations, 2014 CFR

2014-01-01

... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61...) Plans for use of the land disposal facility for purposes other than disposal of radioactive wastes; and..., and first emplacement of waste at the proposed land disposal facility. ...

Collaboration, Automation, and Information Management at Hanford High Level Radioactive Waste (HLW) Tank Farms

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

Aurah, Mirwaise Y.; Roberts, Mark A.

Washington River Protection Solutions (WRPS), operator of High Level Radioactive Waste (HLW) Tank Farms at the Hanford Site, is taking an over 20-year leap in technology, replacing systems that were monitored with clipboards and obsolete computer systems, as well as solving major operations and maintenance hurdles in the area of process automation and information management. While WRPS is fully compliant with procedures and regulations, the current systems are not integrated and do not share data efficiently, hampering how information is obtained and managed.

300 Area dangerous waste tank management system: Compliance plan approach. Final report

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

NONE

1996-03-01

In its Dec. 5, 1989 letter to DOE-Richland (DOE-RL) Operations, the Washington State Dept. of Ecology requested that DOE-RL prepare ``a plant evaluating alternatives for storage and/or treatment of hazardous waste in the 300 Area...``. This document, prepared in response to that letter, presents the proposed approach to compliance of the 300 Area with the federal Resource Conservation and Recovery Act and Washington State`s Chapter 173-303 WAC, Dangerous Waste Regulations. It also contains 10 appendices which were developed as bases for preparing the compliance plan approach. It refers to the Radioactive Liquid Waste System facilities and to the radioactive mixedmore » waste.« less

Extinct Radioactivities and the R-Process Jet

NASA Technical Reports Server (NTRS)

Cameron, A. G. W.

2001-01-01

All extinct radioactive species in the solar nebula were injected from a core-collapse supernova. I discuss primarily the products expected from an r-process jet in this supernova, and various supporting astrophysical observations. Additional information is contained in the original extended abstract.

Digital version of the European Atlas of natural radiation.

PubMed

Cinelli, Giorgia; Tollefsen, Tore; Bossew, Peter; Gruber, Valeria; Bogucarskis, Konstantins; De Felice, Luca; De Cort, Marc

2018-02-26

The European Atlas of Natural Radiation is a collection of maps displaying the levels of natural radioactivity caused by different sources. It has been developed and is being maintained by the Joint Research Centre (JRC) of the European Commission, in line with its mission, based on the Euratom Treaty: to collect, validate and report information on radioactivity levels in the environment of the EU Member States. This work describes the first version of the European Atlas of Natural Radiation, available in digital format through a web portal, as well as the methodology and results for the maps already developed. So far the digital Atlas contains: an annual cosmic-ray dose map; a map of indoor radon concentration; maps of uranium, thorium and potassium concentration in soil and in bedrock; a terrestrial gamma dose rate map; and a map of soil permeability. Through these maps, the public will be able to: familiarize itself with natural environmental radioactivity; be informed about the levels of natural radioactivity caused by different sources; have a more balanced view of the annual dose received by the European population, to which natural radioactivity is the largest contributor; and make direct comparisons between doses from natural sources of ionizing radiation and those from man-made (artificial) ones, hence, to better assess the latter. Work will continue on the European Geogenic Radon Map and on estimating the annual dose that the public may receive from natural radioactivity, by combining all the information from the different maps. More maps could be added to the Atlas, such us radon in outdoor air and in water and concentration of radionuclides in water, even if these sources usually contribute less to the total exposure. Copyright © 2018 The Authors. Published by Elsevier Ltd.. All rights reserved.

F-Tank Farm Performance Assessment Updates through the Special Analysis Process at Savannah River Site - 12169

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

Layton, Mark H.

2012-07-01

The F-Area Tank Farm (FTF) is owned by the U.S. Department of Energy and operated by Savannah River Remediation, LLC (SRR), Liquid Waste Operations contractor at DOE's Savannah River Site (SRS). The FTF is in the north-central portion of the SRS and occupies approximately 22 acres within F-Area. The FTF is an active radioactive waste storage facility consisting of 22 carbon steel waste tanks and ancillary equipment such as transfer lines, evaporators and pump tanks. An FTF Performance Assessment (PA) was prepared to support the eventual closure of the FTF underground radioactive waste tanks and ancillary equipment. The PA providesmore » the technical basis and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements identified below for final closure of FTF. The FTank Farm is subject to a state industrial waste water permit and Federal Facility Agreement. Closure documentation will include an F-Tank Farm Closure Plan and tank-specific closure modules utilizing information from the performance assessment. For this reason, the State of South Carolina and the Environmental Protection Agency must be involved in the performance assessment review process. The residual material remaining after tank cleaning is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005. The projected waste tank inventories in the FTF PA provide reasonably bounding FTF inventory projections while taking into account uncertainties in the effectiveness of future tank cleaning technologies. As waste is removed from the FTF waste tanks, the residual contaminants will be sampled and the remaining residual inventory is characterized. In this manner, tank specific data for the tank inventories at closure will be available to supplement the waste tank inventory projections currently used in the FTF PA. For FTF, the new tank specific data will be evaluated through the Special Analysis process. The FTF Special Analyses process will be utilized to evaluate information regarding the final residual waste that will be grouted in place in the FTF Tanks and assess the potential impact the new inventory information has on the FTF PA assumptions and results. The Special Analysis can then be used to inform decisions regarding FTF tank closure documents. The purpose of this paper is to discuss the Special Analysis process and share insights gained while implementing this process. An example of an area of interest in the revision process is balancing continuous improvement versus configuration control of agreed upon methodologies. Other subjects to be covered include: 1) defining the scope of the revisions included in the Special Analysis, 2) determining which PA results should be addressed in the Special Analysis, and 3) deciding whether the Special Analysis should utilize more qualitative or quantitative assessments. For the SRS FTF, an FTF PA has been prepared to provide the technical basis and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements for final closure of FTF. The FTF Special Analyses process will be utilized to evaluate the impact new information has on the FTF PA assumptions and results. The Special Analysis can then be used to inform decisions regarding FTF tank closure documents. In preparing SAs, it is crucial that the scope of the SA be well defined within the SA, since the specific scope will vary from SA to SA. Since the SAs are essentially addendums to the PA, the SA scope should utilize the PA as the baseline from which the SA scope is defined. The SA needs to focus on evaluating the change associated with the scope, and not let other changes interfere with the ability to perform that evaluation by masking the impact of the change. In preparing the SA, it is also important to let the scope determine whether the Special Analysis should utilize more qualitative or quantitative assessments and also which results from the PA should be addressed in the Special Analysis. These decisions can vary from SA and should not be predetermined. (author)« less

The g factor of the 21+ state in 126Sn

NASA Astrophysics Data System (ADS)

Kumbartzki, G. J.; Benczer-Koller, N.; Torres, D. A.; Gürdal, G.; Gross, C. J.; Galindo-Uribarri, A.; Bingham, C.; Stone, N.; Stuchberry, A. E.; Speidel, K.-H.

2011-10-01

In the quest to develop the necessary tools and gather experience in using the transient field technique to measure g factors of low-lying short-lived nuclear states in radioactive beam experiments, the 126Sn (t1/2 = 2 . 3 .105 years) will be measured at the HRIBF, ORNL. Each radioactive beam experiment presents its own set of problems and challenges due to the radioactive background from the beam and beam contaminants and their life times, and the low beam intensity. This experiment is a test with a very long lived, nearly stable beam. The target is designed to stop the reaction products in the backing of the target but to allow the bulk of the beam to pass through and stop in a foil placed between the target and the particle detector. This foil can be changed in the course of the experiment, should it become too radioactive. The experiment is scheduled to run in July 2011. Success or failure will provide a wealth of information on working in different radioactive environments and will extend the spectroscopic information on g factors of 21+states in Sn isotopes. The transient field measurement will provide the sign of the g factor.

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

Dehmel, J.C.; Loomis, D.; Mauro, J.

Under contract to the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, the firms of S. Cohen & Associates, Inc. (SC&A) and Eastern Research Group (ERG) have compiled a report that describes the physical, chemical, and radiological properties of Class-A low-level radioactive waste. The report also presents information characterizing various methods and facilities used to treat and dispose non-radioactive waste. A database management program was developed for use in accessing, sorting, analyzing, and displaying the electronic data provided by EG&G. The program was used to present and aggregate data characterizing the radiological, physical, and chemical properties of the wastemore » from descriptions contained in shipping manifests. The data thus retrieved are summarized in tables, histograms, and cumulative distribution curves presenting radionuclide concentration distributions in Class-A waste as a function of waste streams, by category of waste generators, and regions of the United States. The report also provides information characterizing methods and facilities used to treat and dispose non-radioactive waste, including industrial, municipal, and hazardous waste regulated under Subparts C and D of the Resource Conservation and Recovery Act (RCRA). The information includes a list of disposal options, the geographical locations of the processing and disposal facilities, and a description of the characteristics of such processing and disposal facilities. Volume 1 contains the Executive Summary, Volume 2 presents the Class-A waste database, Volume 3 presents the information characterizing non-radioactive waste management practices and facilities, and Volumes 4 through 7 contain Appendices A through P with supporting information.« less

Fracture mechanics based design for radioactive material transport packagings -- Historical review

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

Smith, J.A.; Salzbrenner, D.; Sorenson, K.

1998-04-01

The use of a fracture mechanics based design for the radioactive material transport (RAM) packagings has been the subject of extensive research for more than a decade. Sandia National Laboratories (SNL) has played an important role in the research and development of the application of this technology. Ductile iron has been internationally accepted as an exemplary material for the demonstration of a fracture mechanics based method of RAM packaging design and therefore is the subject of a large portion of the research discussed in this report. SNL`s extensive research and development program, funded primarily by the U. S. Department ofmore » Energy`s Office of Transportation, Energy Management and Analytical Services (EM-76) and in an auxiliary capacity, the office of Civilian Radioactive Waste Management, is summarized in this document along with a summary of the research conducted at other institutions throughout the world. In addition to the research and development work, code and standards development and regulatory positions are also discussed.« less

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

Layton, Deborah L.

The Toxic Substances Control Act, 40 CFR 761.65(a)(1) provides an exemption from the one year storage time limit for PCB/radioactive waste. PCB/radioactive waste may exceed the one year time limit provided that the provisions at 40 CFR 761.65(a)(2)(ii) and 40 CFR 761.65(a)(2)(iii) are followed. These two subsections require, (ii) "A written record documenting all continuing attempts to secure disposal is maintained until the waste is disposed of" and (iii) "The written record required by subsection (ii) of this section is available for inspection or submission if requested by EPA." EPA Region 10 has requested the Department of Energy (DOE) tomore » submit an inventory of radioactive-contaminated PCB waste in storage at the Idaho National Laboratory (INL) for the previous calendar year. The annual inventory is separated into two parts, INL without Advanced Mixed Waste Treatment Project (AMWTP) (this includes Battelle Energy Alliance, LLC, CH2M-WG Idaho, LLC, and the Naval Reactors Facility), and AMWTP.« less

Managing the nation`s nuclear waste. Site descriptions: Cypress Creek, Davis Canyon, Deaf Smith, Hanford Reference, Lavender Canyon, Richton Dome, Swisher, Vacherie Dome, and Yucca Mountain

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

NONE

1985-12-31

In 1982, the Congress enacted the Nuclear Waste Policy Act (Public Law 97-425), which established a comprehensive national program directed toward siting, constructing, and operating geologic repositories for the permanent disposal of high-level radioactive waste. In February 1983, the United States Department of Energy (DOE) identified the nine referenced repository locations as potentially acceptable sites for a mined geologic repository. These sites have been evaluated in accordance with the DOE`s General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. The DOE findings and determinations are based on the evaluations contained in the draft Environmental Assessments (EA). A finalmore » EA will be prepared after considering the comments received on the draft EA. The purpose of this document is to provide the public with specific site information on each potential repository location.« less

International development workshops. Final technical report

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

NONE

1997-08-06

The US Department of Energy (DOE) and the Nuclear Energy Agency of the Organization for Economic Cooperation and Development/Nuclear Energy Agency (OECD/NEA) began to act on their recognition of the importance of education in nuclear literacy, specifically in radioactive waste management (RWM), several years ago. To address this Goal for nuclear literacy, the US DOE; through the Information and Education Division of the Office of Civilian Radioactive Waste Management (OCRWM) and in cooperation with the OECD/NEA, organized an ``International Workshop on Education in the Field of Radioactive Waste Management`` in Engelberg, Switzerland in June of 1991. To this end, amore » grant to support nuclear literacy and RWM was written and funded by the OCRWM and the education division of the DOE Yucca Mountain Office in 1990. The over-riding Goal of that workshop and the DOE grant was to find ways of raising the level of nuclear literacy in the general public through educational programs in radioactive waste management (RWM). The two Main Objectives of the workshop were: first, to contribute to an information base for education systems, on global aspects of radioactive waste management; and second, to achieve international consensus on the basic tools and methods required to develop the information base. These two objectives also became the principal objectives of the DOE International Workshops grant. In other words, the global and local (Nevada) objectives were one and the same. Workshop overviews and accomplishments are summarized in this report.« less

Radiological environmental dose assessment methods and compliance dose results for 2015 operations at the Savannah River Site

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

Jannik, G. T.; Dixon, K. L.

This report presents the environmental dose assessment methods and the estimated potential doses to the offsite public from 2015 Savannah River Site (SRS) atmospheric and liquid radioactive releases. Also documented are potential doses from special-case exposure scenarios - such as the consumption of deer meat, fish, and goat milk.

10 CFR 110.70 - Public notice of receipt of an application.

Code of Federal Regulations, 2010 CFR

2010-01-01

... MATERIAL Public Notification and Availability of Documents and Records § 110.70 Public notice of receipt of... kilograms or more of heavy water. (4) Nuclear grade graphite for nuclear end use. (5) Radioactive waste. (Note: Does not apply to exports of heavy water to Canada.) (c) The Commission will also publish in the...

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

MCCOY, J.C.

This Safety Analysis Report for Packaging (SARP) provides a technical evaluation of the Sample Pig Transport System as compared to the requirements of the U.S. Department of Energy, Richland Operations Office (RL) Order 5480.1, Change 1, Chapter III. The evaluation concludes that the package is acceptable for the onsite transport of Type B, fissile excepted radioactive materials when used in accordance with this document.

Assessment of alpha radioactivity in lipstick, nailpolish, toothpaste and vermilion using CR-39 detector.

PubMed

Ghosh, Dipak; Deb, Argha; Maiti, Sunil; Haldar, Subrata; Bera, Sukumar; Sengupta, Rosalima; Bhaitacharyya, Rini

2010-04-01

Human beings are always exposed to radiation from chemical cosmetics. In order to collect information regarding the radioactivity of chemical cosmetics used in our daily life, we studied the alpha radioactivity in different cosmetics samples, such as lipsticks, nail-polish, toothpaste and vermilion. The significant accumulation ofradionuclide in and on the tissues, directly or indirectly exposed due to the lipsticks, toothpaste, vermilion, may cause health hazards. Different samples of these cosmetic materials (Indian and foreign brands) were collected from the local markets of Kolkata, India. CR-39--a useful solid state nuclear track detector (SSNTD) was used to detect alpha radioactivity of these samples. Such exhaustive measurement of radioactivity in lipsticks, nail-polish, toothpaste and vermilion has not been reported so far.

High Resolution 3d Imaging during the Construction of National Radioactive Waste Repository from BÁTAAPÁTI, Hungary

NASA Astrophysics Data System (ADS)

Gaich, A.; Deák, F.; Pötsch, M.

2012-12-01

The Hungarian National Radioactive Waste Repository is being built in the neighborhood of the village called Bátaapáti. The program of the new disposal facility for the low- and intermediate-level wastes (L/ILW) is conducted by PURAM (Public Limited Company for Radioactive Waste Management). The Bátaapáti underground research program began in February 2005, with the excavation of the two inclined exploratory tunnels. These tunnels have 30 m distance between their axes, 10% inclination and 1.7 km length, and have reached the 0 m Baltic sea-level in the Mórágy Granite Formation. The safety of nuclear repository mainly is influenced by the ground behaviour and its fracturing hence mapping of the geological features has a great importance. Because of the less stable ground, the cavern walls were shotcreted after every tunnelling advance. The site geologists were required to make the tunnel mapping after every drill and blast cycle. The time interval was short and the documenting work was unrepeatable due to the shotcrete supported walls, so it was very important to use a modern, precise system to create 3D photorealistic models of the rock surfaces on the excavated tunnel walls. We have chosen the photogrammetric method, because it has adequate resolution and quality for the photo combined 3D models. At the beginning, we had used the JointMetriX3D (JMX) system and subsequently ShapeMetriX3D (SMX) in the repository chamber excavation phase. From the acquired 3D images through geological mapping is performed as the system allows directly measuring geometric information on visible discontinuities such as dip and dip direction. Descriptive rock mass parameters such as spacing, area, roughness are instantly available. In this article we would like to continue that research having made by JMX model of a tunnel face of "TSZV" access tunnel and using SMX model of a tunnel face from "DEK" Chamber. Our studies were carried out by field engineering geologists on further investigation of the photorealistic 3D models reproducibility in the both cases JMX and SMX. Regularly geotechnical rock mass classifications (Q, RMR and GSI) were used on the basis of the 3D models without field experience of the given tunnel faces. All documentations were analysed with statistical methods considering the circumstances of scanning and picturing. The orientation of main characteristic discontinuities were defined by each geologist, but also some differences occured. These discrepancies had not occurred in the results of geotechnical evaluation. Due to several cases the information provided by the 3D modelling systems could be very useful in different phases of excavation works. These information were applied in geoscience researches for example in surface roughness determination, fracture system modelling of the host rock and geological or technical objects findings behind the shotcrete layer. Beside the above mentioned advanteges we have to emphasize that JMX and SMX systems provide contact free acqusition and assessment of rock and terrain surfaces by metric high resolution 3D images in very short time period.

Spatial database for the management of "urban geology" geothematic information: the case of Drama City, Greece

NASA Astrophysics Data System (ADS)

Pantelias, Eustathios; Zervakou, Alexandra D.; Tsombos, Panagiotis I.; Nikolakopoulos, Konstantinos G.

2008-10-01

The aggregation of population in big cities leads to the concentration of human activities, economic wealth, over consumption of natural resources and urban growth without planning and sustainable management. As a result, urban societies are exposed to various dangers and threats with economical, social, ecological - environmental impacts on the urban surroundings. Problems associated with urban development are related to their geological conditions and those of their surroundings, e.g. flooding, land subsidence, groundwater pollution, soil contamination, earthquakes, landslides, etc. For these reasons, no sustainable urban planning can be done without geological information support. The first systematic recording, codification and documentation of "urban geology" geothematic information in Greece is implemented by the Institute of Geological and Mineral Exploration (I.G.M.E.) in the frame of project "Collection, codification and documentation of geothematic information for urban and suburban areas in Greece - pilot applications". Through the implementation of this project, all geothematic information derived from geological mapping, geotechnical - geochemical - geophysical research and measurements in four pilot areas of Greece Drama (North Greece), Nafplio & Sparti (Peloponnesus) and Thrakomakedones (Attica) is stored and processed in specially designed geodatabases in GIS environment containing vector and raster data. For the specific GIS application ArcGIS Personal Geodatabase is used. Data is classified in geothematic layers, grouped in geothematic datasets (e.g. Topography, Geology - Tectonics, Submarine Geology, Technical Geology, Hydrogeology, Soils, Radioactive elements, etc) and being processed in order to produced multifunctional geothematic maps. All compiled data constitute the essential base for land use planning and environmental protection in specific urban areas. With the termination of the project the produced geodatabase and other digital data (thematic maps, DEMs) will be available to all, public or private sector, concerning geological environment in urban and suburban areas, being in charge of protection and improvement of natural and human made environment.

The Optimized Integration of the Decontamination Plan and the Radwaste Management Plan into Decommissioning Plan to the VVR-S Research Reactor from Romania

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

Barariu, G.

2008-07-01

The paper presents the progress of the Decontamination Plan and Radioactive Waste Management Plan which accompanies the Decommissioning Plan for research reactor VVR-S located in Magurele, Ilfov, near Bucharest, Romania. The new variant of the Decommissioning Plan was elaborated taking into account the IAEA recommendation concerning radioactive waste management. A new feasibility study for VVR-S decommissioning was also elaborated. The preferred safe management strategy for radioactive wastes produced by reactor decommissioning is outlined. The strategy must account for reactor decommissioning, as well as rehabilitation of the existing Radioactive Waste Treatment Plant and the upgrade of the Radioactive Waste Disposal Facilitymore » at Baita-Bihor. Furthermore, the final rehabilitation of the laboratories and reusing of cleaned reactor building is envisaged. An inventory of each type of radioactive waste is presented. The proposed waste management strategy is selected in accordance with the IAEA assistance. Environmental concerns are a part of the radioactive waste management strategy. In conclusion: The current version 8 of the Draft Decommissioning Plan which include the Integrated concept of Decontamination and Decommissioning and Radwaste Management, reflects the substantial work that has been incorporated by IFIN-HH in collaboration with SITON, which has resulted in substantial improvement in document The decommissioning strategy must take into account costs for VVR-S Reactor decommissioning, as well as costs for much needed refurbishments to the radioactive waste treatment plant and the Baita-Bihor waste disposal repository. Several improvements to the Baita-Bihor repository and IFIN-HH waste treatment facility were proposed. The quantities and composition of the radioactive waste generated by VVR-S Reactor dismantling were again estimated by streams and the best demonstrated practicable processing solution was proposed. The estimated quantities of materials to be managed in the near future raise some issues that need to be solved swiftly, such as treatment of aluminum and lead and graphite management. It is envisaged that these materials to be treated to Subsidiary for Nuclear Research (SCN) Pitesti. (authors)« less

Hanford High-Level Waste Vitrification Program at the Pacific Northwest National Laboratory: technology development - annotated bibliography

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

Larson, D.E.

1996-09-01

This report provides a collection of annotated bibliographies for documents prepared under the Hanford High-Level Waste Vitrification (Plant) Program. The bibliographies are for documents from Fiscal Year 1983 through Fiscal Year 1995, and include work conducted at or under the direction of the Pacific Northwest National Laboratory. The bibliographies included focus on the technology developed over the specified time period for vitrifying Hanford pretreated high-level waste. The following subject areas are included: General Documentation; Program Documentation; High-Level Waste Characterization; Glass Formulation and Characterization; Feed Preparation; Radioactive Feed Preparation and Glass Properties Testing; Full-Scale Feed Preparation Testing; Equipment Materials Testing; Meltermore » Performance Assessment and Evaluations; Liquid-Fed Ceramic Melter; Cold Crucible Melter; Stirred Melter; High-Temperature Melter; Melter Off-Gas Treatment; Vitrification Waste Treatment; Process, Product Control and Modeling; Analytical; and Canister Closure, Decontamination, and Handling« less

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

Bryan, Charles R.; Weck, Philippe F.; Vaughn, Palmer

Report RWEV-REP-001, Analysis of Postclosure Groundwater Impacts for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High Level Radioactive Waste at Yucca Mountain, Nye County, Nevada was issued by the DOE in 2009 and is currently being updated. Sandia National Laboratories (SNL) provided support for the original document, performing calculations and extracting data from the Yucca Mountain Performance Assessment Model that were used as inputs to the contaminant transport and dose calculations by Jason Associates Corporation, the primary developers of the DOE report. The inputs from SNL were documented in LSA-AR-037, Inputs to Jason Associates Corporation inmore » Support of the Postclosure Repository Supplemental Environmental Impact Statement. To support the updating of the original Groundwater Impacts document, SNL has reviewed the inputs provided in LSA-AR-037 to verify that they are current and appropriate for use. The results of that assessment are documented here.« less

76 FR 20489 - Occupational Radiation Protection

Federal Register 2010, 2011, 2012, 2013, 2014

2011-04-13

...-5865, e-mail: [email protected]hq.doe.gov . SUPPLEMENTARY INFORMATION: I. Background The requirements in... Exposure during Immersion in a Cloud of Airborne Radioactive Material. The calculations done for the 2007... absorbed by the body; they affect the worker only while immersed in a cloud of airborne radioactivity. A...

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

Waste Information Management System with 2012-13 Waste Streams - 13095

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

Upadhyay, H.; Quintero, W.; Lagos, L.

2013-07-01

The Waste Information Management System (WIMS) 2012-13 was updated to support the Department of Energy (DOE) accelerated cleanup program. The schedule compression required close coordination and a comprehensive review and prioritization of the barriers that impeded treatment and disposition of the waste streams at each site. Many issues related to waste treatment and disposal were potential critical path issues under the accelerated schedule. In order to facilitate accelerated cleanup initiatives, waste managers at DOE field sites and at DOE Headquarters in Washington, D.C., needed timely waste forecast and transportation information regarding the volumes and types of radioactive waste that wouldmore » be generated by DOE sites over the next 40 years. Each local DOE site historically collected, organized, and displayed waste forecast information in separate and unique systems. In order for interested parties to understand and view the complete DOE complex-wide picture, the radioactive waste and shipment information of each DOE site needed to be entered into a common application. The WIMS application was therefore created to serve as a common application to improve stakeholder comprehension and improve DOE radioactive waste treatment and disposal planning and scheduling. WIMS allows identification of total forecasted waste volumes, material classes, disposition sites, choke points, technological or regulatory barriers to treatment and disposal, along with forecasted waste transportation information by rail, truck and inter-modal shipments. The Applied Research Center (ARC) at Florida International University (FIU) in Miami, Florida, developed and deployed the web-based forecast and transportation system and is responsible for updating the radioactive waste forecast and transportation data on a regular basis to ensure the long-term viability and value of this system. (authors)« less

The discovery of radioactivity

NASA Astrophysics Data System (ADS)

Radvanyi, Pierre; Villain, Jacques

2017-11-01

The radioactivity of uranium was discovered in 1896 by Henri Becquerel who, starting from a wrong idea, progressively realized what he was observing, regularly informing the French Academy of Sciences of the progress he was doing. In the next years, it was found that thorium was radioactive too, and two new radioactive elements, polonium and radium, were discovered by Pierre and Marie Curie, while a third one, actinium, was identified by André Debierne. The study of the penetrating power and of the effect of electric and magnetic fields allowed scientists to demonstrate the complexity of nuclear radiation with its three components α, β, γ. The Comptes rendus de l'Académie des sciences allow the reader to see how difficult it was to understand the nature of radioactivity, which was essentially elucidated by Ernest Rutherford and Frederick Soddy.

Abundance and genetic damage of barn swallows from Fukushima

PubMed Central

Bonisoli-Alquati, A.; Koyama, K.; Tedeschi, D. J.; Kitamura, W.; Sukuzi, H.; Ostermiller, S.; Arai, E.; Møller, A. P.; Mousseau, T. A.

2015-01-01

A number of studies have assessed or modeled the distribution of the radionuclides released by the accident at the Fukushima-Daiichi Nuclear Power Plant (FDNPP). Few studies however have investigated its consequences for the local biota. We tested whether exposure of barn swallow (Hirundo rustica) nestlings to low dose ionizing radiation increased genetic damage to their peripheral erythrocytes. We estimated external radiation exposure by using thermoluminescent dosimeters, and by measuring radioactivity of the nest material. We then assessed DNA damage by means of the neutral comet assay. In addition, we conducted standard point-count censuses of barn swallows across environmental radiation levels, and estimated their abundance and local age ratio. Radioactivity of nest samples was in the range 479–143,349 Bq kg−1, while external exposure varied between 0.15 and 4.9 mGy. Exposure to radioactive contamination did not correlate with higher genetic damage in nestlings. However, at higher levels of radioactive contamination the number of barn swallows declined and the fraction of juveniles decreased, indicating lower survival and lower reproduction and/or fledging rate. Thus, genetic damage to nestlings does not explain the decline of barn swallows in contaminated areas, and a proximate mechanism for the demographic effects documented here remains to be clarified. PMID:25838205

Alarm inhalation dosemeter for long living radioactive dust due to an uncontrolled release

NASA Astrophysics Data System (ADS)

Streil, T.; Oeser, V.; Rambousky, R.; Buchholz, F. W.

2008-08-01

MyRIAM is the acronym for My Radioactivity In Air Monitor and points out that the device was designed for personal use to detect any radioactivity in the air at the place and at the moment of danger. The active air sampling process enables a detection limit several orders of magnitude below that of Gamma detectors. Therefore, it is the unique way to detect dangerous exposures in time. Individual protection against inhalation of long living radioactive dust (LLRD) saves human life and health. LLRD may occur in natural environment as well as in case of nuclear accidence or military and terrorist attacks. But in any case, the immediate warning of the population is of great importance. Keep in mind: it is very easy to avoid LLRD inhalation—but you have to recognize the imminent danger. The second requirement of gap-less documentation and reliable assessment of any derived LLRD exposure is building the link to Dosimetry applications. The paper demonstrates the possibility to design small and low cost air samplers, which can be used as personal alarm dosimeters and fulfil the requirements mentioned above. Several test measurements taken by a mobile phone sized MyRIAM, shall be used to demonstrate the correctness of this statement.

Information Strategy of Nuclear Training Center Ljubljana in the Area of Radioactive Waste Management

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

Jeneie, I.

2008-07-01

Slovenia has plans to build a repository for low- and medium-radioactive waste by 2013, the location in the very neighborhood of nuclear power plant is almost chosen, but the final approval hasn't been granted yet. The main obstacle is public opinion. Public information activities are therefore vitally important. One of the most important players in this area in Slovenia is Nuclear Training Center in Ljubljana. Though its main task is training of nuclear professionals, it has a significant role in dissemination of knowledge about radioactivity and nuclear technology also among general public. Public information is focused on youngsters. Almost onemore » half of every generation of schoolchildren in Slovenia visits the Information center yearly and in May 2007, we have celebrated the 100,000. visitor since its opening. Live lectures, exhibition, publications and laboratory demonstrations are offered. To measure the opinion of youngsters about nuclear power and get a feed-back for our activities about 1000 youngsters are polled every year since 1993 using the same basic set of questions. The paper describes the information strategy, types of lectures and information materials, permanent exhibition with the most important exhibits. Furthermore, the results of yearly polls of our visitors and comparison with relevant Euro-barometer polls are presented. (authors)« less

Radioactive Nanomaterials for Multimodality Imaging

PubMed Central

Chen, Daiqin; Dougherty, Casey A.; Yang, Dongzhi; Wu, Hongwei; Hong, Hao

2016-01-01

Nuclear imaging techniques, including primarily positron emission tomography (PET) and single-photon emission computed tomography (SPECT), can provide quantitative information for a biological event in vivo with ultra-high sensitivity, however, the comparatively low spatial resolution is their major limitation in clinical application. By convergence of nuclear imaging with other imaging modalities like computed tomography (CT), magnetic resonance imaging (MRI) and optical imaging, the hybrid imaging platforms can overcome the limitations from each individual imaging technique. Possessing versatile chemical linking ability and good cargo-loading capacity, radioactive nanomaterials can serve as ideal imaging contrast agents. In this review, we provide a brief overview about current state-of-the-art applications of radioactive nanomaterials in the circumstances of multimodality imaging. We present strategies for incorporation of radioisotope(s) into nanomaterials along with applications of radioactive nanomaterials in multimodal imaging. Advantages and limitations of radioactive nanomaterials for multimodal imaging applications are discussed. Finally, a future perspective of possible radioactive nanomaterial utilization is presented for improving diagnosis and patient management in a variety of diseases. PMID:27227167

The 9th international symposium on the packaging and transportation of radioactive materials

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

None

1989-06-01

This three-volume document contains the papers and poster sessions presented at the symposium. Volume 3 contains 87 papers on topics such as structural codes and benchmarking, shipment of plutonium by air, spent fuel shipping, planning, package design and risk assessment, package testing, OCRWN operations experience and regulations. Individual papers were processed separately for the data base. (TEM)

Onsite transportation of radioactive materials at the Savannah River Site

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

Watkins, R.

The Savannah River Site (SRS) Transportation Safety Document (TSD) defines the onsite packaging and transportation safety program at SRS and demonstrates its compliance with Department of Energy (DOE) transportation safety requirements, to include DOE Order 460.1C, DOE Order 461.2, Onsite Packaging and Transfer of Materials of National Security Interest, and 10 CFR 830, Nuclear Safety Management (Subpart B).

Cleanup Verification Package for the 118-F-5 PNL Sawdust Pit

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

L. D. Habel

2008-05-20

This cleanup verification package documents completion of remedial action, sampling activities, and compliance with cleanup criteria for the 118-F-5 Burial Ground, the PNL (Pacific Northwest Laboratory) Sawdust Pit. The 118-F-5 Burial Ground was an unlined trench that received radioactive sawdust from the floors of animal pens in the 100-F Experimental Animal Farm.

10 CFR 72.22 - Contents of application: General and financial information.

Code of Federal Regulations, 2011 CFR

2011-01-01

... INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN... of spent fuel, high-level radioactive waste, and/or reactor-related GTCC waste from storage. (f) Each applicant for a license under this part to receive, transfer, and possess power reactor spent fuel, power...

Obtaining and Investigating Unconventional Sources of Radioactivity

ERIC Educational Resources Information Center

Lapp, David R.

2010-01-01

This paper provides examples of naturally radioactive items that are likely to be found in most communities. Additionally, there is information provided on how to acquire many of these items inexpensively. I have found that the presence of these materials in the classroom is not only useful for teaching about nuclear radiation and debunking the…

Radiation Safety Aspects of Nanotechnology

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

Hoover, Mark; Myers, David; Cash, Leigh Jackson

This Report is intended primarily for operational health physicists, radiation safety officers, and internal dosimetrists who are responsible for establishing and implementing radiation safety programs involving radioactive nanomaterials. It should also provide useful information for workers, managers and regulators who are either working directly with or have other responsibilities related to work with radioactive nanomaterials.

Radiotherapy and Nuclear Medicine Project for an Integral Oncology Center at the Oaxaca High Specialization Regional Hospital

NASA Astrophysics Data System (ADS)

De Jesús, M.; Trujillo-Zamudio, F. E.

2010-12-01

A building project of Radiotherapy & Nuclear Medicine services (diagnostic and therapy), within an Integral Oncology Center (IOC), requires interdisciplinary participation of architects, biomedical engineers, radiation oncologists and medical physicists. This report focus on the medical physicist role in designing, building and commissioning stages, for the final clinical use of an IOC at the Oaxaca High Specialization Regional Hospital (HRAEO). As a first step, during design stage, the medical physicist participates in discussions about radiation safety and regulatory requirements for the National Regulatory Agency (called CNSNS in Mexico). Medical physicists propose solutions to clinical needs and take decisions about installing medical equipment, in order to fulfill technical and medical requirements. As a second step, during the construction stage, medical physicists keep an eye on building materials and structural specifications. Meanwhile, regulatory documentation must be sent to CNSNS. This documentation compiles information about medical equipment, radioactivity facility, radiation workers and nuclear material data, in order to obtain the license for the linear accelerator, brachytherapy and nuclear medicine facilities. As a final step, after equipment installation, the commissioning stage takes place. As the conclusion, we show that medical physicists are essentials in order to fulfill with Mexican regulatory requirements in medical facilities.

Decommissioning Handbook

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

Not Available

1994-03-01

The Decommissioning Handbook is a technical guide for the decommissioning of nuclear facilities. The decommissioning of a nuclear facility involves the removal of the radioactive and, for practical reasons, hazardous materials to enable the facility to be released and not represent a further risk to human health and the environment. This handbook identifies and technologies and techniques that will accomplish these objectives. The emphasis in this handbook is on characterization; waste treatment; decontamination; dismantling, segmenting, demolition; and remote technologies. Other aspects that are discussed in some detail include the regulations governing decommissioning, worker and environmental protection, and packaging and transportationmore » of the waste materials. The handbook describes in general terms the overall decommissioning project, including planning, cost estimating, and operating practices that would ease preparation of the Decommissioning Plan and the decommissioning itself. The reader is referred to other documents for more detailed information. This Decommissioning Handbook has been prepared by Enserch Environmental Corporation for the US Department of Energy and is a complete restructuring of the original handbook developed in 1980 by Nuclear Energy Services. The significant changes between the two documents are the addition of current and the deletion of obsolete technologies and the addition of chapters on project planning and the Decommissioning Plan, regulatory requirements, characterization, remote technology, and packaging and transportation of the waste materials.« less

Subsurface Contamination Control

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

Y. Yuan

There are two objectives of this report, ''Subsurface Contamination Control''. The first is to provide a technical basis for recommending limiting radioactive contamination levels (LRCL) on the external surfaces of waste packages (WP) for acceptance into the subsurface repository. The second is to provide an evaluation of the magnitude of potential releases from a defective WP and the detectability of the released contents. The technical basis for deriving LRCL has been established in ''Retrieval Equipment and Strategy for Wp on Pallet'' (CRWMS M and O 2000g, 6.3.1). This report updates the derivation by incorporating the latest design information of themore » subsurface repository for site recommendation. The derived LRCL on the external surface of WPs, therefore, supercede that described in CRWMS M and O 2000g. The derived LRCL represent the average concentrations of contamination on the external surfaces of each WP that must not be exceeded before the WP is to be transported to the subsurface facility for emplacement. The evaluation of potential releases is necessary to control the potential contamination of the subsurface repository and to detect prematurely failed WPs. The detection of failed WPs is required in order to provide reasonable assurance that the integrity of each WP is intact prior to MGR closure. An emplaced WP may become breached due to manufacturing defects or improper weld combined with failure to detect the defect, by corrosion, or by mechanical penetration due to accidents or rockfall conditions. The breached WP may release its gaseous and volatile radionuclide content to the subsurface environment and result in contaminating the subsurface facility. The scope of this analysis is limited to radioactive contaminants resulting from breached WPs during the preclosure period of the subsurface repository. This report: (1) documents a method for deriving LRCL on the external surfaces of WP for acceptance into the subsurface repository; (2) provides a table of derived LRCL for nuclides of radiological importance; (3) Provides an as low as is reasonably achievable (ALARA) evaluation of the derived LRCL by comparing potential onsite and offsite doses to documented ALARA requirements; (4) Provides a method for estimating potential releases from a defective WP; (5) Provides an evaluation of potential radioactive releases from a defective WP that may become airborne and result in contamination of the subsurface facility; and (6) Provides a preliminary analysis of the detectability of a potential WP leak to support the design of an airborne release monitoring system.« less

Radioactive Waste Management and Environmental Contamination Issues at the Chernobyl Site

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

Napier, Bruce A.; Schmieman, Eric A.; Voitsekhovitch, Oleg V.

2007-11-01

The destruction of the Unit 4 reactor at the Chernobyl Nuclear Power Plant resulted in the generation of radioactive contamination and radioactive waste at the site and in the surrounding area (referred to as the Exclusion Zone). In the course of remediation activities, large volumes of radioactive waste were generated and placed in temporary near surface waste-storage and disposal facilities. Trench and landfill type facilities were created from 1986 to 1987 in the Chernobyl Exclusion Zone at distances 0.5 to 15 km from the NPP site. This large number of facilities was established without proper design documentation, engineered barriers, ormore » hydrogeological investigations and they do not meet contemporary waste-safety requirements. Immediately following the accident, a Shelter was constructed over the destroyed reactor; in addition to uncertainties in stability at the time of its construction, structural elements of the Shelter have degraded as a result of corrosion. The main potential hazard of the Shelter is a possible collapse of its top structures and release of radioactive dust into the environment. A New Safe Confinement (NSC) with a 100-years service life is planned to be built as a cover over the existing Shelter as a longer-term solution. The construction of the NSC will enable the dismantlement of the current Shelter, removal of highly radioactive, fuel-containing materials from Unit 4, and eventual decommissioning of the damaged reactor. More radioactive waste will be generated during NSC construction, possible Shelter dismantling, removal of fuel containing materials, and decommissioning of Unit 4. The future development of the Exclusion Zone depends on the future strategy for converting Unit 4 into an ecologically safe system, i.e., the development of the NSC, the dismantlement of the current Shelter, removal of fuel containing material, and eventual decommissioning of the accident site. To date, a broadly accepted strategy for radioactive waste management at the reactor site and in the Exclusion Zone, and especially for high-level and long-lived waste, has not been developed.« less

Preparation and quantification of radioactive particles for tracking hydrodynamic behavior in multiphase reactors.

PubMed

Yunos, Mohd Amirul Syafiq Mohd; Hussain, Siti Aslina; Yusoff, Hamdan Mohamed; Abdullah, Jaafar

2014-09-01

Radioactive particle tracking (RPT) has emerged as a promising and versatile technique that can provide rich information about a variety of multiphase flow systems. However, RPT is not an off-the-shelf technique, and thus, users must customize RPT for their applications. This paper presents a simple procedure for preparing radioactive tracer particles created via irradiation with neutrons from the TRIGA Mark II research reactor. The present study focuses on the performance evaluation of encapsulated gold and scandium particles for applications as individual radioactive tracer particles using qualitative and quantitative neutron activation analysis (NAA) and an X-ray microcomputed tomography (X-ray Micro-CT) scanner installed at the Malaysian Nuclear Agency. Copyright © 2014 Elsevier Ltd. All rights reserved.

Environmental assessment of the thermal neutron activation explosive detection system for concourse use at US airports

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

Jones, C.G.

1990-08-01

This document is an environmental assessment of a system designed to detect the presence of explosives in checked airline baggage or cargo. The system is meant to be installed at the concourse or lobby ticketing areas of US commercial airports and uses a sealed radioactive source of californium-252 to irradiate baggage items. The major impact of the use of this system arises from direct exposure of the public to scattered or leakage radiation from the source and to induced radioactivity in baggage items. Under normal operation and the most likely accident scenarios, the environmental impacts that would be created bymore » the proposed licensing action would not be significant. 44 refs., 19 figs., 18 tabs.« less

Integrated Data Base Program: a status report

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

Notz, K.J.; Klein, J.A.

1984-06-01

The Integrated Data Base (IDB) Program provides official Department of Energy (DOE) data on spent fuel and radioactive waste inventories, projections, and characteristics. The accomplishments of FY 1983 are summarized for three broad areas: (1) upgrading and issuing of the annual report on spent fuel and radioactive waste inventories, projections, and characteristics, including ORIGEN2 applications and a quality assurance plan; (2) creation of a summary data file in user-friendly format for use on a personal computer and enhancing user access to program data; and (3) optimizing and documentation of the data handling methodology used by the IDB Program and providingmore » direct support to other DOE programs and sites in data handling. Plans for future work in these three areas are outlined. 23 references, 11 figures.« less

Final voluntary release assessment/corrective action report

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

NONE

1996-11-12

The US Department of Energy, Carlsbad Area Office (DOE-CAO) has completed a voluntary release assessment sampling program at selected Solid Waste Management Units (SWMUs) at the Waste Isolation Pilot Plant (WIPP). This Voluntary Release Assessment/Corrective Action (RA/CA) report has been prepared for final submittal to the Environmental protection Agency (EPA) Region 6, Hazardous Waste Management Division and the New Mexico Environment Department (NMED) Hazardous and Radioactive Materials Bureau to describe the results of voluntary release assessment sampling and proposed corrective actions at the SWMU sites. The Voluntary RA/CA Program is intended to be the first phase in implementing the Resourcemore » Conservation and Recovery Act (RCRA) Facility Investigation (RFI) and corrective action process at the WIPP. Data generated as part of this sampling program are intended to update the RCRA Facility Assessment (RFA) for the WIPP (Assessment of Solid Waste Management Units at the Waste Isolation Pilot Plant), NMED/DOE/AIP 94/1. This Final Voluntary RA/CA Report documents the results of release assessment sampling at 11 SWMUs identified in the RFA. With this submittal, DOE formally requests a No Further Action determination for these SWMUs. Additionally, this report provides information to support DOE`s request for No Further Action at the Brinderson and Construction landfill SWMUs, and to support DOE`s request for approval of proposed corrective actions at three other SWMUs (the Badger Unit Drill Pad, the Cotton Baby Drill Pad, and the DOE-1 Drill Pad). This information is provided to document the results of the Voluntary RA/CA activities submitted to the EPA and NMED in August 1995.« less

Assessing the Effectiveness of Risk Communication for Maintenance Workers Who Deal With Induced Radioactivity Management of Medical Linear Accelerators.

PubMed

Watanabe, Hiroshi; Maehara, Yoshiaki; Fujibuchi, Toshioh; Koizumi, Mitsue; Yamaguchi, Ichiro; Kida, Tetsuo; Ooyama, Masaya; Horitsugi, Genki; Hiraki, Hitoshi; Tsukamoto, Atsuko; Itami, Jyun

2015-08-01

In Japan, an amended law that mandates levels of unintended induced radioactivity has been in effect since 1 April 2012. According to the new regulation, if the concentration of induced radioactivity in affected parts is above the clearance level, the parts must be regarded as radioactive even if they weigh less than 1 kg. This regulation reform raises several new issues concerning medical linear accelerators, including how to determine the decay period for induced radioactivity before maintenance can be performed and how to identify what parts should be considered radioactive waste. The authors performed several risk communication (RC) activities aimed at improving the understanding of maintenance workers at medical accelerator manufacturers and establishing good guidelines by involving stakeholders. For this purpose, a working group was established and conducted RC activities, such as holding opinion exchange meetings between medical staff and maintenance workers and creating a booklet to answer questions from maintenance workers. To evaluate these activities, three questionnaire surveys were conducted between 2011 and 2014. According to the results of this study, the ratio of maintenance workers who accepted "The decay period is within one week" was approximately 60% at the third survey and significantly increased (P < 0.0001) during the survey period. Approximately 25% of the maintenance workers felt that not enough information was provided about the decay period, and approximately 63% thought that the information provided on the health effects of radiation was sufficient. These results suggest that the present RC was successful.

10 CFR 40.27 - General license for custody and long-term care of residual radioactive material disposal sites.

Code of Federal Regulations, 2010 CFR

2010-01-01

... disposed. In such cases, the Commission shall grant a license permitting use of the land if it finds that... the disposal site to be licensed, including documentation on whether land and interests are owned by the United States or an Indian tribe. If the site is on Indian land, then, as specified in the Uranium...

Proceedings of the tenth annual DOE low-level waste management conference: Session 2: Site performance assessment

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

Not Available

1988-12-01

This document contains twelve papers on various aspects of low-level radioactive waste management. Topics of this volume include: performance assessment methodology; remedial action alternatives; site selection and site characterization procedures; intruder scenarios; sensitivity analysis procedures; mathematical models for mixed waste environmental transport; and risk assessment methodology. Individual papers were processed separately for the database. (TEM)

36 CFR 1193.33 - Information, documentation, and training.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 36 Parks, Forests, and Public Property 3 2010-07-01 2010-07-01 false Information, documentation... Accessibility and Usability § 1193.33 Information, documentation, and training. (a) Manufacturers shall ensure access to information and documentation it provides to its customers. Such information and documentation...

Spent Sealed Sources Management in Switzerland - 12011

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

Beer, H.F.

2012-07-01

Information is provided about the international recommendations for the safe management of disused and spent sealed radioactive sources wherein the return to the supplier or manufacturer is encouraged for large radioactive sources. The legal situation in Switzerland is described mentioning the demand of minimization of radioactive waste as well as the situation with respect to the interim storage facility at the Paul Scherrer Institute (PSI). Based on this information and on the market situation with a shortage of some medical radionuclides the management of spent sealed sources is provided. The sources are sorted according to their activity in relation tomore » the nuclide-specific A2-value and either recycled as in the case of high active sources or conditioned as in the case for sources with lower activity. The results are presented as comparison between recycled and conditioned activity for three selected nuclides, i.e. Cs-137, Co-60 and Am-241. (author)« less

Radiation Protection. Measurement of radioactivity in the environment - Air- radon 222. A proposed ISO standard.

NASA Astrophysics Data System (ADS)

Gillmore, G.; Woods, M.

2009-04-01

Radon isotopes (222, 220, 219) are radioactive gases produced by the disintegration of radium isotopes 226, 224 and 223, which are decay products of uranium238, thorium232 and uranium235 respectively. All are found in the earth's crust. Solid elements, also radioactive, are produced by radon disintegration. Radon is classed as a rare gas in the periodic table of elements, along with helium, argon, neon, krypton and xenon. When disintegrating, radon emits alpha particles and generates solid decay products, which are also radioactive (polonium, bismuth, lead etc.). The potential danger of radon lies in its solid decay products rather than the gas itself. Whether or not they are attached aerosols, radon decay products can be inhaled and deposited in the bronchopulmonary tree to varying depths according to their size. Radon today is considered to be the main source of human exposure to natural radiation. At the international level, radon accounts for 52% of global average exposure to natural radiation. Isotope 222 (48%) is far more significant than isotope 220 (4%), whilst isotope 219 is considered as negligible. Exposure to radon varies considerably from one region to another, depending on factors such as weather conditions, and underlying geology. Activity concentration can therefore vary by a factor of 10 or even a 100 from one period of time to the next and from one area to another. There are many ways of measuring the radon 222 activity concentration and the potential alpha energy concentration of its short-lived decay products. Measuring techniques fall into three categories: - spot measurement methods; continuous measurement; integrated measurement. The proposed ISO (International Organisation for Standardisation) document suggests guidelines for measuring radon222 activity concentration and the potential alpha energy concentration of its short-lived decay products in a free (environment) and confined (buildings) atmosphere. The target date for availability of this work item is 2011. The ISO document here highlighted is a working draft. ISO is a worldwide federation of national standards bodies. Keywords: radon; international standards; measurement techniques.

Airborne radioactivity survey of parts of Atlantic Ocean beach, Virginia to Florida

USGS Publications Warehouse

Moxham, R.M.; Johnson, R.W.

1953-01-01

The accompanying maps show the results of an airborne radioactivity survey along the Atlantic Ocean beach from Cape Henry, Virginia to Cape Fear, North Carolina and from Savannah Bach Georgia to Miami Beach, Florida. The survey was made March 23-24, 1953, as part of a cooperative program with the U.S. Atomic Energy Commission. The survey was made with scintillation detection equipment mounted in a Douglas DC-3 aircraft and consisted of one flight line, at a 500-foot altitude, parallel to the beach. The vertical projection of the flight line coincided approximately with the landward limit of the modern beach. The width of the zone on the ground from which anomalous radiation is measured at the normal 500 foot flight altitude varies with the areal extent radioactivity of the source. For strong sources of radioactivity the width of the zone would be as much as 1,400 feet. The location of the flight lines is shown on the index map below. No abnormal radioactivity was detected along the northern flight line between Cape Henry, Virginia and Cape Fear, North Carolina. Along the southern flight line fourteen areas of abnormal radioactivity were detected between Savannah Beach, Georgia and Anastasia Island, Florida as shown on the map on the left. The abnormal radioactivity is apparently due to radioactive minerals associated with "black sand" deposits with occur locally along the beach in this region. The present technique of airborne radioactivity measurement does not permit distinguishing between activity sue to thorium and that due to uranium. An anomaly, therefore, may represent radioactivity due entirely to one or to a combination of these elements. It is not possible to determine the extent or radioactive content of the materials responsible for the abnormal radioactivity. The information given on the accompanying map indicates only those localities of greater-than-average radioactivity and, therefore suggest areas in which uranium and thorium deposits are more likely to occur.

Report on Maternal Anxiety 16 Months After the Great East Japan Earthquake Disaster: Anxiety Over Radioactivity

PubMed Central

Yoshii, Hatsumi; Saito, Hidemitsu; Kikuchi, Saya; Ueno, Takashi; Sato, Kineko

2014-01-01

The Great East Japan Earthquake occurred on March 11, 2011. The tsunami caused extensive damage to the Fukushima Daiichi Nuclear Power Plant, resulting in a level 7 nuclear accident. Among those affected by this combined disaster were many pregnant and parturient women. Sixteen months after the earthquake, we conducted a questionnaire survey on anxiety among 259 women who gave birth around the time of the earthquake in Miyagi Prefecture, one of the affected areas. Participants reported 12 categories of anxiety, including anxiety over radioactivity. This study aimed to determine anxiety over radioactivity among this specific population and to record measures for future study. Anxiety over radiation was classified into seven subcategories: food safety, outdoor safety, effects on the fetuses of pregnant women, effects on children, radiation exposure, economic problems, and distrust of information disclosed. This study confirmed that concrete types of anxiety over radiation were keenly felt by mothers who had experienced the disaster who were currently raising children. The findings suggest the need to provide accurate information to these mothers, who are otherwise inundated with miscellaneous confusing information. PMID:25363115

Report on maternal anxiety 16 months after the great East Japan earthquake disaster: anxiety over radioactivity.

PubMed

Yoshii, Hatsumi; Saito, Hidemitsu; Kikuchi, Saya; Ueno, Takashi; Sato, Kineko

2014-06-25

The Great East Japan Earthquake occurred on March 11, 2011. The tsunami caused extensive damage to the Fukushima Daiichi Nuclear Power Plant, resulting in a level 7 nuclear accident. Among those affected by this combined disaster were many pregnant and parturient women. Sixteen months after the earthquake, we conducted a questionnaire survey on anxiety among 259 women who gave birth around the time of the earthquake in Miyagi Prefecture, one of the affected areas. Participants reported 12 categories of anxiety, including anxiety over radioactivity. This study aimed to determine anxiety over radioactivity among this specific population and to record measures for future study. Anxiety over radiation was classified into seven subcategories: food safety, outdoor safety, effects on the fetuses of pregnant women, effects on children, radiation exposure, economic problems, and distrust of information disclosed. This study confirmed that concrete types of anxiety over radiation were keenly felt by mothers who had experienced the disaster who were currently raising children. The findings suggest the need to provide accurate information to these mothers, who are otherwise inundated with miscellaneous confusing information.

Fallout: The experiences of a medical team in the care of a Marshallese population accidently exposed to fallout radiation

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

Conard, R.A.

1992-09-01

This report presents an historical account of the experiences of the Brookhaven Medical Team in the examination and treatment of the Marshallese people following their accidental exposure to radioactive fallout in 1954. This is the first time that a population has been heavily exposed to radioactive fallout, and even though this was a tragic mishap, the medical findings have provided valuable information for other accidents involving fallout such as the recent reactor accident at Chernobyl. Noteworthy has been the unexpected importance of radioactive iodine in the fallout in producing thyroid abnormalities.

Fallout: The experiences of a medical team in the care of a Marshallese population accidentally exposed to fallout radiation

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

Conard, R.A.

1991-12-31

This report presents an historical account of the experiences of the Brookhaven Medical team in the examination and treatment of the Marshallese people following their accidental exposure to radioactive fallout in 1954. This is the first time that a population has been heavily exposed to radioactive fallout, and even though this was a tragic mishap, the medical findings have provided valuable information for other accidents involving fallout such as the recent reactor accident at Chernobyl. Particularly important has been the unexpected importance of radioactive iodine in the fallout in producing thyroid abnormalities.

Fallout: The experiences of a medical team in the care of a Marshallese population accidentally exposed to fallout radiation

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

Conard, R.A.

1991-01-01

This report presents an historical account of the experiences of the Brookhaven Medical team in the examination and treatment of the Marshallese people following their accidental exposure to radioactive fallout in 1954. This is the first time that a population has been heavily exposed to radioactive fallout, and even though this was a tragic mishap, the medical findings have provided valuable information for other accidents involving fallout such as the recent reactor accident at Chernobyl. Particularly important has been the unexpected importance of radioactive iodine in the fallout in producing thyroid abnormalities.

78 FR 7815 - Agency Information Collection Activities; Submission for OMB Review; Comment Request; Gamma...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-02-04

... Labor (DOL) is submitting the Mine Safety and Health Administration (MSHA) sponsored information.... This requirement protects the health of workers in mines with radioactive ores. This information... DEPARTMENT OF LABOR Office of the Secretary Agency Information Collection Activities; Submission...

10 CFR 61.15 - Financial information.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Financial information. 61.15 Section 61.15 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.15 Financial information. The financial information must be sufficient to demonstrate that the...

10 CFR 61.15 - Financial information.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Financial information. 61.15 Section 61.15 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.15 Financial information. The financial information must be sufficient to demonstrate that the...

10 CFR 61.15 - Financial information.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Financial information. 61.15 Section 61.15 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.15 Financial information. The financial information must be sufficient to demonstrate that the...

10 CFR 61.15 - Financial information.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Financial information. 61.15 Section 61.15 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.15 Financial information. The financial information must be sufficient to demonstrate that the...

10 CFR 61.15 - Financial information.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Financial information. 61.15 Section 61.15 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.15 Financial information. The financial information must be sufficient to demonstrate that the...

Deciphering the Measured Ratios of Iodine-131 to Cesium-137 at the Fukushima Reactors

NASA Astrophysics Data System (ADS)

Matsui, T.

2011-12-01

We calculate the relative abundance of the radioactive isotopes Iodine-131 and Cesium-137 produced by nuclear fission in reactors and compare it with data taken at the troubled Fukushima Dai-ichi nuclear power plant. The ratio of radioactivities of these two isotopes can be used to obtain information about when the nuclear reactions terminated.

Radiochemistry in the twenty-first century: Strenghts, weaknesses, opportunities and threats

NASA Astrophysics Data System (ADS)

de Goeij, J. J. M.

2003-01-01

Strengths, weaknesses, opportunities and threats of radiochemistry and associated nuclear chemistry are discussed. For that purpose radiochemistry is subdivided into three categories. The first category covers fundamental aspects, e.g. nuclear reaction cross-sections, production routes with associated yields and radionuclidic impurities, decay schemes, radiochemical separations, recoil and hot-atom chemistry, isotope effects and fractionation, and interaction of radiation with matter and detection. The second category covers topics where radioactivity is inextricably involved, e.g. the nuclear fuel cycle, very heavy elements and other actinides, primordial and cosmogenic radioactivity, and radionuclide techniques for dating. The third category involves radioactivity as essential part of a technique. On one hand radioactivity is used here as source of ionising radiation for food conservation, polymerisation of plastics, sterilisation, radiotherapy and pain palliation. On the other hand it is used to get information on systems and materials, via radiotracer methods and nuclear activation techniques. In particular the latter field is experiencing strong competition with other, non-nuclear methods. In this frame it is indicated what is required to achieve a situation where nuclear analytical techniques may successfully be exploited to the full extent of their potentials, particularly in providing valuable and sometimes unique information.

Nuclear regulatory legislation: 102d Congress. Volume 1, No. 2

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

Not Available

1993-10-01

This document is a compilation of nuclear regulatory legislation and other relevant material through the 102d Congress, 2d Session. This compilation has been prepared for use as a resource document, which the NRC intends to update at the end of every Congress. The contents of NUREG-0980 include: The Atomic Energy Act of 1954, as amended; Energy Reorganization Act of 1974, as amended, Uranium Mill Tailings Radiation Control Act of 1978; Low-Level Radioactive Waste Policy Act; Nuclear Waste Policy Act of 1982; and NRC Authorization and Appropriations Acts. Other materials included are statutes and treaties on export licensing, nuclear non-proliferation, andmore » environmental protection.« less

Nuclear regulatory legislation, 102d Congress. Volume 2, No. 2

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

Not Available

1993-10-01

This document is a compilation of nuclear regulatory legislation and other relevant material through the 102d Congress, 2d Session. This compilation has been prepared for use as a resource document, which the NRC intends to update at the end of every Congress. The contents of NUREG-0980 include The Atomic Energy Act of 1954, as amended; Energy Reorganization Act of 1974, as amended, Uranium Mill Tailings Radiation Control Act of 1978; Low-Level Radioactive Waste Policy Act; Nuclear Waste Policy Act of 1982; and NRC Authorization and Appropriations Acts. Other materials included are statutes and treaties on export licensing, nuclear non-proliferation, andmore » environmental protection.« less

Structural analysis of color video camera installation on tank 241AW101 (2 Volumes)

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

Strehlow, J.P.

1994-08-24

A video camera is planned to be installed on the radioactive storage tank 241AW101 at the DOE` s Hanford Site in Richland, Washington. The camera will occupy the 20 inch port of the Multiport Flange riser which is to be installed on riser 5B of the 241AW101 (3,5,10). The objective of the project reported herein was to perform a seismic analysis and evaluation of the structural components of the camera for a postulated Design Basis Earthquake (DBE) per the reference Structural Design Specification (SDS) document (6). The detail of supporting engineering calculations is documented in URS/Blume Calculation No. 66481-01-CA-03 (1).

LLWnotes - Volume 11, Number 3

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

NONE

1996-04-01

This document is the April 1996 issue of LLWnotes. It contains articles and news items on the following topics: news items related to states and compacts, Low-Level Radioactive Waste (LLW) Forum activities, and court rulings and calendars. State and compact items featured include Texas licensing procedures, renewal of Envirocare`s license, and Ward Valley. Massachusetts Board suspension of some siting tasks and Massachusetts Court rules for US DOE regarding rebates are also reported.

Guidebook for Preparation of Aircraft System Survivability Requirements for Procurement Documents.

DTIC Science & Technology

1977-05-01

Hardening for Electrical arid Electronic EqJuipment .. ... .... .... ..... 91 8.6.5~ Crew Protection from Radioactive Particulate Matter .. ... ..... 93...compatible with the subject matter of the individual sections. These guidelines present alternate language for both general requirements and specific...relation to the threat." 18 I. # . .. . ..o JTCG/AS-77-D-001 "’ Pasive IR suppression will be designed into the air vehicle utilizing a combination of hot

Deep Borehole Field Test Conceptual Design Report

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

Hardin, Ernest L.

This report documents conceptual design development for the Deep Borehole Field Test (DBFT), including test packages (simulated waste packages, not containing waste) and a system for demonstrating emplacement and retrieval of those packages in the planned Field Test Borehole (FTB). For the DBFT to have demonstration value, it must be based on conceptualization of a deep borehole disposal (DBD) system. This document therefore identifies key options for a DBD system, describes an updated reference DBD concept, and derives a recommended concept for the DBFT demonstration. The objective of the DBFT is to confirm the safety and feasibility of the DBDmore » concept for long-term isolation of radioactive waste. The conceptual design described in this report will demonstrate equipment and operations for safe waste handling and downhole emplacement of test packages, while contributing to an evaluation of the overall safety and practicality of the DBD concept. The DBFT also includes drilling and downhole characterization investigations that are described elsewhere (see Section 1). Importantly, no radioactive waste will be used in the DBFT, nor will the DBFT site be used for disposal of any type of waste. The foremost performance objective for conduct of the DBFT is to demonstrate safe operations in all aspects of the test.« less

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

Casbon, M. A.; Nichols, W. E.

DOE O 435.1, Radioactive Waste Management, and DOE M 435.1-1, Radioactive Waste Management Manual, require that a determination of continued adequacy of the performance assessment (PA), composite analysis (CA), and disposal authorization statement (DAS) be made on an annual basis, and it must consider the results of data collection and analysis from research, field studies, and monitoring. Annual summaries of low-level waste (LLW) disposal operations must be prepared with respect to the conclusions and recommendations of the PA and CA, and a determination of the need to revise the PA or CA must be made. The annual summary requirement providesmore » a structured approach for demonstrating the continued adequacy of the PA and CA in demonstrating a reasonable expectation that the performance objectives will be met. This annual summary addresses only the status of the Environmental Restoration Disposal Facility (ERDF) PA (CP-60089, Performance Assessment for the Environmental Restoration Disposal Facility, Hanford Site, Washington, formerly WCH-520 Rev. 1)1. The CA for ERDF is supported by DOE/RL-2016-62, Annual Status Report (FY 2016): Composite Analysis of Low Level Waste Disposal in the Central Plateau at the Hanford Site. The ERDF PA portion of the CA document is found in Section 3.1.4, and the ERDF operations portion is found in Section 3.3.3.2 of that document.« less

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

10 CFR 60.10 - Completeness and accuracy of information.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Completeness and accuracy of information. 60.10 Section 60.10 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN GEOLOGIC REPOSITORIES General Provisions § 60.10 Completeness and accuracy of information. (a) Information...

36 CFR 1194.41 - Information, documentation, and support.

Code of Federal Regulations, 2010 CFR

2010-07-01

... TRANSPORTATION BARRIERS COMPLIANCE BOARD ELECTRONIC AND INFORMATION TECHNOLOGY ACCESSIBILITY STANDARDS Information, Documentation, and Support § 1194.41 Information, documentation, and support. (a) Product support... 36 Parks, Forests, and Public Property 3 2010-07-01 2010-07-01 false Information, documentation...

Communicating Performance Assessments Results - 13609

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

Layton, Mark

2013-07-01

The F-Area Tank Farms (FTF) and H-Area Tank Farm (HTF) are owned by the U.S. Department of Energy (DOE) and operated by Savannah River Remediation LLC (SRR), Liquid Waste Operations contractor at DOE's Savannah River Site (SRS). The FTF and HTF are active radioactive waste storage and treatment facilities consisting of 51 carbon steel waste tanks and ancillary equipment such as transfer lines, evaporators and pump tanks. Performance Assessments (PAs) for each Tank Farm have been prepared to support the eventual closure of the underground radioactive waste tanks and ancillary equipment. PAs provide the technical bases and results to bemore » used in subsequent documents to demonstrate compliance with the pertinent requirements for final closure of the Tank Farms. The Tank Farms are subject to a number of regulatory requirements. The State regulates Tank Farm operations through an industrial waste water permit and through a Federal Facility Agreement approved by the State, DOE and the Environmental Protection Agency (EPA). Closure documentation will include State-approved Tank Farm Closure Plans and tank-specific closure modules utilizing information from the PAs. For this reason, the State of South Carolina and the EPA must be involved in the performance assessment review process. The residual material remaining after tank cleaning is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005. PAs are performance-based, risk-informed analyses of the fate and transport of FTF and HTF residual wastes following final closure of the Tank Farms. Since the PAs serve as the primary risk assessment tools in evaluating readiness for closure, it is vital that PA conclusions be communicated effectively. In the course of developing the FTF and HTF PAs, several lessons learned have emerged regarding communicating PA results. When communicating PA results it is important to stress that the primary goal of the PA results is to provide risk understanding, recognizing the magnitude of risk and identifying the conceptual model decisions and critical assumptions that most impact the results. Conceptual models that describe reality using simplified, mathematical approaches, and their roles in arriving at the PA results, must also be communicated. When presenting PA results, evaluations will typically be focused on a single baseline (or Base Case) to provide a foundation for discussion. The PA results are supplemented by other studies (alternate configurations, uncertainty analyses, and sensitivity analyses) which provide a breadth of modeling to supplement the Base Case. The suite of information offered by the various modeling cases and studies provides confidence that the overall risk is understood along with the underlying parameters and conditions that contribute to risk. (author)« less

ORNL Remedial Action Program strategy (FY 1987-FY 1992)

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

Trabalka, J.R.; Myrick, T.E.

1987-12-01

Over 40 years of Oak Ridge National Laboratory (ORNL) operations have produced a diverse legacy of contaminated inactive facilities, research areas, and waste disposal areas that are potential candidates for remedial action. The ORNL Remedial Action Program (RAP) represents a comprehensive effort to meet new regulatory requirements and ensure adequate protection of on-site workers, the public, and the environment by providing appropriate corrective measures at over 130 sites contaminated historically with radioactive, hazardous chemical, or mixed wastes. A structured path of program planning, site characterization, alternatives assessment, technology development, engineering design, continued site maintenance and surveillance, interim corrective action, andmore » eventual site closure or decommissioning is required to meet these objectives. This report documents the development of the Remedial Action Program, through its preliminary characterization, regulatory interface, and strategy development activities. It provides recommendations for a comprehensive, long-term strategy consistent with existing technical, institutional, and regulatory information, along with a six-year plan for achieving its initial objectives. 53 refs., 8 figs., 12 tabs.« less

Geologic and geophysical characterization studies of Yucca Mountain, Nevada, a potential high-level radioactive-waste repository

USGS Publications Warehouse

Whitney, J.W.; Keefer, W.R.

2000-01-01

In recognition of a critical national need for permanent radioactive-waste storage, Yucca Mountain in southwestern Nevada has been investigated by Federal agencies since the 1970's, as a potential geologic disposal site. In 1987, Congress selected Yucca Mountain for an expanded and more detailed site characterization effort. As an integral part of this program, the U.S. Geological Survey began a series of detailed geologic, geophysical, and related investigations designed to characterize the tectonic setting, fault behavior, and seismicity of the Yucca Mountain area. This document presents the results of 13 studies of the tectonic environment of Yucca Mountain, in support of a broad goal to assess the effects of future seismic and fault activity in the area on design, long-term performance, and safe operation of the potential surface and subsurface repository facilities.

Long-term surveillance plan for the Bodo Canyon Disposal Site, Durango, Colorado

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

Not Available

1994-03-01

This long-term surveillance plan (LTSP) for the Durango, Colorado, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Durango (Bodo Canyon) disposal site, which will be referred to as the disposal site throughout this document. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal site continues to function as designed. This LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM). RRMs include tailings and other uranium ore processing wastesmore » still at the site, which the DOE determines to be radioactive. This LTSP is based on the DOE`s Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992).« less

Compendium of federal and state radioactive materials transportation laws and regulations: Transportation Legislative Database (TLDB)

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

Not Available

The Transportation Legislative Database (TLDB) is an on-line information service containing detailed information on legislation and regulations regarding the transportation of radioactive materials in the United States. The system is dedicated to serving the legislative and regulatory information needs of the US Department of Energy and other federal agencies; state, tribal, and local governments; the hazardous materials transportation industry; and interested members of the general public. In addition to the on-line information service, quarterly and annual Legal Developments Reports are produced using information from the TLDB. These reports summarize important changes in federal and state legislation, regulations, administrative agency rulings,more » and judicial decisions over the reporting period. Information on significant legal developments at the tribal and local levels is also included on an as-available basis. Battelle's Office of Transportation Systems and Planning (OTSP) will also perform customized searches of the TLDB and produce formatted printouts in response to specific information requests.« less

Emergency communication and information issues in terrorist events involving radioactive materials.

PubMed

Becker, Steven M

2004-01-01

With the threat posed by terrorism involving radioactive materials now high on the nation's agenda, local, state, and federal agencies are moving to enhance preparedness and response capabilities. Crucial to these efforts is the development of effective risk communication strategies. This article reports findings from an ongoing study of risk communication issues in nuclear/radiological terrorism situations. It is part of a larger CDC-funded effort that aims to better understand communication challenges associated with weapons of mass destruction terrorism incidents. Presented here are formative research findings from 16 focus groups (n = 163) in which a multi-part, hypothetical radioactive materials terrorism situation was discussed. Twelve of the focus groups were carried out with members of the general public (drawn from a variety of ethnic backgrounds and geographic locations), and four groups were composed of first responders, hospital emergency department personnel, and public health professionals. One aim of the focus groups was to elicit detailed information on people's knowledge, views, perceptions, reactions, and concerns related to a nuclear/radiological terrorism event, and to better understand people's specific information needs and preferred information sources. A second aim was to pretest draft informational materials prepared by CDC and NIOSH. Key findings for the public and professional groups are presented, and the implications of the research for developing messages in radiological/nuclear terrorism situations are explored.

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

Revisions to US EPA Superfund Risk and Dose Assessment Models and Guidance - 13403

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

Walker, Stuart A.

2013-07-01

The U.S. Environmental Protection Agency (EPA) Superfund program's six Preliminary Remediation Goal (PRG) and Dose Compliance Concentration (DCC) internet based calculators for risk and dose assessment at Superfund sites are being revised to reflect better science, revisions to existing exposure scenarios and new scenarios, and changes to match up more closely with the EPA chemical regional screening level calculator. A revised version of the 1999 guidance document that provides an overview for the Superfund risk assessment process at radioactively contaminated sites, 'Radiation Risk Assessment At CERCLA Sites: Q and A', is being completed that will reflect Superfund recommended guidance andmore » other technical documents issued over the past 13 years. EPA is also issuing a series of fact sheets in the document 'Superfund Radiation Risk Assessment: A Community Tool-kit'. This presentation would go over those changes that are expected to be finished by this spring. (authors)« less

A Challenge for Radioactive Waste Management: Memory Preservation

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

Charton, P.; Ouzounian, G.

2008-07-01

ANDRA, the French National Radioactive Waste Management Agency, is responsible for managing all radioactive waste in France over the long term. In the case of short-lived waste for which disposal facilities have a life expectancy of a few centuries, the Agency has set up a system for preserving the memory of those sites. Based on the historical analysis on a comparable timescale and on an appraisal of information-conservation means, a series of regulatory as well as technical provisions was made in order to ensure that sound information be transmitted to future generations. Requirements associated to the provisions deal mostly withmore » legibility and a clear understanding of the information that must be decrypted and understood at least during the lifetime of the facilities (i.e., a few centuries). It must therefore be preserved throughout the same period. Responses to the requirements will be presented notably on various information-recording media, together with the information-diffusion strategy to the different authorities and structures within French society. A concrete illustration of the achievements made so far is the Centre de la Manche Disposal Facility, which was closed down in 1994 and is currently in its post-closure monitoring phase since 2003. In the case of deep geological repositories for long-lived radioactive waste, preserving memory takes a different aspect. First of all, timescales are much longer and are counted in hundreds of thousands of years. It is therefore much more difficult to consider how to maintain the richness of the information over such time periods than it is for short-lived waste. Both the nature and the form of the information to be transmitted must be revised. It would be risky indeed to base memory preservation over the long term on similar mechanisms beyond 1,000 years. Based on the heritage of a much more ancient history, we must seek to find appropriate means in order to develop surface markers and even more to ensure their conservation over compatible timescales with those of deep geological repositories. It will also be necessary, in the light of the experiments and efforts made in order to decrypt the messages written on rupestral paintings or in pyramids, find suitable expression means that will help, not the next few generations, but much more future generations, to grasp the meaning of what we aim at transmitting them. This paper presents the state of the French reflection on memory preservation and transmission over the very long term, for timescales consistent with the long-lived radioactive geological waste disposal projects. (author)« less

AED INFORMATION SERVICE. SERIES C: BIBLIOGRAPHIES. SECTION 02: RADIATION EFFECTS ON FOOD (INCL. RADIOACTIVE CONTAMINATION)

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

Lueck, H. comp.

Eleven hundred and fifty-eight references are presented to the world literature on radiation effects on food. References to related biological and chemical studies and studies on radiation dosimetry are included. Emphasis is placed on radiation processing of foods and food products to increase storage life and the effects of fallout fission products on radioactivity in food chains. (C.H.)

Interagency, Intergovernmental Organization, and Nongovernmental Organization Coordination During Joint Operations. Volume 2

DTIC Science & Technology

2006-03-17

energy programs, fossil energy, nuclear energy information, and civilian radioactive waste management; oversight of the power marketing administrations...ADMINISTRATION ALASKA BONNEVILLE SOUTHEASTERN SOUTHWESTERN WESTERN AREA OFFICE OF CIVILIAN RADIOACTIVE WASTE MANAGEMENT ASST SECRETARY ( FOSSIL ENERGY) OFFICE ON...Cutter Service and the Lifesaving Service. The USCG remained in the Department of Treasury until 1967 when it transferred to the Department of

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

V. Finley

This report provides the U.S. Department of Energy (DOE) and the public with information on the level of radioactive and non-radioactive pollutants (if any) that are added to the environment as a result of Princeton Plasma Physics Laboratory's (PPPL) operations. The results of the 2004 environmental surveillance and monitoring program for PPPL's are presented and discussed. The report also summarizes environmental initiatives, assessments, and programs that were undertaken in 2004.

Information system life-cycle and documentation standards, volume 1

NASA Technical Reports Server (NTRS)

Callender, E. David; Steinbacher, Jody

1989-01-01

The Software Management and Assurance Program (SMAP) Information System Life-Cycle and Documentation Standards Document describes the Version 4 standard information system life-cycle in terms of processes, products, and reviews. The description of the products includes detailed documentation standards. The standards in this document set can be applied to the life-cycle, i.e., to each phase in the system's development, and to the documentation of all NASA information systems. This provides consistency across the agency as well as visibility into the completeness of the information recorded. An information system is software-intensive, but consists of any combination of software, hardware, and operational procedures required to process, store, or transmit data. This document defines a standard life-cycle model and content for associated documentation.

Induced radioactivity in LDEF components

NASA Technical Reports Server (NTRS)

Harmon, B. A.; Fishman, G. J.; Parnell, T. A.; Laird, C. E.

1992-01-01

A systematic study of the induced radioactivity of the Long Duration Exposure Facility (LDEF) is being carried out in order to gather information about the low earth orbit radiation environment and its effects on materials. The large mass of the LDEF spacecraft, its stabilized configuration, and long mission duration have presented an opportunity to determine space radiation-induced radioactivities with a precision not possible before. Data presented include preliminary activities for steel and aluminum structural samples, and activation subexperiment foils. Effects seen in the data show a clear indication of the trapped proton anisotropy in the South Atlantic Anomaly and suggest contributions from different sources of external radiation fluxes.

Radioactivity observed in the sodium iodide gamma-ray spectrometer returned on the Apollo 17 mission

NASA Technical Reports Server (NTRS)

Dyer, C. S.; Trombka, J. I.; Schmadebeck, R. L.; Eller, E.; Bielefeld, M. J.; Okelley, G. D.; Eldridge, J. S.; Northcutt, K. J.; Metzger, A. E.; Reedy, R. C.

1975-01-01

In order to obtain information on radioactive background induced in the Apollo 15 and 16 gamma-ray spectrometers (7 cm x 7 cm NaI) by particle irradiation during spaceflight, and identical detector was flown and returned to earth on the Apollo 17 mission. The induced radioactivity was monitored both internally and externally from one and a half hours after splashdown. When used in conjunction with a computation scheme for estimating induced activation from calculated trapped proton and cosmic-ray fluences, these results show an important contribution resulting from both thermal and energetic neutrons produced in the heavy spacecraft by cosmic-ray interactions.

Current Measures on Radioactive Contamination in Japan: A Policy Situation Analysis.

PubMed

Gilmour, Stuart; Miyagawa, Shoji; Kasuga, Fumiko; Shibuya, Kenji

2016-01-01

The Great East Japan Earthquake on 11th March 2011 and the subsequent Fukushima Dai-ichi nuclear power plant disaster caused radioactive contamination in the surrounding environment. In the immediate aftermath of the accident the Government of Japan placed strict measures on radio-contamination of food, and enhanced radio-contamination monitoring activities. Japan is a pilot country in the WHO Foodborne Disease Burden Epidemiology Reference Group (FERG), and through this initiative has an opportunity to report on policy affecting chemicals and toxins in the food distribution network. Nuclear accidents are extremely rare, and a policy situation analysis of the Japanese government's response to the Fukushima Dai-ichi nuclear accident is a responsibility of Japanese scientists. This study aims to assess Japan government policies to reduce radio-contamination risk and to identify strategies to strengthen food policies to ensure the best possible response to possible future radiation accidents. We conducted a hand search of all publicly available policy documents issued by the Cabinet Office, the Food Safety Commission, the Ministry of Health, Labor and Welfare (MHLW), the Ministry of Agriculture, Forestry and Fishery (MAFF) and prefectural governments concerning food safety standards and changes to radiation and contamination standards since March 11th, 2011. We extracted information on food shipment and sales restrictions, allowable radio-contamination limits, monitoring activities and monitoring results. The standard for allowable radioactive cesium (Cs-134 and Cs-137) of 100 Bq/Kg in general food, 50 Bq/Kg in infant formula and all milk products, and 10 Bq/Kg in drinking water was enforced from April 2012 under the Food Sanitation Law, although a provisional standard on radio-contamination had been applied since the nuclear accident. Restrictions on the commercial sale and distribution of specific meat, vegetable and fish products were released for areas at risk of radioactive contamination. Monitoring of radioactive materials in food products in the prefectures has been mainly conducted before shipment to restrict the distribution of radio-contaminated foods. Between March 2011 and March 2012, 133,832 tests of non-commercial and commercial products were conducted, and 1,204 tests (0.9%) were found to violate the provisional standards. Since April 2012, 278,275 tests were conducted, and 2,372 tests (0.9%) were found to violate the revised standards. MHLW assessment of representative market baskets of foodstuffs at 15 locations throughout Japan between February and March 2014 found very low estimated dietary intake of radioactive cesium (0.0007-0.019 mSv/year), as did assessments of the contents of an average day's food. Monitoring of fisheries products in coastal areas affected by the nuclear accident found very limited and declining radio-contamination of live fish outside of Fukushima prefecture. Fisheries monitoring is of limited geographical scope and covers only certain fishes. Area-specific bans on production and distribution have been effective in preventing radioactive contamination in the Japanese food market. Currently there is no major concern about radioactive cesium concentrations in retail foodstuffs in Japan, and very low levels of contamination at the production and wholesale stage. However, because the residue limits and food safety policies were revised on an ad hoc, emergency basis after the nuclear accident, the monitoring procedure needs to be reviewed based on objective and scientifically rational criteria. A transparent and objective scientific framework is needed for prioritizing foodstuffs for inspection and revising Prefecture-specific restrictions. Monitoring of fishes and other seafood products in the wild should be regularized and the information made more publicly accessible, and monitoring activities expanded to identify foodstuffs that are no longer a food safety risk. Consultation with producers and consumers should be more formalized to ensure their concerns are incorporated into regular policy reviews in an appropriate and transparent manner. However, despite the limited available knowledge on best practice in food control and enforcement of provisional radio-contamination limits after the accident, current Japanese policy is sufficient to protect the Japanese public from major risk of radio-contamination from the commercial food market.

Current Measures on Radioactive Contamination in Japan: A Policy Situation Analysis

PubMed Central

Gilmour, Stuart; Miyagawa, Shoji; Kasuga, Fumiko; Shibuya, Kenji

2016-01-01

Background The Great East Japan Earthquake on 11th March 2011 and the subsequent Fukushima Dai-ichi nuclear power plant disaster caused radioactive contamination in the surrounding environment. In the immediate aftermath of the accident the Government of Japan placed strict measures on radio-contamination of food, and enhanced radio-contamination monitoring activities. Japan is a pilot country in the WHO Foodborne Disease Burden Epidemiology Reference Group (FERG), and through this initiative has an opportunity to report on policy affecting chemicals and toxins in the food distribution network. Nuclear accidents are extremely rare, and a policy situation analysis of the Japanese government’s response to the Fukushima Dai-ichi nuclear accident is a responsibility of Japanese scientists. This study aims to assess Japan government policies to reduce radio-contamination risk and to identify strategies to strengthen food policies to ensure the best possible response to possible future radiation accidents. Methods and Findings We conducted a hand search of all publicly available policy documents issued by the Cabinet Office, the Food Safety Commission, the Ministry of Health, Labor and Welfare (MHLW), the Ministry of Agriculture, Forestry and Fishery (MAFF) and prefectural governments concerning food safety standards and changes to radiation and contamination standards since March 11th, 2011. We extracted information on food shipment and sales restrictions, allowable radio-contamination limits, monitoring activities and monitoring results. The standard for allowable radioactive cesium (Cs-134 and Cs-137) of 100 Bq/Kg in general food, 50 Bq/Kg in infant formula and all milk products, and 10 Bq/Kg in drinking water was enforced from April 2012 under the Food Sanitation Law, although a provisional standard on radio-contamination had been applied since the nuclear accident. Restrictions on the commercial sale and distribution of specific meat, vegetable and fish products were released for areas at risk of radioactive contamination. Monitoring of radioactive materials in food products in the prefectures has been mainly conducted before shipment to restrict the distribution of radio-contaminated foods. Between March 2011 and March 2012, 133,832 tests of non-commercial and commercial products were conducted, and 1,204 tests (0.9%) were found to violate the provisional standards. Since April 2012, 278,275 tests were conducted, and 2,372 tests (0.9%) were found to violate the revised standards. MHLW assessment of representative market baskets of foodstuffs at 15 locations throughout Japan between February and March 2014 found very low estimated dietary intake of radioactive cesium (0.0007–0.019 mSv/year), as did assessments of the contents of an average day’s food. Monitoring of fisheries products in coastal areas affected by the nuclear accident found very limited and declining radio-contamination of live fish outside of Fukushima prefecture. Fisheries monitoring is of limited geographical scope and covers only certain fishes. Conclusions Area-specific bans on production and distribution have been effective in preventing radioactive contamination in the Japanese food market. Currently there is no major concern about radioactive cesium concentrations in retail foodstuffs in Japan, and very low levels of contamination at the production and wholesale stage. However, because the residue limits and food safety policies were revised on an ad hoc, emergency basis after the nuclear accident, the monitoring procedure needs to be reviewed based on objective and scientifically rational criteria. A transparent and objective scientific framework is needed for prioritizing foodstuffs for inspection and revising Prefecture-specific restrictions. Monitoring of fishes and other seafood products in the wild should be regularized and the information made more publicly accessible, and monitoring activities expanded to identify foodstuffs that are no longer a food safety risk. Consultation with producers and consumers should be more formalized to ensure their concerns are incorporated into regular policy reviews in an appropriate and transparent manner. However, despite the limited available knowledge on best practice in food control and enforcement of provisional radio-contamination limits after the accident, current Japanese policy is sufficient to protect the Japanese public from major risk of radio-contamination from the commercial food market. PMID:27007509

Land and Water Use Characteristics and Human Health Input Parameters for use in Environmental Dosimetry and Risk Assessments at the Savannah River Site. 2016 Update

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

Jannik, G. Tim; Hartman, Larry; Stagich, Brooke

Operations at the Savannah River Site (SRS) result in releases of small amounts of radioactive materials to the atmosphere and to the Savannah River. For regulatory compliance purposes, potential offsite radiological doses are estimated annually using computer models that follow U.S. Nuclear Regulatory Commission (NRC) regulatory guides. Within the regulatory guides, default values are provided for many of the dose model parameters, but the use of applicant site-specific values is encouraged. Detailed surveys of land-use and water-use parameters were conducted in 1991 and 2010. They are being updated in this report. These parameters include local characteristics of meat, milk andmore » vegetable production; river recreational activities; and meat, milk and vegetable consumption rates, as well as other human usage parameters required in the SRS dosimetry models. In addition, the preferred elemental bioaccumulation factors and transfer factors (to be used in human health exposure calculations at SRS) are documented. The intent of this report is to establish a standardized source for these parameters that is up to date with existing data, and that is maintained via review of future-issued national references (to evaluate the need for changes as new information is released). These reviews will continue to be added to this document by revision.« less

Land and Water Use Characteristics and Human Health Input Parameters for use in Environmental Dosimetry and Risk Assessments at the Savannah River Site 2017 Update

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

Jannik, T.; Stagich, B.

Operations at the Savannah River Site (SRS) result in releases of relatively small amounts of radioactive materials to the atmosphere and to the Savannah River. For regulatory compliance purposes, potential offsite radiological doses are estimated annually using computer models that follow U.S. Nuclear Regulatory Commission (NRC) regulatory guides. Within the regulatory guides, default values are provided for many of the dose model parameters, but the use of site-specific values is encouraged. Detailed surveys of land-use and water-use parameters were conducted in 1991, 2008, 2010, and 2016 and are being concurred with or updated in this report. These parameters include localmore » characteristics of meat, milk, and vegetable production; river recreational activities; and meat, milk, and vegetable consumption rates, as well as other human usage parameters required in the SRS dosimetry models. In addition, the preferred elemental bioaccumulation factors and transfer factors (to be used in human health exposure calculations at SRS) are documented. The intent of this report is to establish a standardized source for these parameters that is up to date with existing data, and that is maintained via review of future-issued national references (to evaluate the need for changes as new information is released). These reviews will continue to be added to this document by revision.« less

10 CFR 60.8 - Information collection requirements: Approval.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Information collection requirements: Approval. 60.8 Section 60.8 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN GEOLOGIC REPOSITORIES General Provisions § 60.8 Information collection requirements: Approval. (a) The...

10 CFR 61.16 - Other information.

Code of Federal Regulations, 2014 CFR

2014-01-01

... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.16 Other information. Depending upon the nature of the wastes to be disposed of, and the design and proposed operation of the land disposal facility, additional information may be requested by the Commission...

10 CFR 61.16 - Other information.

Code of Federal Regulations, 2013 CFR

2013-01-01

... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.16 Other information. Depending upon the nature of the wastes to be disposed of, and the design and proposed operation of the land disposal facility, additional information may be requested by the Commission...

10 CFR 61.16 - Other information.

Code of Federal Regulations, 2012 CFR

2012-01-01

... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.16 Other information. Depending upon the nature of the wastes to be disposed of, and the design and proposed operation of the land disposal facility, additional information may be requested by the Commission...

10 CFR 61.16 - Other information.

Code of Federal Regulations, 2010 CFR

2010-01-01

... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.16 Other information. Depending upon the nature of the wastes to be disposed of, and the design and proposed operation of the land disposal facility, additional information may be requested by the Commission...

10 CFR 61.16 - Other information.

Code of Federal Regulations, 2011 CFR

2011-01-01

... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.16 Other information. Depending upon the nature of the wastes to be disposed of, and the design and proposed operation of the land disposal facility, additional information may be requested by the Commission...

Report of the Peer Review Panel on the early site suitability evaluation of the Potential Repository Site at Yucca Mountain, Nevada; Yucca Mountain Site Characterization Project

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

NONE

1992-01-01

The US Department of Energy (DOE) Yucca mountain Site Characterization Project Office (YMPO) assigned Science Applications International Corporation (SAIC), the Technical and Management Support Services (T&MSS) contractor to the YmPo, the task of conducting an Early Site Suitability Evaluation (ESSE) of the Yucca mountain site as a potential site for a high-level radioactive waste repository. First, the assignment called for the development of a method to evaluate a single site against the DOE General Guidelines for Recommendation of Sites for Nuclear Waste Repositories, 10 CFR Part 960. Then, using this method, an evaluation team, the ESSE Core Team, of seniormore » YMP scientists, engineers, and technical experts, evaluated new information obtained about the site since publication of the final Environmental Assessment (DOE, 1986) to determine if new suitability/unsuitability findings could be recommended. Finally, the Core Team identified further information and analyses needed to make final determinations for each of the guidelines. As part of the task, an independent peer review of the ESSE report has been conducted. Expertise was solicited that covered the entire spectrum of siting guidelines in 10 CFR Part 960 in order to provide a complete, in-depth critical review of the data evaluated and cited in the ESSE report, the methods used to evaluate the data, and the conclusions and recommendations offered by the report. Fourteen nationally recognized technical experts (Table 2) served on the Peer Review Panel. The comments from the Panel and the responses prepared by the ESSE Core Team, documented on formal Comment Response Forms, constitute the body of this document.« less

Energy Materials Coordinating Committee (EMaCC), Fiscal year 1992. Annual technical report

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

Not Available

The DOE EMaCC serves to coordinate the department`s materials programs and to further effective use of materials expertise within the department. This document presents summaries of budgets and of research projects, arranged according to the offices of energy efficiency and renewable energy, energy research, environmental restoration and waste management, nuclear energy, civilian radioactive waste management, defense, and fossil energy. A directory and a keyword index are included.

Information Scanning and Processing at the Nuclear Safety Information Center.

ERIC Educational Resources Information Center

Parks, Celia; Julian, Carol

This report is a detailed manual of the information specialist's duties at the Nuclear Safety Information Center. Information specialists scan the literature for documents to be reviewed, procure the documents (books, journal articles, reports, etc.), keep the document location records, and return the documents to the plant library or other…

Thallium-201 for cardiac stress tests: residual radioactivity worries patients and security.

PubMed

Geraci, Matthew J; Brown, Norman; Murray, David

2012-12-01

A 47-year-old man presented to the Emergency Department (ED) in duress and stated he was "highly radioactive." There were no reports of nuclear disasters, spills, or mishaps in the local area. This report discusses the potential for thallium-201 (Tl-201) patients to activate passive radiation alarms days to weeks after nuclear stress tests, even while shielded inside industrial vehicles away from sensors. Characteristics of Tl-201, as used for medical imaging, are described. This patient was twice detained by Homeland Security Agents and searched after he activated radiation detectors at a seaport security checkpoint. Security agents deemed him not to be a threat, but they expressed concern regarding his health and level of personal radioactivity. The patient was subsequently barred from his job and sent to the hospital. Tl-201 is a widely used radioisotope for medical imaging. The radioactive half-life of Tl-201 is 73.1h, however, reported periods of extended personal radiation have been seen as far out as 61 days post-administration. This case describes an anxious, but otherwise asymptomatic patient presenting to the ED with detection of low-level personal radiation. Documentation should be provided to and carried by individuals receiving radionuclides for a minimum of five to six half-lives of the longest-lasting isotope provided. Patients receiving Tl-201 should understand the potential for security issues; reducing probable tense moments, confusion, and anxiety to themselves, their employers, security officials, and ED staff. Copyright © 2012 Elsevier Inc. All rights reserved.

EPRI guide to managing nuclear utility protective clothing programs

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

Kelly, J.J.

1991-05-01

The Electric Power Research Institute (EPRI) commissioned a radioactive waste related project (RP2414-34) during the last quarter of 1989 to produce a guide for developing and managing nuclear protective clothing programs. Every nuclear facility must coordinate some type of protective clothing program for its radiation workers to insure proper and safe protection for the wearer and to maintain control over the spread of contamination. Yet, every nuclear facility has developed its own unique program for managing such clothing. Accordingly, a need existed for a reference guide to assist with the standardization of protective clothing programs and to assist in controllingmore » the potentially runaway economics of such programs. This document is the first known effort to formalize the planning and economic factors surrounding a nuclear utility protective clothing program. It is intended to be informative by addressing the various pieces of information necessary to establish and maintain an effective, professionally managed protective clothing program. It also attempts to provide guidance toward tailoring the information and providing examples within the report to fit each utility's specific needs. This report is further intended to address new issues and trends occurring throughout the nuclear industry in late 1989 which can have either a significant positive or negative impact on the operations or economics of nuclear protective clothing programs. 1 ref., 11 tabs.« less

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

Finley, V.L.; Wiezcorek, M.A.

This report gives the results of the environmental activities and monitoring programs at the Princeton Plasma Physics Laboratory (PPPL) for CY93. The report is prepared to provide the U.S. Department of Energy (DOE) and the public with information on the level of radioactive and non-radioactive pollutants, if any, added to the environment as a result of PPPL operations, as well as environmental initiatives, assessments, and programs that were undertaken in 1993. The objective of the Annual Site Environmental Report is to document evidence that DOE facility environmental protection programs adequately protect the environment and the public health. The Princeton Plasmamore » Physics Laboratory has engaged in fusion energy research since 1951. The long-range goal of the U.S. Magnetic Fusion Energy Research Program is to develop and demonstrate the practical application of fusion power as an alternate energy source. In 1993, PPPL had both of its two large tokamak devices in operation; the Tokamak Fusion Test Reactor (TFTR) and the Princeton Beta Experiment-Modification (PBX-M). PBX-M completed its modifications and upgrades and resumed operation in November 1991. TFTR began the deuterium-tritium (D-T) experiments in December 1993 and set new records by producing over six million watts of energy. The engineering design phase of the Tokamak Physics Experiment (TPX), which replaced the cancelled Burning Plasma Experiment in 1992 as PPPL`s next machine, began in 1993 with the planned start up set for the year 2001. In 1993, the Environmental Assessment (EA) for the TFRR Shutdown and Removal (S&R) and TPX was prepared for submittal to the regulatory agencies.« less

Radioactive materials released from nuclear power plants. Annual report, 1980

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

Tichler, J.; Benkovitz, C.

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1980 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1980 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

Radioactive materials released from nuclear power plants

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

Tichler, J.; Norden, K.; Congemi, J.

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1987 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1987 release data are summarized in tabular form. Data covering specific radionuclides are summarized. 16 tabs.

Radioactive materials released from nuclear power plants

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

Tichler, J.; Benkovitz, C.

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1979 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1979 release data are compared with previous year's releases in tabular form. Data covering specific radionuclides are summarized.

Radioactive materials released from nuclear power plants: Annual report, 1984

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

Tichler, J.; Norden, K.; Congemi, J.

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1984 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1984 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

Radioactive materials released from nuclear power plants: Annual report, 1985

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

Tichler, J.; Norden, K.; Congemi, J.

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1985 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1985 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

Radioactive materials released from nuclear power plants

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

Tichler, J.; Norden, K.; Congemi, J.

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1988 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1988 release data are summarized in tabular form. Data covering specific radionuclides are summarized. 16 tabs.

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

Finley, Virginia

This report provides the U.S. Department of Energy (DOE) and the public with information on the level of radioactive and non-radioactive pollutants (if any) that are added to the environment as a result of Princeton Plasma Physics Laboratory’s (PPPL) operations. The results of the 2013 environmental surveillance and monitoring program for PPPL’s are presented and discussed. The report also summarizes environmental initiatives, assessments, and community involvement programs that were undertaken in 2013.

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

Virginia L. Finley, Editor

This report provides the U.S. Department of Energy (DOE) and the public with information on the level of radioactive and non-radioactive pollutants (if any) that are added to the environment as a result of Princeton Plasma Physics Laboratory's (PPPL) operations. The results of the 2002 and 2003 environmental surveillance and monitoring program for PPPL are presented and discussed. The report also summarizes environmental initiatives, assessments, and programs that were undertaken in 2002 and 2003.

1st Quarter Transportation Report FY 2015: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

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

Gregory, Louis

2015-02-20

This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to and from the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the 1st quarter of Fiscal Year (FY) 2015 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. Tabular summaries are provided which include the following: Sources of and carriers for LLW and MLLW shipments tomore » and from the NNSS; Number and external volume of LLW and MLLW shipments; Highway routes used by carriers; and Incident/accident data applicable to LLW and MLLW shipments. In this report shipments are accounted for upon arrival at the NNSS, while disposal volumes are accounted for upon waste burial. The disposal volumes presented in this report include minor volumes of non-radioactive classified waste/material that were approved for disposal (non-radioactive classified or nonradioactive classified hazardous). Volume reports showing cubic feet generated using the Low-Level Waste Information System may vary slightly due to rounding conventions for volumetric conversions from cubic meters to cubic feet.« less

Atmospheric Dispersal and Dispostion of Tephra From a Potential Volcanic Eruption at Yucca Mountain, Nevada

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

G. Keating; W.Statham

2004-02-12

The purpose of this model report is to provide documentation of the conceptual and mathematical model (ASHPLUME) for atmospheric dispersal and subsequent deposition of ash on the land surface from a potential volcanic eruption at Yucca Mountain, Nevada. This report also documents the ash (tephra) redistribution conceptual model. The ASHPLUME conceptual model accounts for incorporation and entrainment of waste fuel particles associated with a hypothetical volcanic eruption through the Yucca Mountain repository and downwind transport of contaminated tephra. The ASHPLUME mathematical model describes the conceptual model in mathematical terms to allow for prediction of radioactive waste/ash deposition on the groundmore » surface given that the hypothetical eruptive event occurs. This model report also describes the conceptual model for tephra redistribution from a basaltic cinder cone. Sensitivity analyses and model validation activities for the ash dispersal and redistribution models are also presented. Analyses documented in this model report will improve and clarify the previous documentation of the ASHPLUME mathematical model and its application to the Total System Performance Assessment (TSPA) for the License Application (TSPA-LA) igneous scenarios. This model report also documents the redistribution model product outputs based on analyses to support the conceptual model.« less

Method for gathering and summarizing internet information

DOEpatents

Potok, Thomas E.; Elmore, Mark Thomas; Reed, Joel Wesley; Treadwell, Jim N.; Samatova, Nagiza Faridovna

2010-04-06

A computer method of gathering and summarizing large amounts of information comprises collecting information from a plurality of information sources (14, 51) according to respective maps (52) of the information sources (14), converting the collected information from a storage format to XML-language documents (26, 53) and storing the XML-language documents in a storage medium, searching for documents (55) according to a search query (13) having at least one term and identifying the documents (26) found in the search, and displaying the documents as nodes (33) of a tree structure (32) having links (34) and nodes (33) so as to indicate similarity of the documents to each other.

System for gathering and summarizing internet information

DOEpatents

Potok, Thomas E.; Elmore, Mark Thomas; Reed, Joel Wesley; Treadwell, Jim N.; Samatova, Nagiza Faridovna

2006-07-04

A computer method of gathering and summarizing large amounts of information comprises collecting information from a plurality of information sources (14, 51) according to respective maps (52) of the information sources (14), converting the collected information from a storage format to XML-language documents (26, 53) and storing the XML-language documents in a storage medium, searching for documents (55) according to a search query (13) having at least one term and identifying the documents (26) found in the search, and displaying the documents as nodes (33) of a tree structure (32) having links (34) and nodes (33) so as to indicate similarity of the documents to each other.

Method for gathering and summarizing internet information

DOEpatents

Potok, Thomas E [Oak Ridge, TN; Elmore, Mark Thomas [Oak Ridge, TN; Reed, Joel Wesley [Knoxville, TN; Treadwell, Jim N [Louisville, TN; Samatova, Nagiza Faridovna [Oak Ridge, TN

2008-01-01

A computer method of gathering and summarizing large amounts of information comprises collecting information from a plurality of information sources (14, 51) according to respective maps (52) of the information sources (14), converting the collected information from a storage format to XML-language documents (26, 53) and storing the XML-language documents in a storage medium, searching for documents (55) according to a search query (13) having at least one term and identifying the documents (26) found in the search, and displaying the documents as nodes (33) of a tree structure (32) having links (34) and nodes (33) so as to indicate similarity of the documents to each other.

10 CFR 60.47 - Facility information and verification.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Facility information and verification. 60.47 Section 60.47 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN GEOLOGIC REPOSITORIES Licenses Us/iaea Safeguards Agreement § 60.47 Facility information and verification. (a) In...

10 CFR 37.31 - Protection of information.

Code of Federal Regulations, 2014 CFR

2014-01-01

... verifies information such as name, date of birth, social security number, gender, and other applicable... 10 Energy 1 2014-01-01 2014-01-01 false Protection of information. 37.31 Section 37.31 Energy NUCLEAR REGULATORY COMMISSION PHYSICAL PROTECTION OF CATEGORY 1 AND CATEGORY 2 QUANTITIES OF RADIOACTIVE...

10 CFR 61.8 - Information collection requirements: OMB approval.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Information collection requirements: OMB approval. 61.8 Section 61.8 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.8 Information collection requirements: OMB approval. (a) The Nuclear...

10 CFR 61.32 - Facility information and verification.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Facility information and verification. 61.32 Section 61.32 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses Us/iaea Safeguards Agreement § 61.32 Facility information and verification. (a) In...

10 CFR 61.8 - Information collection requirements: OMB approval.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Information collection requirements: OMB approval. 61.8 Section 61.8 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.8 Information collection requirements: OMB approval. (a) The Nuclear...

10 CFR 61.8 - Information collection requirements: OMB approval.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Information collection requirements: OMB approval. 61.8 Section 61.8 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.8 Information collection requirements: OMB approval. (a) The Nuclear...

10 CFR 61.8 - Information collection requirements: OMB approval.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Information collection requirements: OMB approval. 61.8 Section 61.8 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.8 Information collection requirements: OMB approval. (a) The Nuclear...

10 CFR 61.32 - Facility information and verification.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Facility information and verification. 61.32 Section 61.32 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses Us/iaea Safeguards Agreement § 61.32 Facility information and verification. (a) In...

10 CFR 61.8 - Information collection requirements: OMB approval.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Information collection requirements: OMB approval. 61.8 Section 61.8 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.8 Information collection requirements: OMB approval. (a) The Nuclear...

10 CFR 61.32 - Facility information and verification.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Facility information and verification. 61.32 Section 61.32 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses Us/iaea Safeguards Agreement § 61.32 Facility information and verification. (a) In...

Novel methods for estimating 3D distributions of radioactive isotopes in materials

NASA Astrophysics Data System (ADS)

Iwamoto, Y.; Kataoka, J.; Kishimoto, A.; Nishiyama, T.; Taya, T.; Okochi, H.; Ogata, H.; Yamamoto, S.

2016-09-01

In recent years, various gamma-ray visualization techniques, or gamma cameras, have been proposed. These techniques are extremely effective for identifying "hot spots" or regions where radioactive isotopes are accumulated. Examples of such would be nuclear-disaster-affected areas such as Fukushima or the vicinity of nuclear reactors. However, the images acquired with a gamma camera do not include distance information between radioactive isotopes and the camera, and hence are "degenerated" in the direction of the isotopes. Moreover, depth information in the images is lost when the isotopes are embedded in materials, such as water, sand, and concrete. Here, we propose two methods of obtaining depth information of radioactive isotopes embedded in materials by comparing (1) their spectra and (2) images of incident gamma rays scattered by the materials and direct gamma rays. In the first method, the spectra of radioactive isotopes and the ratios of scattered to direct gamma rays are obtained. We verify experimentally that the ratio increases with increasing depth, as predicted by simulations. Although the method using energy spectra has been studied for a long time, an advantage of our method is the use of low-energy (50-150 keV) photons as scattered gamma rays. In the second method, the spatial extent of images obtained for direct and scattered gamma rays is compared. By performing detailed Monte Carlo simulations using Geant4, we verify that the spatial extent of the position where gamma rays are scattered increases with increasing depth. To demonstrate this, we are developing various gamma cameras to compare low-energy (scattered) gamma-ray images with fully photo-absorbed gamma-ray images. We also demonstrate that the 3D reconstruction of isotopes/hotspots is possible with our proposed methods. These methods have potential applications in the medical fields, and in severe environments such as the nuclear-disaster-affected areas in Fukushima.

Factors associated with the risk perception and purchase decisions of Fukushima-related food in South Korea

PubMed Central

Song, Min Kyoung; Lee, Hyang Ki; Park, Sunhoo; Jin, Young Woo

2017-01-01

Following the Fukushima nuclear power plant accident, the risk level perceived by Koreans on the radioactive contamination of Japanese food that is being distributed in Korea remains high. Many of these perceptions are based on subjective risk perception rather than an objective measure with scientific evidence, which makes communicating risks more difficult; therefore, it is critical to understand factors associated with risk perception for effective risk communication. In this study, we identified variables that are associated with buying tendencies and opinions about the regulatory policy of Japanese seafood after the accident. A survey was conducted with 1045 adults aged over 20 years in Korea. The majority (68.8%) responded that they would not purchase Japanese seafood when radioactivity levels in the food were non-detectable. Moreover, 82.2% responded that the current levels of import restrictions on Japanese seafood must be maintained. Despite many concerns regarding the exposure to radiation and the effects from food products following the Fukushima accident, the opportunities to encounter and to collect correct information remain limited and average radioactive knowledge scores were low (3.63 out of 9). Of the various characteristics associated with purchase decisions and agreement on the current import restraints of Japanese seafood, trust levels in the government and the mass media for providing information on radioactivity were major factors that influenced risk perception. While the scope of this study was limited to seafood, it is very closely tied to daily lives, where we revealed differences about risk perceptions and agreement on import restraints of Japanese seafood per a complex mixture of individual characteristics and the surrounding environment. These results provide useful information to understand the risk perception of the potential radioactive contamination of food and to predict the public’s responses to food consumption and import restraint policies due to nuclear accidents in neighboring countries. PMID:29117237

Factors associated with the risk perception and purchase decisions of Fukushima-related food in South Korea.

PubMed

Lee, Dalnim; Seo, Songwon; Song, Min Kyoung; Lee, Hyang Ki; Park, Sunhoo; Jin, Young Woo

2017-01-01

Following the Fukushima nuclear power plant accident, the risk level perceived by Koreans on the radioactive contamination of Japanese food that is being distributed in Korea remains high. Many of these perceptions are based on subjective risk perception rather than an objective measure with scientific evidence, which makes communicating risks more difficult; therefore, it is critical to understand factors associated with risk perception for effective risk communication. In this study, we identified variables that are associated with buying tendencies and opinions about the regulatory policy of Japanese seafood after the accident. A survey was conducted with 1045 adults aged over 20 years in Korea. The majority (68.8%) responded that they would not purchase Japanese seafood when radioactivity levels in the food were non-detectable. Moreover, 82.2% responded that the current levels of import restrictions on Japanese seafood must be maintained. Despite many concerns regarding the exposure to radiation and the effects from food products following the Fukushima accident, the opportunities to encounter and to collect correct information remain limited and average radioactive knowledge scores were low (3.63 out of 9). Of the various characteristics associated with purchase decisions and agreement on the current import restraints of Japanese seafood, trust levels in the government and the mass media for providing information on radioactivity were major factors that influenced risk perception. While the scope of this study was limited to seafood, it is very closely tied to daily lives, where we revealed differences about risk perceptions and agreement on import restraints of Japanese seafood per a complex mixture of individual characteristics and the surrounding environment. These results provide useful information to understand the risk perception of the potential radioactive contamination of food and to predict the public's responses to food consumption and import restraint policies due to nuclear accidents in neighboring countries.

Closure of hazardous and mixed radioactive waste management units at DOE facilities. [Contains glossary

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

Not Available

This is document addresses the Federal regulations governing the closure of hazardous and mixed waste units subject to Resource Conservation and Recovery Act (RCRA) requirements. It provides a brief overview of the RCRA permitting program and the extensive RCRA facility design and operating standards. It provides detailed guidance on the procedural requirements for closure and post-closure care of hazardous and mixed waste management units, including guidance on the preparation of closure and post-closure plans that must be submitted with facility permit applications. This document also provides guidance on technical activities that must be conducted both during and after closure ofmore » each of the following hazardous waste management units regulated under RCRA.« less

Personal information documents for people with dementia: Healthcare staff 's perceptions and experiences.

PubMed

Baillie, Lesley; Thomas, Nicola

2018-01-01

Person-centred care is internationally recognised as best practice for the care of people with dementia. Personal information documents for people with dementia are proposed as a way to support person-centred care in healthcare settings. However, there is little research about how they are used in practice. The aim of this study was to analyse healthcare staff 's perceptions and experiences of using personal information documents, mainly Alzheimer's Society's 'This is me', for people with dementia in healthcare settings. The method comprised a secondary thematic analysis of data from a qualitative study, of how a dementia awareness initiative affected care for people with dementia in one healthcare organisation. The data were collected through 12 focus groups (n = 58 participants) and 1 individual interview, conducted with a range of healthcare staff, both clinical and non-clinical. There are four themes presented: understanding the rationale for personal information documents; completing personal information documents; location for personal information documents and transfer between settings; impact of personal information documents in practice. The findings illuminated how healthcare staff use personal information documents in practice in ways that support person-centred care. Practical issues about the use of personal information documents were revealed and these may affect the optimal use of the documents in practice. The study indicated the need to complete personal information documents at an early stage following diagnosis of dementia, and the importance of embedding their use across care settings, to support communication and integrated care.

An overview of EPA regulation of the safe disposal of transuranic waste at the Waste Isolation Pilot Plant.

PubMed

Wolbarst, A B; Forinash, E K; Byrum, C O; Peake, R T; Marcinowski, F; Kruger, M U

2001-02-01

In March of 1999, the Waste Isolation Pilot Plant (WIPP) in southeast New Mexico, the world's first deep geological repository for radioactive materials, began receiving defense-related transuranic waste. The WIPP was designed and constructed by the U.S. Department of Energy, but critical to its opening was certification by the U.S. Environmental Protection Agency that the repository complies with the radioactive waste disposal regulations set forth as environmental radiation protection standards (40 CFR Part 191) and compliance criteria (40 CFR Part 194). This paper provides a summary of the regulatory process, including the Environmental Protection Agency's waste containment, groundwater protection, and individual dose regulations for the WIPP; the Department of Energy's performance assessment and the other parts of its compliance certification application; and the Environmental Protection Agency's review and analysis of the compliance certification application and related documentation.

Environmental Remediation Activities in Japan Following the Fukushima Dai-ichi Reactor Incident - 12603

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

Lively, J.W.; Kelley, J.L.; Marcial, M.R.

2012-07-01

In March 2011, the Fukushima Dai-ichi reactor power plant was crippled by the Great Pacific earthquake and subsequent tsunami. Much of the focus in the news was on the reactor site itself as the utility company (TEPCO), the Japanese government, and experts from around the world worked to bring the damaged plants into a safe shutdown condition and stem the release of radioactivity to the environment. Most of the radioactivity released was carried out to sea with the prevailing winds. Still, as weather patterns changed and winds shifted, a significant plume of radioactive materials released from the plant deposited inmore » the environment surrounding the plant, contaminating large land areas of the Fukushima Prefecture. The magnitude of the radiological impact to the surrounding environmental is so large that the Japanese government has had to reevaluate the meaning of 'acceptably clean'. In many respects, 'acceptably clean' cannot be a one-size-fits-all standard. The economics costs of such an approach would make impossible what is already an enormous and costly environmental response and remediation task. Thus, the Japanese government has embarked upon an approach that is both situation-specific and reasonably achievable. For example, the determination of acceptably clean for a nursery school or kindergarten play yard may be different from that for a parking lot. The acceptably clean level of residual radioactivity in the surface soil of a rice paddy is different from that in a forested area. The recognized exposure situation (scenario) thus plays a large role in the decision process. While sometimes complicated to grasp or implement, such an approach does prioritize national resources to address environment remediation based upon immediate and significant risks. In addition, the Japanese government is testing means and methods, including advanced or promising technologies, that could be proven to be effective in reducing the amount of radioactivity in the environment beyond a fixed, concentration based limit. Essentially, the definition of acceptably clean includes the concept of reasonably achievable, given the available technology, means and methods, and the cost to implement such. The Japanese government recently issued three technology demonstration contracts expressly designed to test and evaluate the available technologies, means, and methods, which, if implemented, might produce the greatest risk reduction from environmental contamination for the best value. One of the Japanese contract holders, Obayashi JV, has teamed with AMEC to demonstrate the applicability and capabilities of the Orion ScanPlot{sup SM} and ScanSort{sup SM} technologies in radiologically impacted towns both inside and immediately outside the 20 km restricted zone. This presentation provides some unique images and informative insight into the environmental radioactive impacts in and around the exclusion zone. It will provide a look at one element of the Japanese government?s efforts to achieve the greatest risk reduction that is reasonably achievable. The Orion ScanPlot{sup SM} and ScanSort{sup SM} are being used with success on the Japan Town Demonstration Project to assess pre-remedial action contamination levels, document the post-remedial action contamination levels and to precisely measure and segregate excavated soils based on their radioactive content and the prescribed segregation limits (DCS). Initial results suggest that these technologies could provide capabilities to the remedial action efforts that would result in considerable improvements in field data certainty and compliance with remedial objectives while reducing overall costs. (authors)« less

Principles of Product Quality Control of German Radioactive Waste Forms from the Reprocessing of Spent Fuel: Vitrification, Compaction and Numerical Simulation - 12529

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

Tietze-Jaensch, Holger; Schneider, Stephan; Aksyutina, Yuliya

2012-07-01

The German product quality control is inter alia responsible for control of two radioactive waste forms of heat generating waste: a) homogeneous vitrified HLW and b) heterogeneous compacted hulls, end-pieces and technological metallic waste. In either case, significantly different metrology is employed at the site of the conditioning plant for the obligatory nuclide inventory declaration. To facilitate an independent evaluation and checking of the accompanying documentation numerical simulations are carried out. The physical and chemical properties of radioactive waste residues are used to assess the data consistency and uncertainty margins, as well as to predict the long-term behavior of themore » radioactive waste. This is relevant for repository acceptance and safety considerations. Our new numerical approach follows a bottom-up simulation starting from the burn-up behavior of the fuel elements in the reactor core. The output of these burn-up calculations is then coupled with a program that simulates the material separation in the subsequent dissolution and extraction processes normalized to the mass balance. Follow-up simulations of the separated reprocessing lines of a) the vitrification of highly-active liquid and b) the compaction of residual intermediate-active metallic hulls remaining after fuel pellets dissolution, end-pieces and technological waste, allows calculating expectation values for the various repository relevant properties of either waste stream. The principles of the German product quality control of radioactive waste residues from the spent fuel reprocessing have been introduced and explained. Namely, heat generating homogeneous vitrified HLW and heterogeneous compacted metallic MLW have been discussed. The advantages of a complementary numerical property simulation have been made clear and examples of benefits are presented. We have compiled a new program suite to calculate the physical and radio-chemical properties of common nuclear waste residues. The immediate benefit is the independent assessment of radio-active inventory declarations and much facilitated product quality control of waste residues that need to be returned to Germany and submitted to a German HLW-repository requirements. Wherever possible, internationally accepted standard programs are used and embedded. The innovative coupling of burn-up calculations (SCALE) with neutron and gamma transport codes (MCPN-X) allows an application in the world of virtual waste properties. If-then-else scenarios of hypothetical waste material compositions and distributions provide valuable information of long term nuclide property propagation under repository conditions over a very long time span. Benchmarking the program with real residue data demonstrates the power and remarkable accuracy of this numerical approach, boosting the reliability of the confidence aforementioned numerous applications, namely the proof tool set for on-the-spot production quality checking and data evaluation and independent verification. Moreover, using the numerical bottom-up approach helps to avoid the accumulation of fake activities that may gradually build up in a repository from the so-called conservative or penalizing nuclide inventory declarations. The radioactive waste properties and the hydrolytic and chemical stability can be predicted. The interaction with invasive chemicals can be assessed and propagation scenarios can be developed from reliable and sound data and HLW properties. Hence, the appropriate design of a future HLW repository can be based upon predictable and quality assured waste characteristics. (authors)« less

10 CFR 2.1011 - Management of electronic information.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Management of electronic information. 2.1011 Section 2... High-Level Radioactive Waste at a Geologic Repository § 2.1011 Management of electronic information. (a... Language)-compliant (ANSI IX3.135-1992/ISO 9075-1992) database management system (DBMS). Alternatively, the...

Uses of Radioactive Isotopes in Industry; APLICACIONES DE LOS ISOTOPOS RADIACTIVOS EN LA INDUSTRIA

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

Plata, A.; del Val Cob, M.; Gamboya, J.M.

1962-01-01

A list of some of the most important problems in industry that were approached by the use of radioactive isotopes is presented. The list was compiled through the experience galned in revising for several years important scientific journals and other sources of information on this subject. The classification of industries was done in an arbitrary way, choosing those isotope uses that have reached a higher degree of development. (auth)

Radioactive materials released from nuclear power plants. Annual report 1991, Volume 12

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

Tichler, J.; Doty, K.; Congemi, J.

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1991 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1991 release data are summarized in tabular form. Data Covering specific radionuclides are summarized.

Radioactive materials released from nuclear power plants. Annual report, 1982. Volume 3

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

Tichler, J.; Norden, K.

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1982 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1982 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

Radioactive materials released from nuclear power plants. Volume 11: Annual report, 1990

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

Tichler, J.; Doty, K.; Congemi, J.

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1990 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1990 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

Radioactive materials released from nuclear power plants. Annual report 1978

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

Tichler, J.; Benkovitz, C.

Releases of radioactive materials in airborne and liquid effluents from commerical light water reactors during 1978 have been compiled and reported. Data on soild waste shipments as well as selected operating information have been included. This report supplements earlier annual reports by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1978 release data are compared with previous years releases in tabular form. Data covering specific radionuclides are summarized.

Radioactive materials released from nuclear power plants. Annual report 1981. Vol. 2

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

Tichler, J.; Benkovitz, C.

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1981 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1981 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

Radioactive materials released from nuclear power plants. Annual report, 1983. Volume 4

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

Tichler, J.; Norden, K.

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1983 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1983 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

Lease Operations Environmental Guidance Document

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

Bureau of Land Management

This report contains discussions in nine different areas as follows: (1) Good Lease Operating Practices; (2) Site Assessment and Sampling; (3) Spills/Accidents; (4) Containment and Disposal of Produced Waters; (5) Restoration of Hydrocarbon Impacted Soils; (6) Restoration of Salt Impacted Soils; (7) Pit Closures; (8) Identification, Removal and Disposal of Naturally Occurring Radioactive Materials (NORM); and (9) Site Closure and Construction Methods for Abandonment Wells/Locations. This report is primary directed towards the operation of oil and gas producing wells.

Experiences in the field of radioactive materials seizures in the Czech Republic

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

Svoboda, Karel; Podlaha, Josef; Sir, David

2007-07-01

In recent years, the amount of radioactive materials seizures (captured radioactive materials) has been rising. It was above all due to newly installed detection facilities that were able to check metallic scrap during its collection in scrap yards or on the entrance to iron-mills, checking municipal waste upon entrance to municipal disposal sites, even incineration plants, or through checking vehicles going through the borders of the Czech Republic. Most cases bore a relationship to secondary raw materials or they were connected to the application of machines and installations made from contaminated metallic materials. However, in accordance to our experience, themore » number of cases of seizures of materials and devices containing radioactive sources used in the public domain was lower, but not negligible, in the municipal storage yards or incineration plants. Atomic Act No. 18/1997 Coll. will apply to everybody who provides activities leading to exposure, mandatory assurance as high radiation safety as risk of the endangering of life, personal health and environment is as low as reasonably achievable in according to social and economic aspects. Hence, attention on the examination of all cases of the radioactive material seizure based on detection facilities alarm or reasonably grounds suspicion arising from the other information is important. Therefore, a service carried out by group of workers who ensure assessment of captured radioactive materials and eventual retrieval of radioactive sources from the municipal waste has come into existence in the Nuclear Research Institute Rez plc. This service has covered also transport, storage, processing and disposal of found radioactive sources. This service has arisen especially for municipal disposal sites, but later on even other companies took advantage of this service like incineration plants, the State Office for Nuclear Safety, etc. Our experience in the field of ensuring assessment of captured radioactive materials and eventual retrieval of radioactive sources will be presented in the paper. (authors)« less

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

Paragenesis and Geochronology of the Nopal I Uranium Deposit, Mexico

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

M. Fayek; M. Ren

2007-02-14

Uranium deposits can, by analogy, provide important information on the long-term performance of radioactive waste forms and radioactive waste repositories. Their complex mineralogy and variable elemental and isotopic compositions can provide important information, provided that analyses are obtained on the scale of several micrometers. Here, we present a structural model of the Nopal I deposit as well as petrography at the nanoscale coupled with preliminary U-Th-Pb ages and O isotopic compositions of uranium-rich minerals obtained by Secondary Ion Mass Spectrometry (SIMS). This multi-technique approach promises to provide ''natural system'' data on the corrosion rate of uraninite, the natural analogue ofmore » spent nuclear fuel.« less

Modeling species richness and abundance of phytoplankton and zooplankton in radioactively contaminated water bodies.

PubMed

Shuryak, Igor

2018-06-05

Water bodies polluted by the Mayak nuclear plant in Russia provide valuable information on multi-generation effects of radioactive contamination on freshwater organisms. For example, lake Karachay was probably the most radioactive lake in the world: its water contained ∼2 × 10 7 Bq/L of radionuclides and estimated dose rates to plankton exceeded 5 Gy/h. We performed quantitative modeling of radiation effects on phytoplankton and zooplankton species richness and abundance in Mayak-contaminated water bodies. Due to collinearity between radioactive contamination, water body size and salinity, we combined these variables into one (called HabitatFactors). We employed a customized machine learning approach, where synthetic noise variables acted as benchmarks of predictor performance. HabitatFactors was the only predictor that outperformed noise variables and, therefore, we used it for parametric modeling of plankton responses. Best-fit model predictions suggested 50% species richness reduction at HabitatFactors values corresponding to dose rates of 10 4 -10 5  μGy/h for phytoplankton, and 10 3 -10 4  μGy/h for zooplankton. Under conditions similar to those in lake Karachay, best-fit models predicted 81-98% species richness reductions for various taxa (Cyanobacteria, Bacillariophyta, Chlorophyta, Rotifera, Cladocera and Copepoda), ∼20-300-fold abundance reduction for total zooplankton, but no abundance reduction for phytoplankton. Rotifera was the only taxon whose fractional abundance increased with contamination level, reaching 100% in lake Karachay, but Rotifera species richness declined with contamination level, as in other taxa. Under severe radioactive and chemical contamination, one species of Cyanobacteria (Geitlerinema amphibium) dominated phytoplankton, and rotifers from the genus Brachionus dominated zooplankton. The modeling approaches proposed here are applicable to other radioecological data sets. The results provide quantitative information and easily interpretable model parameter estimates for the shapes and magnitudes of freshwater plankton responses to a wide range of radioactive contamination levels. Copyright © 2018 Elsevier Ltd. All rights reserved.

32 CFR 813.1 - Purpose of the visual information documentation (VIDOC) program.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 32 National Defense 6 2010-07-01 2010-07-01 false Purpose of the visual information documentation (VIDOC) program. 813.1 Section 813.1 National Defense Department of Defense (Continued) DEPARTMENT OF THE AIR FORCE SALES AND SERVICES VISUAL INFORMATION DOCUMENTATION PROGRAM § 813.1 Purpose of the visual information documentation (VIDOC) program....

Product specification documentation standard and Data Item Descriptions (DID). Volume of the information system life-cycle and documentation standards, volume 3

NASA Technical Reports Server (NTRS)

Callender, E. David; Steinbacher, Jody

1989-01-01

This is the third of five volumes on Information System Life-Cycle and Documentation Standards which present a well organized, easily used standard for providing technical information needed for developing information systems, components, and related processes. This volume states the Software Management and Assurance Program documentation standard for a product specification document and for data item descriptions. The framework can be applied to any NASA information system, software, hardware, operational procedures components, and related processes.

Evaluation of Terrorist Interest in Radioactive Wastes

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

McFee, J.N.; Langsted, J.M.; Young, M.E.

2006-07-01

Since September 11, 2001, intelligence gathered from Al Qaeda training camps in Afghanistan, and the ensuing terrorist activities, indicates nuclear material security concerns are valid. This paper reviews available information on sealed radioactive sources thought to be of interest to terrorists, and then examines typical wastes generated during environmental management activities to compare their comparative 'attractiveness' for terrorist diversion. Sealed radioactive sources have been evaluated in numerous studies to assess their security and attractiveness for use as a terrorist weapon. The studies conclude that tens of thousands of curies in sealed radioactive sources are available for potential use in amore » terrorist attack. This risk is mitigated by international efforts to find lost and abandoned sources and bring them under adequate security. However, radioactive waste has not received the same level of scrutiny to ensure security. This paper summarizes the activity and nature of radioactive sources potentially available to international terrorists. The paper then estimates radiation doses from use of radioactive sources as well as typical environmental restoration or decontamination and decommissioning wastes in a radioactive dispersal device (RDD) attack. These calculated doses indicate that radioactive wastes are, as expected, much less of a health risk than radioactive sources. The difference in radiation doses from wastes used in an RDD are four to nine orders of magnitude less than from sealed sources. We then review the International Atomic Energy Agency (IAEA) definition of 'dangerous source' in an adjusted comparison to common radioactive waste shipments generated in environmental management activities. The highest waste dispersion was found to meet only category 1-3.2 of the five step IAEA scale. A category '3' source by the IAEA standard 'is extremely unlikely, to cause injury to a person in the immediate vicinity'. The obvious conclusion of the analysis is that environmental management generated radioactive wastes have substantially less impact than radioactive sources if dispersed by terrorist-induced explosion or fire. From a health standpoint, the impact is very small. However, there is no basis to conclude that wastes are totally unattractive for use in a disruptive or economic damage event. Waste managers should be cognizant of this potential and take measures to ensure security of stored waste and waste shipments. (authors)« less

Microgravity Experiments Safety and Integration Requirements Document Tree

NASA Technical Reports Server (NTRS)

Hogan, Jean M.

1995-01-01

This report is a document tree of the safety and integration documents required to develop a space experiment. Pertinent document information for each of the top level (tier one) safety and integration documents, and their applicable and reference (tier two) documents has been identified. This information includes: document title, revision level, configuration management, electronic availability, listed applicable and reference documents, source for obtaining the document, and document owner. One of the main conclusions of this report is that no single document tree exists for all safety and integration documents, regardless of the Shuttle carrier. This document also identifies the need for a single point of contact for customers wishing to access documents. The data in this report serves as a valuable information source for the NASA Lewis Research Center Project Documentation Center, as well as for all developers of space experiments.

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

Abercrombie, Robert K; Buckner Jr, Dooley; Newton, David D

The Oak Ridge National Laboratory (ORNL) Weigh-In-Motion (WIM) system provides a portable and/or semi-portable means of accurately weighing vehicles and its cargo as each vehicle crosses the scales (while in motion), and determining (1) axle weights and (2) axle spacing for vehicles (for determination of Bridge Formula compliance), (3) total vehicle/cargo weight and (4) longitudinal center of gravity (for safety considerations). The WIM system can also weigh the above statically. Because of the automated nature of the WIM system, it eliminates the introduction of human errors caused by manual computations and data entry, adverse weather conditions, and stress. Individual vehiclesmore » can be weighed continuously at low speeds (approximately 3-10 mph) and at intervals of less than one minute. The ORNL WIM system operates and is integrated into the Bethel Jacobs Company Transportation Management and Information System (TMIS, a Radio-Frequency Identification [RFID] enabled information system). The integrated process is as follows: Truck Identification Number and Tare Weight are programmed into a RFID Tag. Handheld RFID devices interact with the RFID Tag, and Electronic Shipping Document is written to the RFID Tag. The RFID tag read by an RFID tower identifies the vehicle and its associated cargo, the specific manifest of radioactive debris for the uniquely identified vehicle. The weight of the cargo (in this case waste debris) is calculated from total vehicle weight information supplied from WIM to TMIS and is further processed into the Information System and kept for historical and archival purposes. The assembled data is the further process in downstream information systems where waste coordination activities at the Y-12 Environmental Management Waste Management Facility (EMWMF) are written to RFID Tag. All cycle time information is monitored by Transportation Operations and Security personnel.« less

Invisibly Sanitizable Digital Signature Scheme

NASA Astrophysics Data System (ADS)

Miyazaki, Kunihiko; Hanaoka, Goichiro; Imai, Hideki

A digital signature does not allow any alteration of the document to which it is attached. Appropriate alteration of some signed documents, however, should be allowed because there are security requirements other than the integrity of the document. In the disclosure of official information, for example, sensitive information such as personal information or national secrets is masked when an official document is sanitized so that its nonsensitive information can be disclosed when it is requested by a citizen. If this disclosure is done digitally by using the current digital signature schemes, the citizen cannot verify the disclosed information because it has been altered to prevent the leakage of sensitive information. The confidentiality of official information is thus incompatible with the integrity of that information, and this is called the digital document sanitizing problem. Conventional solutions such as content extraction signatures and digitally signed document sanitizing schemes with disclosure condition control can either let the sanitizer assign disclosure conditions or hide the number of sanitized portions. The digitally signed document sanitizing scheme we propose here is based on the aggregate signature derived from bilinear maps and can do both. Moreover, the proposed scheme can sanitize a signed document invisibly, that is, no one can distinguish whether the signed document has been sanitized or not.

Sandia National Laboratories support of the Iraq Nuclear Facility Dismantlement and Disposal Program.

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

Cochran, John Russell; Danneels, Jeffrey John

2009-03-01

Because of past military operations, lack of upkeep and looting there are now enormous radioactive waste problems in Iraq. These waste problems include destroyed nuclear facilities, uncharacterized radioactive wastes, liquid radioactive waste in underground tanks, wastes related to the production of yellow cake, sealed radioactive sources, activated metals and contaminated metals that must be constantly guarded. Iraq currently lacks the trained personnel, regulatory and physical infrastructure to safely and securely manage these facilities and wastes. In 2005 the International Atomic Energy Agency (IAEA) agreed to organize an international cooperative program to assist Iraq with these issues. Soon after, the Iraqmore » Nuclear Facility Dismantlement and Disposal Program (the NDs Program) was initiated by the U.S. Department of State (DOS) to support the IAEA and assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials. The Iraq NDs Program is providing support for the IAEA plus training, consultation and limited equipment to the GOI. The GOI owns the problems and will be responsible for implementation of the Iraq NDs Program. Sandia National Laboratories (Sandia) is a part of the DOS's team implementing the Iraq NDs Program. This report documents Sandia's support of the Iraq NDs Program, which has developed into three principal work streams: (1) training and technical consultation; (2) introducing Iraqis to modern decommissioning and waste management practices; and (3) supporting the IAEA, as they assist the GOI. Examples of each of these work streams include: (1) presentation of a three-day training workshop on 'Practical Concepts for Safe Disposal of Low-Level Radioactive Waste in Arid Settings;' (2) leading GOI representatives on a tour of two operating low level radioactive waste disposal facilities in the U.S.; and (3) supporting the IAEA's Technical Meeting with the GOI from April 21-25, 2008. As noted in the report, there was significant teaming between the various participants to best help the GOI. On-the-ground progress is the focus of the Iraq NDs Program and much of the work is a transfer of technical and practical skills and knowledge that Sandia uses day-to-day. On-the-ground progress was achieved in July of 2008 when the GOI began the physical cleanup and dismantlement of the Active Metallurgical Testing Laboratory (LAMA) facility at Al Tuwaitha, near Baghdad.« less

Waste Information Record Keeping System (WIRKS) in Romania

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

Dogaru, D.M.; Raducea, D.; Dogaru, G.

2006-07-01

In Romania there is no common national WIRKS used by all waste management organizations. Each waste management organization uses an own WIRKS. The regulatory authority approves the WIRKS of each radioactive waste facility and checks the recordings during the process of authorization. This paper summarizes the regulatory requirements regarding to WIRKS, the types of the waste generators, facilities and their waste classification of radioactive waste. Also the paper summarizes the WIRKS applied to the most important waste generators. (authors)

Gamma-emitting radionuclides in the shallow marine sediments off the Sindh coast, Arabian Sea.

PubMed

Akram, M; Qureshi, Riffat M; Ahmad, Nasir; Solaija, Tariq Jamal

2006-01-01

Determination of gamma emitting radionuclides in shallow marine sediments off the Sindh coast has been carried out using a gamma spectrometry technique. The activity concentration measured in various sediment samples off the Sindh coast has been found to vary from 15.93 +/- 5.22 to 30.53 +/- 4.70 Bq kg(-1) for 226Ra, from 11.72 +/- 1.22 to 33.94 +/- 1.86 Bq kg(-1) for 228Ra and from 295.22 +/- 32.83 to 748.47 +/- 28.75 Bq kg(-1) for 40K. The calculated mean values of radium equivalent activity, absorbed dose rate and effective dose are 98 Bq kg(-1), 49 nGy h(-1) and 0.06 mSv y(-1), respectively. No artificial radionuclide was detected in the samples measured from the study area. As no data on radioactivity of the coastal environment of Pakistan are available, the data presented here will serve as baseline information on radionuclide concentration in shallow sea sediments off the Sindh coast. The data will also be useful for tracking pollution inventories from unusual radiological events (if any) in the territorial waters of the study area. Further, the information presented will contribute to modelling of a regional radioactivity database from the perspectives of the International Atomic Energy Agency's Asia-Pacific Marine Radioactivity Database and Global Marine Radioactivity Database.

Renewed soil erosion and remobilisation of radioactive sediment in Fukushima coastal rivers after the 2013 typhoons.

PubMed

Evrard, Olivier; Chartin, Caroline; Onda, Yuichi; Lepage, Hugo; Cerdan, Olivier; Lefèvre, Irène; Ayrault, Sophie

2014-04-03

Summer typhoons and spring snowmelt led to the riverine spread of continental Fukushima fallout to the coastal plains of Northeastern Japan and the Pacific Ocean. Four fieldwork campaigns based on measurement of radioactive dose rates in fine riverine sediment that has recently deposited on channel bed-sand were conducted between November 2011 and May 2013 to document the spread of fallout by rivers. After a progressive decrease in the fresh riverine sediment doses rates between 2011 and early spring in 2013, a fifth campaign conducted in November 2013 showed that they started to increase again after the occurrence of violent typhoons. We show that this increase in dose rates was mostly due to remobilization of contaminated material that was temporarily stored in river channels or, more importantly, in dam reservoirs of the region during the typhoons. In addition, supply of particles from freshly eroded soils in autumn 2013 was the most important in areas where decontamination works are under progress. Our results underline the need to monitor the impact of decontamination works and dam releases in the region, as they may provide a continuous source of radioactive contamination to the coastal plains and the Pacific Ocean during the coming years.

Fukushima Daiichi Nuclear Plant accident: Atmospheric and oceanic impacts over the five years.

PubMed

Hirose, Katsumi

2016-06-01

The Fukushima Daiichi Nuclear Plant (FDNPP) accident resulted in huge environmental and socioeconomic impacts to Japan. To document the actual environmental and socioeconomic effects of the FDNPP accident, we describe here atmospheric and marine contamination due to radionuclides released from the FDNPP accident using papers published during past five years, in which temporal and spatial variations of FDNPP-derived radionuclides in air, deposition and seawater and their mapping are recorded by local, regional and global monitoring activities. High radioactivity-contaminated area in land were formed by the dispersion of the radioactive cloud and precipitation, depending on land topography and local meteorological conditions, whereas extremely high concentrations of (131)I and radiocesium in seawater occurred due to direct release of radioactivity-contaminated stagnant water in addition to atmospheric deposition. For both of atmosphere and ocean, numerical model simulations, including local, regional and global-scale modeling, were extensively employed to evaluate source terms of the FDNPP-derived radionuclides from the monitoring data. These models also provided predictions of the dispersion and high deposition areas of the FDNPP-derived radionuclides. However, there are significant differences between the observed and simulated values. Then, the monitoring data would give a good opportunity to improve numerical modeling. Copyright © 2016 Elsevier Ltd. All rights reserved.

Iodine-131 Releases from Radioactive Lanthanum Processing at the X-10 Site in Oak Ridge, Tennessee (1944-1956)- An Assessment of Quantities released, Off-Site Radiation Doses, and Potential Excess Risks of Thyroid Cancer, Volume 1

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

Apostoaei, A.I.; Burns, R.E.; Hoffman, F.O.

1999-07-01

In the early 1990s, concern about the Oak Ridge Reservation's past releases of contaminants to the environment prompted Tennessee's public health officials to pursue an in-depth study of potential off-site health effects at Oak Ridge. This study, the Oak Ridge dose reconstruction, was supported by an agreement between the U.S. Department of Energy (DOE) and the State of Tennessee, and was overseen by a 12-member panel appointed by Tennessee's Commissioner of Health. One of the major contaminants studied in the dose reconstruction was radioactive iodine, which was released to the air by X-10 (now called Oak Ridge National Laboratory) asmore » it processed spent nuclear reactor fuel from 1944 through 1956. The process recovered radioactive lanthanum for use in weapons development. Iodine concentrates in the thyroid gland so health concerns include various diseases of the thyroid, such as thyroid cancer. The large report, ''Iodine-131 Releases from Radioactive Lanthanum Processing at the X-10 Site in Oak Ridge, Tennessee (1944-1956) - An Assessment of Quantities Released, Off-site Radiation Doses, and Potential Excess Risks of Thyroid Cancer,'' is in two volumes. Volume 1 is the main body of the report, and Volume 1A, which has the same title, consists of 22 supporting appendices. Together, these reports serve the following purposes: (1) describe the methodologies used to estimate the amount of iodine-131 (I-131) released; (2) evaluate I-131's pathway from air to vegetation to food to humans; (3) estimate doses received by human thyroids; (4) estimate excess risk of acquiring a thyroid cancer during ones lifetime; and (5) provide equations, examples of historical documents used, and tables of calculated values. Results indicate that females born in 1952 who consumed milk from a goat pastured a few miles east of X-10 received the highest doses from I-131 and would have had the highest risks of contracting thyroid cancer. Doses from cow's milk are considerably less . Detailed dose and risk estimates, and associated uncertainties, for other contaminants studied for the Oak Ridge dose reconstruction are presented in several other technical reports. One way to easily locate them in OSTI's Information Bridge is by searching the ''report number field'' for the number DOE/OR/21981*. Be sure to place the asterisk after the base number so your search can list the complete series of reports related to Oak Ridge Dose Reconstruction.« less

Report of ICRP Task Group 80: 'radiological protection in geological disposal of long-lived solid radioactive waste'.

PubMed

Weiss, W

2012-01-01

The report of International Commission on Radiological Protection (ICRP) Task Group 80 entitled 'Radiological protection in geological disposal of long-lived solid radioactive waste' updates and consolidates previous ICRP recommendations related to solid waste disposal (ICRP Publications 46, 77, and 81). The recommendations given in this report apply specifically to geological disposal of long-lived solid radioactive waste. The report explains how the 2007 system of radiological protection, described in ICRP Publication 103, can be applied in the context of the geological disposal of long-lived solid radioactive waste. The report is written as a self-standing document. It describes the different stages in the lifetime of a geological disposal facility, and addresses the application of relevant radiological protection principles for each stage depending on the various exposure situations that can be encountered. In particular, the crucial factor that influences application of the protection system over the different phases in the lifetime of a disposal facility is the level of oversight that is present. The level of oversight affects the capability to reduce or avoid exposures. Three main time frames have to be considered for the purpose of radiological protection: time of direct oversight when the disposal facility is being implemented and active oversight is taking place; time of indirect oversight when the disposal facility is sealed and indirect oversight is being exercised to provide additional assurance on behalf of the population; and time of no oversight when oversight is no longer exercised because memory is lost. Copyright © 2012. Published by Elsevier Ltd.

Deep Borehole Disposal Concept: Development of Universal Canister Concept of Operations

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

Rigali, Mark J.; Price, Laura L.

This report documents key elements of the conceptual design for deep borehole disposal of radioactive waste to support the development of a universal canister concept of operations. A universal canister is a canister that is designed to be able to store, transport, and dispose of radioactive waste without the canister having to be reopened to treat or repackage the waste. This report focuses on the conceptual design for disposal of radioactive waste contained in a universal canister in a deep borehole. The general deep borehole disposal concept consists of drilling a borehole into crystalline basement rock to a depth ofmore » about 5 km, emplacing WPs in the lower 2 km of the borehole, and sealing and plugging the upper 3 km. Research and development programs for deep borehole disposal have been ongoing for several years in the United States and the United Kingdom; these studies have shown that deep borehole disposal of radioactive waste could be safe, cost effective, and technically feasible. The design concepts described in this report are workable solutions based on expert judgment, and are intended to guide follow-on design activities. Both preclosure and postclosure safety were considered in the development of the reference design concept. The requirements and assumptions that form the basis for the deep borehole disposal concept include WP performance requirements, radiological protection requirements, surface handling and transport requirements, and emplacement requirements. The key features of the reference disposal concept include borehole drilling and construction concepts, WP designs, and waste handling and emplacement concepts. These features are supported by engineering analyses.« less

Assessment of Quality Assurance Measures for Radioactive Material Transport Packages not Requiring Competent Authority Design Approval - 13282

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

Komann, Steffen; Groeke, Carsten; Droste, Bernhard

The majority of transports of radioactive materials are carried out in packages which don't need a package design approval by a competent authority. Low-active radioactive materials are transported in such packages e.g. in the medical and pharmaceutical industry and in the nuclear industry as well. Decommissioning of NPP's leads to a strong demand for packages to transport low and middle active radioactive waste. According to IAEA regulations the 'non-competent authority approved package types' are the Excepted Packages and the Industrial Packages of Type IP-1, IP-2 and IP-3 and packages of Type A. For these types of packages an assessment bymore » the competent authority is required for the quality assurance measures for the design, manufacture, testing, documentation, use, maintenance and inspection (IAEA SSR 6, Chap. 306). In general a compliance audit of the manufacturer of the packaging is required during this assessment procedure. Their regulatory level in the IAEA regulations is not comparable with the 'regulatory density' for packages requiring competent authority package design approval. Practices in different countries lead to different approaches within the assessment of the quality assurance measures in the management system as well as in the quality assurance program of a special package design. To use the package or packaging in a safe manner and in compliance with the regulations a management system for each phase of the life of the package or packaging is necessary. The relevant IAEA-SSR6 chap. 801 requires documentary verification by the consignor concerning package compliance with the requirements. (authors)« less

The Multimedia Environmental Pollutant Assessment System (MEPAS){reg_sign}: Atmospheric pathway formulations. Revision

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

Droppo, J.G.; Buck, J.W.

1996-03-01

The Multimedia Environmental Pollutant Assessment System (MEPAS) is an integrated software implementation of physics-based fate and transport models for health and environmental risk assessments of both radioactive and hazardous pollutants. This atmospheric component report is one of a series of formulation reports that document the MEPAS mathematical models. MEPAS is a multimedia model; pollutant transport is modeled within, through, and between multiple media (air, soil, groundwater, and surface water). The estimated concentrations in the various media are used to compute exposures and impacts to the environment, to maximum individuals, and to populations. The MEPAS atmospheric component for the air mediamore » documented in this report includes models for emission from a source to the air, initial plume rise and dispersion, airborne pollutant transport and dispersion, and deposition to soils and crops. The material in this report is documentation for MEPAS Versions 3.0 and 3.1 and the MEPAS version used in the Remedial Action Assessment System (RAAS) Version 1.0.« less

Radioactivity of the moon, planets, and meteorites

NASA Technical Reports Server (NTRS)

Surkou, Y. A.; Fedoseyev, G. A.

1977-01-01

Analytical data is summarized for the content of natural radioactive elements in meteorites, eruptive terrestrial rocks, and also in lunar samples returned by Apollo missions and the Luna series of automatic stations. The K-U systematics of samples analyzed in the laboratory are combined with data for orbital gamma-ray measurements for Mars (Mars 5) and with the results of direct gamma-ray measurements of the surface of Venus by the Venera 8 lander. Using information about the radioactivity of solar system bodies and evaluations of the content of K, U, and Th in the terrestrial planets, we examine certain aspects of the evolution of material in the protoplanetary gas-dust cloud and then in the planets of the solar system.

Variation in adverse drug reactions listed in product information for antidepressants and anticonvulsants, between the USA and Europe: a comparison review of paired regulatory documents

PubMed Central

Cornelius, Victoria R; Liu, Kun; Peacock, Janet; Sauzet, Odile

2016-01-01

Objective To compare consistency of adverse drug reaction (ADR) data in publicly available product information documents for brand drugs, between the USA and Europe. To assess the usefulness of information for prescribers and patients. Design A comparison review of product information documents for antidepressants and anticonvulsants concurrently marketed by the same pharmaceutical company in the USA and Europe. Setting For each drug, data were extracted from the US Product Inserts and the European Summary of Product Characteristics documents between 09/2013 and 01/2015. Participants Individuals contributing ADR information to product information documents. Main outcomes measures All ADRs reported in product information sections 5 and 6 (USA), and 4·4 and 4·8 (Europe). Results Twelve brand drugs—24 paired documents—were included. On average, there were 77 more ADRs reported in the USA compared with in the European product information document, with a median number of 201 ADRs (range: 65–425) and 114 (range: 56–265), respectively. More product information documents in the USA reported information on the source of evidence (10 vs 5) and risk (9 vs 5) for greater than 80% of ADRs included in the document. There was negligible information included regarding duration, severity, reversibility or recurrence of ADRs. On average, only 29% of ADR terms were reported in both paired documents. Conclusions Product information documents contained a large number of ADRs, but lacked contextual data and information important to patients and prescribers, such as duration, severity and reversibility. The ADR profile was found to be inconsistently reported between the USA and Europe, for the same drug. Identifying, selecting, summarising and presenting multidimensional harm data should be underpinned by practical evidence-based guidelines. In order for prescribers to provide considered risk-benefit advice across competing drug therapies to patients, they need access to comprehensible and reliable ADR information. PMID:26996819

Detection with Enhanced Energy Windowing Phase I Report

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

Bass, David A.; Enders, Alexander L.

2016-12-01

This document reviews the progress of Phase I of the Detection with Enhanced Energy Windowing (DEEW) project. The DEEW project is the implementation of software incorporating an algorithm which reviews data generated by radiation portal monitors and utilizes advanced and novel techniques for detecting radiological and fissile material while not alarming on Naturally Occurring Radioactive Material. Independent testing indicated that the Enhanced Energy Windowing algorithm showed promise at reducing the probability of alarm in the stream of commerce compared to existing algorithms and other developmental algorithms, while still maintaining adequate sensitivity to threats. This document contains a brief description ofmore » the project, instructions for setting up and running the applications, and guidance to help make reviewing the output files and source code easier.« less

Recommended Parameter Values for GENII Modeling of Radionuclides in Routine Air and Water Releases

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

Snyder, Sandra F.; Arimescu, Carmen; Napier, Bruce A.

The GENII v2 code is used to estimate dose to individuals or populations from the release of radioactive materials into air or water. Numerous parameter values are required for input into this code. User-defined parameters cover the spectrum from chemical data, meteorological data, agricultural data, and behavioral data. This document is a summary of parameter values that reflect conditions in the United States. Reasonable regional and age-dependent data is summarized. Data availability and quality varies. The set of parameters described address scenarios for chronic air emissions or chronic releases to public waterways. Considerations for the special tritium and carbon-14 modelsmore » are briefly addressed. GENIIv2.10.0 is the current software version that this document supports.« less

Radiation Detection at Borders for Homeland Security

NASA Astrophysics Data System (ADS)

Kouzes, Richard

2004-05-01

Countries around the world are deploying radiation detection instrumentation to interdict the illegal shipment of radioactive material crossing international borders at land, rail, air, and sea ports of entry. These efforts include deployments in the US and a number of European and Asian countries by governments and international agencies. Items of concern include radiation dispersal devices (RDD), nuclear warheads, and special nuclear material (SNM). Radiation portal monitors (RPMs) are used as the main screening tool for vehicles and cargo at borders, supplemented by handheld detectors, personal radiation detectors, and x-ray imaging systems. Some cargo contains naturally occurring radioactive material (NORM) that triggers "nuisance" alarms in RPMs at these border crossings. Individuals treated with medical radiopharmaceuticals also produce nuisance alarms and can produce cross-talk between adjacent lanes of a multi-lane deployment. The operational impact of nuisance alarms can be significant at border crossings. Methods have been developed for reducing this impact without negatively affecting the requirements for interdiction of radioactive materials of interest. Plastic scintillator material is commonly used in RPMs for the detection of gamma rays from radioactive material, primarily due to the efficiency per unit cost compared to other detection materials. The resolution and lack of full-energy peaks in the plastic scintillator material prohibits detailed spectroscopy. However, the limited spectroscopic information from plastic scintillator can be exploited to provide some discrimination. Energy-based algorithms used in RPMs can effectively exploit the crude energy information available from a plastic scintillator to distinguish some NORM. Whenever NORM cargo limits the level of the alarm threshold, energy-based algorithms produce significantly better detection probabilities for small SNM sources than gross-count algorithms. This presentation discusses experience with RPMs for interdiction of radioactive materials at borders.

Radiation detection and situation management by distributed sensor networks

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

Jan, Frigo; Mielke, Angela; Cai, D Michael

Detection of radioactive materials in an urban environment usually requires large, portal-monitor-style radiation detectors. However, this may not be a practical solution in many transport scenarios. Alternatively, a distributed sensor network (DSN) could complement portal-style detection of radiological materials through the implementation of arrays of low cost, small heterogeneous sensors with the ability to detect the presence of radioactive materials in a moving vehicle over a specific region. In this paper, we report on the use of a heterogeneous, wireless, distributed sensor network for traffic monitoring in a field demonstration. Through wireless communications, the energy spectra from different radiation detectorsmore » are combined to improve the detection confidence. In addition, the DSN exploits other sensor technologies and algorithms to provide additional information about the vehicle, such as its speed, location, class (e.g. car, truck), and license plate number. The sensors are in-situ and data is processed in real-time at each node. Relevant information from each node is sent to a base station computer which is used to assess the movement of radioactive materials.« less

The changes in caregivers' perceptions about the quality of information and benefits of nursing documentation associated with the introduction of an electronic documentation system in a nursing home.

PubMed

Munyisia, Esther N; Yu, Ping; Hailey, David

2011-02-01

To date few studies have compared nursing home caregivers' perceptions about the quality of information and benefits of nursing documentation in paper and electronic formats. With the increased interest in the use of information technology in nursing homes, it is important to obtain information on the benefits of newer approaches to nursing documentation so as to inform investment, organisational and care service decisions in the aged care sector. This study aims to investigate caregivers' perceptions about the quality of information and benefits of nursing documentation before and after the introduction of an electronic documentation system in a nursing home. A self-administered questionnaire survey was conducted three months before, and then six, 18 and 31 months after the introduction of an electronic documentation system. Further evidence was obtained through informal discussions with caregivers. Scores for questionnaire responses showed that the benefits of the electronic documentation system were perceived by the caregivers as provision of more accurate, legible and complete information, and reduction of repetition in data entry, with consequential managerial benefits. However, caregivers' perceptions of relevance and reliability of information, and of their communication and decision-making abilities were perceived to be similar either using an electronic or a paper-based documentation system. Improvement in some perceptions about the quality of information and benefits of nursing documentation was evident in the measurement conducted six months after the introduction of the electronic system, but were not maintained 18 or 31 months later. The electronic documentation system was perceived to perform better than the paper-based system in some aspects, with subsequent benefits to management of aged care services. In other areas, perceptions of additional benefits from the electronic documentation system were not maintained. In a number of attributes, there were similar perceptions on the two types of systems. Copyright © 2010 Elsevier Ireland Ltd. All rights reserved.

Informacion Bibliografica Educativa, N. 1 (Educational Bibliographic Information, N. 1).

ERIC Educational Resources Information Center

Ministerio de Educacion Nacional, Bogota (Colombia). Instituto Colombiano de Pedagogia.

This document discusses some considerations in the development of a system for educational documentation and information in Colombia. There is a need for a national policy of educational documentation to insure cooperation among various institutions involved in the task. The three main objectives are documentation and information for teacher…

Safety analysis report for the Waste Storage Facility. Revision 2

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

Bengston, S.J.

1994-05-01

This safety analysis report outlines the safety concerns associated with the Waste Storage Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are: define and document a safety basis for the Waste Storage Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume.

Epidermal Growth Factor Receptor Overexpression as a Target for Auger Electron Radiotherapy of Breast Cancer

DTIC Science & Technology

2002-08-01

treatment of mice with 92.5 MBq (2.5 mCi) of ..In-DTPA-hEGF in five divided weekly doses. * Cumulative Radioactivity in Source Compartment (,s, Bq x...equiv- nalization of the radiopharmaceutical resulted in selective alent to a human dose of 14,208 MBq /m 2) can be safely and enhanced cytotoxicity in... be construed as an official Department of the Army position, policy or decision unless so designated by other documentation. " ROIForm Approved

Information Types in Nonmimetic Documents: A Review of Biddle's Wipe-Clean Slate (Understanding Documents).

ERIC Educational Resources Information Center

Mosenthal, Peter B.; Kirsch, Irwin S.

1991-01-01

Describes how the 16 permanent lists used by a first grade reading teacher (and mother of 6) to manage the household represents the whole range of documents covered in the 3 major types of documents: matrix documents, graphic documents, and locative documents. Suggests class activities to clarify students' understanding of the information in…

Joint Assessment of Renewable Energy and Water Desalination Research Center (REWDC) Program Capabilities and Facilities In Radioactive Waste Management

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

Bissani, M; Fischer, R; Kidd, S

2006-04-03

The primary goal of this visit was to perform a joint assessment of the Renewable Energy and Water Desalination Center's (REWDC) program in radioactive waste management. The visit represented the fourth technical and scientific interaction with Libya under the DOE/NNSA Sister Laboratory Arrangement. Specific topics addressed during the visit focused on Action Sheet P-05-5, ''Radioactive Waste Management''. The Team, comprised of Mo Bissani (Team Lead), Robert Fischer, Scott Kidd, and Jim Merrigan, consulted with REWDC management and staff. The team collected information, discussed particulars of the technical collaboration and toured the Tajura facility. The tour included the waste treatment facility,more » waste storage/disposal facility, research reactor facility, hot cells and analytical labs. The assessment team conducted the first phase of Task A for Action Sheet 5, which involved a joint assessment of the Radioactive Waste Management Program. The assessment included review of the facilities dedicated to the management of radioactive waste at the Tourja site, the waste management practices, proposed projects for the facility and potential impacts on waste generation and management.« less

A review and overview of nuclear waste management

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

Murray, R.L.

1984-12-31

An understanding of the status and issues in the management of radioactive wastes is based on technical information on radioactivity, radiation, biological hazard of radiation exposure, radiation standards, and methods of protection. The fission process gives rise to radioactive fission products and neutron bombardment gives activation products. Radioactive wastes are classified according to source: defense, commercial, industrial, and institutional; and according to physical features: uranium mill tailings, high-level, transuranic, and low-level. The nuclear fuel cycle, which contributes a large fraction of annual radioactive waste, starts with uranium ore, includes nuclear reactor use for electrical power generation, and ends with ultimatemore » disposal of residues. The relation of spent fuel storage and reprocessing is governed by technical, economic, and political considerations. Waste has been successfully solidified in glass and other forms and choices of the containers for the waste form are available. Methods of disposal of high-level waste that have been investigated are transmutation by neutron bombardment, shipment to Antartica, deep-hole insertion, subseabed placement, transfer by rocket to an orbit in space, and disposal in a mined cavity. The latter is the favored method. The choices of host geological media are salt, basalt, tuff, and granite.« less

Variation in adverse drug reactions listed in product information for antidepressants and anticonvulsants, between the USA and Europe: a comparison review of paired regulatory documents.

PubMed

Cornelius, Victoria R; Liu, Kun; Peacock, Janet; Sauzet, Odile

2016-03-20

To compare consistency of adverse drug reaction (ADR) data in publicly available product information documents for brand drugs, between the USA and Europe. To assess the usefulness of information for prescribers and patients. A comparison review of product information documents for antidepressants and anticonvulsants concurrently marketed by the same pharmaceutical company in the USA and Europe. For each drug, data were extracted from the US Product Inserts and the European Summary of Product Characteristics documents between 09/2013 and 01/2015. Individuals contributing ADR information to product information documents. All ADRs reported in product information sections 5 and 6 (USA), and 4·4 and 4·8 (Europe). Twelve brand drugs--24 paired documents--were included. On average, there were 77 more ADRs reported in the USA compared with in the European product information document, with a median number of 201 ADRs (range: 65-425) and 114 (range: 56-265), respectively. More product information documents in the USA reported information on the source of evidence (10 vs 5) and risk (9 vs 5) for greater than 80% of ADRs included in the document. There was negligible information included regarding duration, severity, reversibility or recurrence of ADRs. On average, only 29% of ADR terms were reported in both paired documents. Product information documents contained a large number of ADRs, but lacked contextual data and information important to patients and prescribers, such as duration, severity and reversibility. The ADR profile was found to be inconsistently reported between the USA and Europe, for the same drug. Identifying, selecting, summarising and presenting multidimensional harm data should be underpinned by practical evidence-based guidelines. In order for prescribers to provide considered risk-benefit advice across competing drug therapies to patients, they need access to comprehensible and reliable ADR information. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/

Implementing the EuroFIR Document and Data Repositories as accessible resources of food composition information.

PubMed

Unwin, Ian; Jansen-van der Vliet, Martine; Westenbrink, Susanne; Presser, Karl; Infanger, Esther; Porubska, Janka; Roe, Mark; Finglas, Paul

2016-02-15

The EuroFIR Document and Data Repositories are being developed as accessible collections of source documents, including grey literature, and the food composition data reported in them. These Repositories will contain source information available to food composition database compilers when selecting their nutritional data. The Document Repository was implemented as searchable bibliographic records in the Europe PubMed Central database, which links to the documents online. The Data Repository will contain original data from source documents in the Document Repository. Testing confirmed the FoodCASE food database management system as a suitable tool for the input, documentation and quality assessment of Data Repository information. Data management requirements for the input and documentation of reported analytical results were established, including record identification and method documentation specifications. Document access and data preparation using the Repositories will provide information resources for compilers, eliminating duplicated work and supporting unambiguous referencing of data contributing to their compiled data. Copyright © 2014 Elsevier Ltd. All rights reserved.

Infrastructure development for radioactive materials at the NSLS-II

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

Sprouster, D. J.; Weidner, R.; Ghose, S. K.

2018-02-01

The X-ray Powder Diffraction (XPD) Beamline at the National Synchrotron Light Source-II is a multipurpose instrument designed for high-resolution, high-energy X-ray scattering techniques. In this article, the capabilities, opportunities and recent developments in the characterization of radioactive materials at XPD are described. The overarching goal of this work is to provide researchers access to advanced synchrotron techniques suited to the structural characterization of materials for advanced nuclear energy systems. XPD is a new beamline providing high photon flux for X-ray Diffraction, Pair Distribution Function analysis and Small Angle X-ray Scattering. The infrastructure and software described here extend the existing capabilitiesmore » at XPD to accommodate radioactive materials. Such techniques will contribute crucial information to the characterization and quantification of advanced materials for nuclear energy applications. We describe the automated radioactive sample collection capabilities and recent X-ray Diffraction and Small Angle X-ray Scattering results from neutron irradiated reactor pressure vessel steels and oxide dispersion strengthened steels.« less

Radioactive source security: the cultural challenges.

PubMed

Englefield, Chris

2015-04-01

Radioactive source security is an essential part of radiation protection. Sources can be abandoned, lost or stolen. If they are stolen, they could be used to cause deliberate harm and the risks are varied and significant. There is a need for a global security protection system and enhanced capability to achieve this. The establishment of radioactive source security requires 'cultural exchanges'. These exchanges include collaboration between: radiation protection specialists and security specialists; the nuclear industry and users of radioactive sources; training providers and regulators/users. This collaboration will facilitate knowledge and experience exchange for the various stakeholder groups, beyond those already provided. This will promote best practice in both physical and information security and heighten security awareness generally. Only if all groups involved are prepared to open their minds to listen to and learn from, each other will a suitable global level of control be achieved. © The Author 2014. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Infrastructure development for radioactive materials at the NSLS-II

DOE PAGES

Sprouster, David J.; Weidner, R.; Ghose, S. K.; ...

2017-11-04

The X-ray Powder Diffraction (XPD) Beamline at the National Synchrotron Light Source-II is a multipurpose instrument designed for high-resolution, high-energy X-ray scattering techniques. In this paper, the capabilities, opportunities and recent developments in the characterization of radioactive materials at XPD are described. The overarching goal of this work is to provide researchers access to advanced synchrotron techniques suited to the structural characterization of materials for advanced nuclear energy systems. XPD is a new beamline providing high photon flux for X-ray Diffraction, Pair Distribution Function analysis and Small Angle X-ray Scattering. The infrastructure and software described here extend the existing capabilitiesmore » at XPD to accommodate radioactive materials. Such techniques will contribute crucial information to the characterization and quantification of advanced materials for nuclear energy applications. Finally, we describe the automated radioactive sample collection capabilities and recent X-ray Diffraction and Small Angle X-ray Scattering results from neutron irradiated reactor pressure vessel steels and oxide dispersion strengthened steels.« less

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

Kelly, D L

The US Department of Energy (DOE) has been conducting, through several of its operating contractors, an evaluation and testing program to qualify Type A radioactive material packagings per US Department of Transportation (DOT) Specification 7A (DOT-7A) of the Code of Federal Regulations (CFR), Title 49, Part 178 (49 CFR 178). This document summarizes the evaluation and testing performed for all of the packagings successfully qualified in this program. This document supersedes DOE Evaluation Document for DOT-7A Type A Packaging (Edling 1987), originally issued in 1987 by Monsanto Research Corporation Mound Laboratory (MLM), Miamisburg, Ohio, for the Department of Energy, Securitymore » Evaluation Program (I)P-4. Mound Laboratory issued four revisions to the document between November 1988 and December 1989. In September 1989, the program was transferred to Westinghouse Hanford Company (Westinghouse Hanford) in Richland, Washington. One additional revision was issued in March 1990 by Westinghouse Hanford. This revision reflects the earlier material and incorporates a number of changes. Evaluation and testing activities on 1208 three DOT-7A Program Dockets resulted in the qualification of three new packaging configurations, which are incorporated herein and summarized. This document presents approximately 300 different packagings that have been determined to meet the requirements for a DOT-7A, type A packaging per 49 CFR 178.350.« less

3rd Quarter Transportation Report FY 2014: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

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

Gregory, Louis

2014-09-20

This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the 3rd quarter of Fiscal Year (FY) 2014 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. This report also includes annual summaries for FY 2014 in Tables 4 and 5. Tabular summaries are provided which includemore » the following: Sources of and carriers for LLW and MLLW shipments to and from the NNSS; Number and external volume of LLW and MLLW shipments; Highway routes used by carriers; and Incident/accident data applicable to LLW and MLLW shipments. In this report shipments are accounted for upon arrival at the NNSS, while disposal volumes are accounted for upon waste burial. The disposal volumes presented in this report do not include minor volumes of non-radioactive materials that were approved for disposal. Volume reports showing cubic feet generated using the Low-Level Waste Information System may vary slightly due to differing rounding conventions.« less

Annual Report to Congress of the Atomic Energy Commission for 1965

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

Seaborg, Glenn T.

1966-01-31

The document represents the 1965 Annual Report of the Atomic Energy Commission (AEC) to Congress. The report opens with a Foreword - a letter from President Lyndon B. Johnson. The main portion is divided into 3 major sections for 1965, plus 10 appendices and the index. Section names and chapters are as follows. Part One reports on Developmental and Promotional Activities with the following chapters: (1) The Atomic Energy Program - 1965; (2) The Industrial Base ; (3) Industrial Relations; (4) Operational Safety; (5) Source and Special Nuclear Materials Production; (6) The Nuclear Defense Effort; (7) Civilian Nuclear Power; (8)more » Nuclear Space Applications; (9) Auxiliary Electrical Power for Land and Sea; (10) Military Reactors; (11) Advanced Reactor Technology and Nuclear Safety Research; (12) The Plowshare Program; (13) Isotopes and Radiation Development; (14) Facilities and Projects for Basic Research; (15) International Cooperation; and, (16) Nuclear Education and Information. Part Two reports on Regulatory Activities with the following chapters: (1) Licensing and Regulating the Atom; (2) Reactors and other Nuclear Facilities; and, (3) Control of Radioactive Materials. Part Three reports on Adjudicatory Activities.« less

30S(α , p) Thermonuclear Reaction Rate from Experimental Level Structure of 34Ar

NASA Astrophysics Data System (ADS)

Kahl, D.; Chen, A. A.; Kubono, S.; Yamaguchi, H.; Binh, D. N.; Chen, J.; Cherubini, S.; Duy, N. N.; Hashimoto, T.; Hayakawa, S.; Iwasa, N.; Jung, H. S.; Kato, S.; Kwon, Y. K.; Nishimura, S.; Ota, S.; Setoodehnia, K.; Teranishi, T.; Tokieda, H.; Yamada, T.; Yun, C. C.; Zhang, L. Y.

Type I X-ray bursts are the most frequent thermonuclear explosions in the galaxy. Owing to their recurrence from known astronomical objects, burst morphology is extensively documented, and they are modeled very successfully as neutron-deficient, thermonuclear runaway on the surface of accreting neutron stars. While reaction networks include hundreds of isotopes and thousands of nuclear processes, only a small subset appear to play a pivotal role. One such reaction is the 30S(α , p) reaction, which is believed to be a crucial link in the explosive helium burning which is responsible for the large energy flux. However, very little experimental information is available concerning the cross section itself, nor the 34Ar compound nucleus at the relevant energies. We performed the first study of the entrance channel via 30S alpha resonant elastic scattering using a state-of-the-art, low-energy, 30S radioactive ion beam. The measurement was performed in inverse kinematics using a newly-developed active target. An R-matrix analysis of the excitation function reveals previously unknown resonances, including their quantum properties of spin, parity, width, and energy.

Systematic approach to characterisation of NORM in Thailand.

PubMed

Chanyotha, S; Kranrod, C; Pengvanich, P

2015-11-01

The aim of this article is to provide information on the systematic approach that has been developed for the measurement of natural radiation exposure and the characterisation of naturally occurring radioactive materials (NORM) in terms of occurrence and distribution in various industrial processes, including the produced waste from the mineral industries in Thailand. The approach can be adapted for various types of study areas. The importance of collaboration among research institutions is discussed. Some developments include 25 documents; the redesign of the field equipment, such as the gamma survey meter, for convenient access to conduct measurement in various study areas; the method to collect and analyse radon gas from a natural gas pipeline and the manganese dioxide fibre to adsorb radium on-site for laboratory analysis. The NORM project in Thailand has been carried out for more than 10 y to support the development of NORM regulation in Thailand. In the previous studies as well as current, international standards for action levels have been adopted for safety purpose. © The Author 2015. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

The ORNL Chemical Technology Division, 1950-1994

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

Jolley, R.L.; Genung, R.K.; McNeese, L.E.

1994-10-01

This document attempts to reconstruct the role played by the Chemical Technology Division (Chem Tech) of the Oak Ridge National Laboratory (ORNL) in the atomic era since the 1940`s related to the development and production of nuclear weapons and power reactors. Chem Tech`s early contributions were landmark pioneering studies. Unknown and dimly perceived problems like chemical hazards, radioactivity, and criticality had to be dealt with. New chemical concepts and processes had to be developed to test the new theories being developed by physicists. New engineering concepts had to be developed and demonstrated in order to build facilities and equipment thatmore » had never before been attempted. Chem Tech`s role was chemical separations, especially uranium and plutonium, and nuclear fuel reprocessing. With diversification of national and ORNL missions, Chem Tech undertook R&D studies in many areas including biotechnology; clinical and environmental chemistry; nuclear reactors; safety regulations; effective and safe waste management and disposal; computer modeling and informational databases; isotope production; and environmental control. The changing mission of Chem Tech are encapsulated in the evolving activities.« less

Sequim Marine Research Laboratory routine environmental measurements during CY-1977

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

Fix, J.J.; Blumer, P.J.

1978-06-01

Beginning in 1976, a routine environmental program was established at the Marine Research Laboratory (MRL) at Sequim, Washington. The program is intended to demonstrate the negligible impact of current MRL operations on the surrounding environs and to provide baseline data through which any cumulative impact could be detected. The sampling frequency is greater during the first 2 years of the program to provide sufficient initial information to allow reliable estimates of observed radionuclide concentrations and to construct a long-term sampling program. The program is designed, primarily, to determine levels of radioactivity present in selected biota in Sequim Bay. The biotamore » were selected because of their presence near the laboratory and their capacity to concentrate trace elements. Other samples were obtained to determine the radionuclides in Sequim Bay and laboratory drinking water, as well as the ambient radiation exposure levels and surface deposition of fallout radionuclides for the laboratory area. Appendix A provides a summary of the analytical methods used. The present document includes data obtained during CY 1977 in addition to CY-1976 data published previously.« less

28 CFR 513.65 - Review of documents for Freedom of Information Act requests.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 28 Judicial Administration 2 2010-07-01 2010-07-01 false Review of documents for Freedom of... JUSTICE GENERAL MANAGEMENT AND ADMINISTRATION ACCESS TO RECORDS Release of Information Freedom of Information Act Requests for Information § 513.65 Review of documents for Freedom of Information Act requests...

Radioactive materials released from nuclear power plants. Volume 13, Annual report 1992

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

Tichler, J.; Doty, K.; Lucadamo, K.

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1992 have been compiled and reported. The summary data for the years 1973 through 1991 are included for comparison. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1992 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

Radioactive materials released from nuclear power plants. Annual report 1989: Volume 10

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

Tichler, J.; Norden, K.; Congemi, J.

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1989 have been compiled and reported. The summary data for the years 1970 through 1988 are included for comparison. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1989 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

Radioactive materials released from nuclear power plants: Annual report, 1993. Volume 14

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

Tichler, J.; Doty, K.; Lucadamo, K.

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1993 have been compiled and reported. The summary data for the years 1974 through 1992 are included for comparison. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1993 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

Use of Very Weak Radiation Sources to Determine Aircraft Runway Position

NASA Technical Reports Server (NTRS)

Drinkwater, Fred J., III; Kibort, Bernard R.

1965-01-01

Various methods of providing runway information in the cockpit during the take-off and landing roll have been proposed. The most reliable method has been to use runway distance markers when visible. Flight tests were used to evaluate the feasibility of using weak radio-active sources to trigger a runway distance counter in the cockpit. The results of these tests indicate that a weak radioactive source would provide a reliable signal by which this indicator could be operated.

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

Maheras, Steven J.; Best, Ralph E.; Ross, Steven B.

A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power reactor sites was conducted. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: (1) characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory, (2) a description of the on-site infrastructure and conditionsmore » relevant to transportation of SNF and GTCC waste, (3) an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing SNF and GTCC waste, including identification of gaps in information, and (4) an evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. Every site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an important source of information used to identify the transportation mode options for the sites. Especially important in conducting the evaluation were site visits, through which information was obtained that would not have been available otherwise. Extensive photographs taken during the site visits proved to be particularly useful in documenting the current conditions at or near the sites. It is expected that additional site visits will be conducted to add to the information presented in the evaluation.« less

Characterization of strong (241)Am sources.

PubMed

Vesterlund, Anna; Chernikova, Dina; Cartemo, Petty; Axell, Kåre; Nordlund, Anders; Skarnemark, Gunnar; Ekberg, Christian; Ramebäck, Henrik

2015-05-01

Gamma ray spectra of strong (241)Am sources may reveal information about the source composition as there may be other radioactive nuclides such as progeny and radioactive impurities present. In this work the possibility to use gamma spectrometry to identify inherent signatures in (241)Am sources in order to differentiate sources from each other, is investigated. The studied signatures are age, i.e. time passed since last chemical separation, and presence of impurities. The spectra of some sources show a number of Doppler broadened peaks in the spectrum which indicate the presence of nuclear reactions on light elements within the sources. The results show that the investigated sources can be differentiated between by age and/or presence of impurities. These spectral features would be useful information in a national nuclear forensics library (NNFL) in cases when the visual information on the source, e.g. the source number, is unavailable. Copyright © 2015 Elsevier Ltd. All rights reserved.

Mexico: Centro de Documentacion e Informacion Educativa. Seminario de Documentacion e Informacion Pedagogica en America Latina (The Mexican Center for Educational Documentation and Information. Working Paper for the Seminar on Educational Documentation and Information in Latin America).

ERIC Educational Resources Information Center

Secretaria de Educacion Publica, Mexico City (Mexico). Centro de Documentacion e Informacion Educativa.

This document describes the Center for Documentation and Educational Information in Mexico City. Background information on similar services in Mexico is provided and a detailed description of the Center is presented, covering organization, objectives, administration, users, activities, services, and publications. (VM)

Failures in communication through documents and documentation across the perioperative pathway.

PubMed

Braaf, Sandra; Riley, Robin; Manias, Elizabeth

2015-07-01

To explore how communication failures occur in documents and documentations across the perioperative pathway in nurses' interactions with other nurses, surgeons and anaesthetists. Documents and documentation are used to communicate vital patient and procedural information among nurses, and in nurses' interactions with surgeons and anaesthetists, across the perioperative pathway. Previous research indicates that communication failure regularly occurs in the perioperative setting. A qualitative study was undertaken. The study was conducted over three hospitals in Melbourne, Australia. One hundred and twenty-five healthcare professionals from the disciplines of surgery, anaesthesia and nursing participated in the study. Data collection commenced in January 2010 and concluded in October 2010. Data were generated through 350 hours of observation, two focus groups and 20 semi-structured interviews. A detailed thematic analysis was undertaken. Communication failure occurred owing to a reliance on documents and documentation to transfer information at patient transition points, poor quality documents and documentation, and problematic access to information. Institutional ruling practices of professional practice, efficiency and productivity, and fiscal constraint dominated the coordination of nurses', surgeons' and anaesthetists' communication through documents and documentation. These governing practices configured communication to be incongruous with reliably meeting safety and quality objectives. Communication failure occurred because important information was sometimes buried in documents, insufficient, inaccurate, out-of-date or not verbally reinforced. Furthermore, busy nurses were not always able to access information they required in a timely manner. Patient safety was affected, which led to delays in treatment and at times inadequate care. Organisational support needs to be provided to nurses, surgeons and anaesthetists so they have sufficient time to complete, locate, and read documents and documentation. Infrastructure supporting communication technologies should be implemented to enable the rapid retrieval, entry, and dispersion of information. © 2015 John Wiley & Sons Ltd.

Directrices para la Creacion del Centro Nacional de Informacion y Documentacion (Guidelines for the Creation of a National Information and Documentation Center).

ERIC Educational Resources Information Center

Menda Behrens, Eduardo

This document discusses background information and guidelines for the creation of a national information and documentation center for the dissemination of scientific and technological information. The study first reports on information services in several other countries and the need for an information center in Venezuela; included are…

78 FR 60919 - In the Matter of Certain Licensees Authorized To Possess and Transfer Items Containing...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-10-02

.... Access to Safeguards Information is limited to those persons who have established a need-to-know the... to Safeguards Information'' (EA-13-041). A need-to-know means a determination by a person having... access. 2. No person may have access to Safeguards Information or unescorted access to radioactive...

Internet as a Source of Misconception: "Radiation and Radioactivity"

ERIC Educational Resources Information Center

Acar Sesen, Burcin; Ince, Elif

2010-01-01

The purpose of this study is to examine students' usage styles of the Internet for seeking information and to investigate whether information obtained from the Internet is a source of misconceptions. For this reason, a two-stage study was conducted. At the first stage, a questionnaire was developed to get information about students' Internet usage…

75 FR 60146 - Agency Information Collection Activities: Submission for the Office of Management and Budget (OMB...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-09-29

... title of the information collection: 10 CFR Part 34, ``Licenses for Radiography and Radiation Safety.... Abstract: 10 CFR Part 34 establishes radiation safety requirements for the use of radioactive material in industrial radiography. The information in the applications, reports and records is used by the NRC staff to...

Traveler information services in rural tourism areas : appendix A, tourist intercept surveys

DOT National Transportation Integrated Search

2000-06-30

This document presents documentation regarding tourist intercept surveys for traveler information services in rural areas. It documents data collection functions and information dissemination functions, and provides an interpretive description of tra...

78 FR 63470 - Agency Information Collection Activities: Proposed Information Collection; Submission for OMB Review

Federal Register 2010, 2011, 2012, 2013, 2014

2013-10-24

... information collection titled, ``Annual Stress Test Reporting Template and Documentation for Covered Banks.... Email: [email protected] . Include ``Annual Stress Test Reporting Template and Documentation'' on the... information collection: Annual Stress Test Reporting Template and Documentation for Covered Banks With Total...

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

Jung, Haeryong; Lee, Eunyong; Jeong, YiYeong

Korea Radioactive-waste Management Corporation (KRMC) established in 2009 has started a new project to collect information on long-term stability of deep geological environments on the Korean Peninsula. The information has been built up in the integrated natural barrier database system available on web (www.deepgeodisposal.kr). The database system also includes socially and economically important information, such as land use, mining area, natural conservation area, population density, and industrial complex, because some of this information is used as exclusionary criteria during the site selection process for a deep geological repository for safe and secure containment and isolation of spent nuclear fuel andmore » other long-lived radioactive waste in Korea. Although the official site selection process has not been started yet in Korea, current integrated natural barrier database system and socio-economic database is believed that the database system will be effectively utilized to narrow down the number of sites where future investigation is most promising in the site selection process for a deep geological repository and to enhance public acceptance by providing readily-available relevant scientific information on deep geological environments in Korea. (authors)« less

10 CFR 72.9 - Information collection requirements: OMB approval.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Information collection requirements: OMB approval. 72.9 Section 72.9 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C...

10 CFR 72.9 - Information collection requirements: OMB approval.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Information collection requirements: OMB approval. 72.9 Section 72.9 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C...

77 FR 70995 - Agency Information Collection Extension

Federal Register 2010, 2011, 2012, 2013, 2014

2012-11-28

... Radioactive Waste, entered into by DOE and the generators or owners of spent nuclear fuel. The proposed..., 735 17th Street NW., Washington, DC 20503. and to: Department of Energy, U.S. Energy Information Administration, Attn: Marta Gospodarczyk, EI-34, Forrestal Building, 1000 Independence Ave. SW., Washington, DC...

10 CFR 72.11 - Completeness and accuracy of information.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Completeness and accuracy of information. 72.11 Section 72.11 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C...

10 CFR 72.11 - Completeness and accuracy of information.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Completeness and accuracy of information. 72.11 Section 72.11 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C...

10 CFR 72.11 - Completeness and accuracy of information.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Completeness and accuracy of information. 72.11 Section 72.11 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C...

10 CFR 72.11 - Completeness and accuracy of information.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Completeness and accuracy of information. 72.11 Section 72.11 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C...

10 CFR 72.11 - Completeness and accuracy of information.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Completeness and accuracy of information. 72.11 Section 72.11 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C...

10 CFR 61.14 - Institutional information.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Institutional information. 61.14 Section 61.14 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE... proposed disposal site is on land not owned by the Federal or a State government, the applicant must submit...

10 CFR 61.14 - Institutional information.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Institutional information. 61.14 Section 61.14 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE... proposed disposal site is on land not owned by the Federal or a State government, the applicant must submit...

10 CFR 61.14 - Institutional information.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Institutional information. 61.14 Section 61.14 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE... proposed disposal site is on land not owned by the Federal or a State government, the applicant must submit...

10 CFR 61.14 - Institutional information.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Institutional information. 61.14 Section 61.14 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE... proposed disposal site is on land not owned by the Federal or a State government, the applicant must submit...

10 CFR 61.14 - Institutional information.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Institutional information. 61.14 Section 61.14 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE... proposed disposal site is on land not owned by the Federal or a State government, the applicant must submit...

Executive overview and introduction to the SMAP information system life-cycle and documentation standards

NASA Technical Reports Server (NTRS)

1989-01-01

An overview of the five volume set of Information System Life-Cycle and Documentation Standards is provided with information on its use. The overview covers description, objectives, key definitions, structure and application of the standards, and document structure decisions. These standards were created to provide consistent NASA-wide structures for coordinating, controlling, and documenting the engineering of an information system (hardware, software, and operational procedures components) phase by phase.

78 FR 79708 - Notice of Receipt of Complaint; Solicitation of Comments Relating to the Public Interest

Federal Register 2010, 2011, 2012, 2013, 2014

2013-12-31

... accessed on the Commission's Electronic Document Information System (EDIS) at EDIS,\\1\\ and will be...-2000. \\1\\ Electronic Document Information System (EDIS): http://edis.usitc.gov . General information... the Commission's Electronic Document Information System (EDIS) at EDIS.\\3\\ Hearing-impaired persons...

Advance assessment for movement of Haz Cat 3 radioactive materials.

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

Vosburg, Susan K.

2010-04-01

The current packaging of most HC-3 radioactive materials at SNL/NM do not meet DOT requirements for offsite shipment. SNL/NM is transporting HC-3 quantities of radioactive materials from their storage locations in the Manzano Nuclear Facilities bunkers to facilities in TA-5 to be repackaged for offsite shipment. All transportation of HC-3 rad material by SNL/NM is onsite (performed within the confines of KAFB). Transport is performed only by the Regulated Waste/Nuclear Material Disposition Department. Part of the HC3T process is to provide the CAT with the following information at least three days prior to the move: (1) RFt-Request for transfer; (2)more » HC3T movement report; (3) Radiological survey; and (4) Transportation Route Map.« less

An overview of selected information storage and retrieval issues in computerized document processing

NASA Technical Reports Server (NTRS)

Dominick, Wayne D. (Editor); Ihebuzor, Valentine U.

1984-01-01

The rapid development of computerized information storage and retrieval techniques has introduced the possibility of extending the word processing concept to document processing. A major advantage of computerized document processing is the relief of the tedious task of manual editing and composition usually encountered by traditional publishers through the immense speed and storage capacity of computers. Furthermore, computerized document processing provides an author with centralized control, the lack of which is a handicap of the traditional publishing operation. A survey of some computerized document processing techniques is presented with emphasis on related information storage and retrieval issues. String matching algorithms are considered central to document information storage and retrieval and are also discussed.

Effects of increased nurses' workload on quality documentation of patient information at selected Primary Health Care facilities in Vhembe District, Limpopo Province.

PubMed

Shihundla, Rhulani C; Lebese, Rachel T; Maputle, Maria S

2016-05-13

Recording of information on multiple documents increases professional nurses' responsibilities and workload during working hours. There are multiple registers and books at Primary Health Care (PHC) facilities in which a patient's information is to be recorded for different services during a visit to a health professional. Antenatal patients coming for the first visit must be recorded in the following documents: tick register; Prevention of Mother-ToChild Transmission (PMTCT) register; consent form for HIV and AIDS testing; HIV Counselling and Testing (HCT) register (if tested positive for HIV and AIDS then this must be recorded in the Antiretroviral Therapy (ART) wellness register); ART file with an accompanying single file, completion of which is time-consuming; tuberculosis (TB) suspects register; blood specimen register; maternity case record book and Basic Antenatal Care (BANC) checklist. Nurses forget to record information in some documents which leads to the omission of important data. Omitting information might lead to mismanagement of patients. Some of the documents have incomplete and inaccurate information. As PHC facilities in Vhembe District render twenty four hour services through a call system, the same nurses are expected to resume duty at 07:00 the following morning. They are expected to work effectively and when tired a nurse may record illegible information which may cause problems when the document is retrieved by the next person for continuity of care. The objective of this study was to investigate and describe the effects of increased nurses' workload on quality documentation of patient information at PHC facilities in Vhembe District, Limpopo Province. The study was conducted in Vhembe District, Limpopo Province, where the effects of increased nurses' workload on quality documentation of information is currently experienced. The research design was explorative, descriptive and contextual in nature. The population consisted of all nurses who work at PHC facilities in Vhembe District. Purposive sampling was used to select nurses and three professional nurses were sampled from each PHC facility. An in-depth face-to-face interview was used to collect data using an interview guide. PHC facilities encountered several effects due to increased nurses' workload where incomplete patient information is documented. Unavailability of patient information was observed, whilst some documented information was found to be illegible, inaccurate and incomplete. Documentation of information at PHC facilities is an evidence of effective communication amongst professional nurses. There should always be active follow-up and mentoring of the nurses' documentation to ensure that information is accurately and fully documented in their respective facilities. Nurses find it difficult to cope with the increased workload associated with documenting patient information on the multiple records that are utilized at PHC facilities, leading to incomplete information. The number of nurses at facilities should be increased to reduce the increased workload.

EMP Attachment 3 DOE-SC PNNL Site Dose Assessment Guidance

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

Snyder, Sandra F.

2011-12-21

This Dose Assessment Guidance (DAG) describes methods to use to determine the Maximally-Exposed Individual (MEI) location and to estimate dose impact to that individual under the U.S. Department of Energy Office of Science (DOE-SC) Pacific Northwest National Laboratory (PNNL) Site Environmental Monitoring Plan (EMP). This guidance applies to public dose from radioactive material releases to the air from PNNL Site operations. This document is an attachment to the Pacific Northwest National Laboratory (PNNL) Environmental Monitoring Plan (EMP) and describes dose assessment guidance for radiological air emissions. The impact of radiological air emissions from the U.S. Department of Energy Office ofmore » Science (DOE-SC) PNNL Site is indicated by dose estimates to a maximally exposed member of the public, referred to as the maximally exposed individual (MEI). Reporting requirements associated with dose to members of the public from radiological air emissions are in 40 CFR Part 61.94, WAC 246-247-080, and DOE Order 458.1. The DOE Order and state standards for dose from radioactive air emissions are consistent with U.S. Environmental Protection Agency (EPA) dose standards in 40 CFR 61.92 (i.e., 10 mrem/yr to a MEI). Despite the fact that the current Contract Requirements Document (CRD) for the DOE-SC PNNL Site operations does not include the requirement to meet DOE CRD 458.1, paragraph 2.b, public dose limits, the DOE dose limits would be met when EPA limits are met.« less

CERISE, a French radioprotection code, to assess the radiological impact and acceptance criteria of installations for material handling, and recycling or disposal of very low-level radioactive waste

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

Santucci, P.; Guetat, P.

1993-12-31

This document describes the code CERISE, Code d`Evaluations Radiologiques Individuelles pour des Situations en Enterprise et dans l`Environnement. This code has been developed in the frame of European studies to establish acceptance criteria of very low-level radioactive waste and materials. This code is written in Fortran and runs on PC. It calculates doses received by the different pathways: external exposure, ingestion, inhalation and skin contamination. Twenty basic scenarios are already elaborated, which have been determined from previous studies. Calculations establish the relation between surface, specific and/or total activities, and doses. Results can be expressed as doses for an average activitymore » unit, or as average activity limits for a set of reference doses (defined for each scenario analyzed). In this last case, the minimal activity values and the corresponding limiting scenarios, are selected and summarized in a final table.« less

Dewatering Treatment Scale-up Testing Results of Hanford Tank Wastes

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

Tedeschi, A.R.; May, T.H.; Bryan, W.E.

2008-07-01

This report documents CH2M HILL Hanford Group Inc. (CH2M HILL) 2007 dryer testing results in Richland, WA at the AMEC Nuclear Ltd., GeoMelt Division (AMEC) Horn Rapids Test Site. It provides a discussion of scope and results to qualify the dryer system as a viable unit-operation in the continuing evaluation of the bulk vitrification process. A 10,000 liter (L) dryer/mixer was tested for supplemental treatment of Hanford tank low activity wastes, drying and mixing a simulated non-radioactive salt solution with glass forming minerals. Testing validated the full scale equipment for producing dried product similar to smaller scale tests, and qualifiedmore » the dryer system for a subsequent integrated dryer/vitrification test using the same simulant and glass formers. The dryer system is planned for installation at the Hanford tank farms to dry/mix radioactive waste for final treatment evaluation of the supplemental bulk vitrification process. (authors)« less

Separation science and technology. Semiannual progress report, October 1993--March 1994

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

Vandegrift, G.F.; Aase, S.B.; Buchholz, B.

1997-12-01

This document reports on the work done by the Separations Science and Technology Programs of the Chemical Technology Division, Argonne National Laboratory (ANL), in the period October 1993-March 1994. This effort is mainly concerned with developing the TRUEX process for removing and concentrating actinides from acidic waste streams contaminated with transuranic (TRU) elements. The objectives of TRUEX processing are to recover valuable TRU elements and to lower disposal costs for the nonTRU waste product of the process. Other projects are underway with the objective of developing (1) evaporation technology for concentrating radioactive waste and product streams such as those generatedmore » by the TRUEX process, (2) treatment schemes for liquid wastes stored are being generated at ANL, (3) a process based on sorbing modified TRUEX solvent on magnetic beads to be used for separation of contaminants from radioactive and hazardous waste streams, and (4) a process that uses low-enriched uranium targets for production of {sup 99}Mo for nuclear medicine uses.« less

Reconciling disparate information in continuity of care documents: Piloting a system to consolidate structured clinical documents.

PubMed

Hosseini, Masoud; Jones, Josette; Faiola, Anthony; Vreeman, Daniel J; Wu, Huanmei; Dixon, Brian E

2017-10-01

Due to the nature of information generation in health care, clinical documents contain duplicate and sometimes conflicting information. Recent implementation of Health Information Exchange (HIE) mechanisms in which clinical summary documents are exchanged among disparate health care organizations can proliferate duplicate and conflicting information. To reduce information overload, a system to automatically consolidate information across multiple clinical summary documents was developed for an HIE network. The system receives any number of Continuity of Care Documents (CCDs) and outputs a single, consolidated record. To test the system, a randomly sampled corpus of 522 CCDs representing 50 unique patients was extracted from a large HIE network. The automated methods were compared to manual consolidation of information for three key sections of the CCD: problems, allergies, and medications. Manual consolidation of 11,631 entries was completed in approximately 150h. The same data were automatically consolidated in 3.3min. The system successfully consolidated 99.1% of problems, 87.0% of allergies, and 91.7% of medications. Almost all of the inaccuracies were caused by issues involving the use of standardized terminologies within the documents to represent individual information entries. This study represents a novel, tested tool for de-duplication and consolidation of CDA documents, which is a major step toward improving information access and the interoperability among information systems. While more work is necessary, automated systems like the one evaluated in this study will be necessary to meet the informatics needs of providers and health systems in the future. Copyright © 2017 Elsevier Inc. All rights reserved.

Informed consent document improvement does not increase patients' comprehension in biomedical research

PubMed Central

Paris, Adeline; Brandt, Christian; Cornu, Catherine; Maison, Patrick; Thalamas, Claire; Cracowski, Jean-Luc

2010-01-01

AIMS International guidelines on ethics in biomedical research require that the informed consent of all enrolled participants is obtained. A written document describing the research, the informed consent (IC) document, must be given to all participants by the investigator. Most IC documents are long, containing much information. The aim of the present study was to determine whether the modification of the IC document by a working group or systematic improvement in its lexicosyntactic readability can improve comprehension of the written information given to patients participating in biomedical research. METHODS One hundred and fifty-nine patients were randomized to read one of the three versions of the IC document: unchanged document, document modified using systematic improvement of lexicosyntactic readability and document modified by a working group. RESULTS Neither the improvement in the lexicosyntactic readability, nor the intervention of the working group significantly improved the score of objective comprehension for the subjects included in this study: it was 66.6 (95% confidence interval 64.0, 69.2) for the control group, 68.8 (66.2, 71.4) for the group with the document improved for lexicosyntactic readability and 69.2 (66.0, 72.4) for the group who read the document improved by the working group (P= 0.38). CONCLUSIONS We failed to show that improving IC document comprehension through a lexicosyntactic approach or by a working group leads to better comprehension. PMID:20233193

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.

Harmonization - Two Years' of Transportation Regulation Lessons Learned

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

Colborn, K.

2007-07-01

The U.S. Department of Transportation issued modifications to the Hazardous Materials Regulations in October, 2004 as part of an ongoing effort to 'harmonize' U.S. regulations with those of the International Atomic Energy Agency. The harmonization effort had several predictable effects on low level radioactive materials shipment that were anticipated even prior to their implementation. However, after two years' experience with the new regulations, transporters have identified several effects on transportation which were not entirely apparent when the regulations were first implemented. This paper presents several case studies in the transportation of low level radioactive materials since the harmonization rules tookmore » effect. In each case, an analysis of the challenge posed by the regulatory revision is provided. In some cases, more than one strategy for compliance was considered, and the advantages and disadvantages of each are discussed. In several cases, regulatory interpretations were sought and obtained, and these are presented to clarify the legitimacy of the compliance approach. The presentation of interpretations will be accompanied by reports of clarifying discussions with the U.S. DOT about the interpretation and scope of the regulatory change. Specific transportation issues raised by the revised hazardous materials regulations are reviewed, including: The new definition of radioactive material in accordance with isotope-specific concentration and total activity limits. The new hazardous materials regulations (HMR) created a new definition for radioactive material. A case study is presented for soils contaminated with low levels of Th-230. These soils had been being shipped for years as exempt material under the old 2,000 pCi/g concentration limit. Under the new HMR, these same soils were radioactive material. Further, in rail-car quantities their activity exceeded an A2 value, so shipment of the material in gondolas appeared to require an IP-2 package. Interpretations, discussions, and an exemption were obtained to secure the continued shipment of this material. A provision to allow 'natural' radioactive materials to be exempt from the requirements of the HMR at up to 10x the listed isotopic concentrations. The revised HMR exempts certain natural materials and ores from regulation as radioactive material at concentrations up to 10x that allowed if the materials are not natural. The term 'natural' is not well defined, and initial attempts to qualify for this exemption were thwarted by concerns over what degree of material processing, if any, materials could experience and still be considered 'natural'. The presentation includes an example from a project involving post-processed tungsten ore, and includes interpretations from the US DOT as well as clarifying language from current and drafted IAEA regulation and guidance. New packaging descriptions allowing the use of cargo containers as IP-2 and IP-3 packages in some applications. The revised HMR provides an alternate certification procedure under which standard cargo containers can be used as IP-2 and IP-3 containers. There has been some confusion about how this high level of certification can apply to standard cargo containers when other sections of the regulations make this certification available only to considerably more stout containers after rigorous testing. The discussion includes interpretive guidance from the US DOT, and from the UK Department of Transport clarifying the same provision in IAEA regulations. A new definition of contamination with apparently broad impact on the shipment of empty containers and conveyances. The revised HMR presented a definition of contamination not referenced by any other part of the HMR. The preamble to the revised HMR provides confusing guidance on the application of the definition to shipment of empty containers, and subsequent interpretive guidance letters appear to conflict with the preamble as well as with each other. The definition also has the effect of regulating materials for transport as radioactive even when US NRC and US Department of Energy (DOE) guidance documents suggest that the materials are free-releasable. This presentation provides the latest available information on this emerging issue. The presentation strives to provide the benefit of recent real-world experience in new aspects of the HMR. The examples provides should have broad application to shippers of a variety of low level radioactive materials in the US and internationally. (authors)« less

10 CFR 72.22 - Contents of application: General and financial information.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Contents of application: General and financial information. 72.22 Section 72.22 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN...

10 CFR 71.7 - Completeness and accuracy of information.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Completeness and accuracy of information. 71.7 Section 71.7 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PACKAGING AND TRANSPORTATION OF RADIOACTIVE.... Notification must be provided to the Administrator of the appropriate Regional Office within 2 working days of...

10 CFR 63.10 - Completeness and accuracy of information.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Completeness and accuracy of information. 63.10 Section 63.10 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN A.... Notification must be provided to the Director of Nuclear Material Safety and Safeguards, U.S. Nuclear...

10 CFR 60.10 - Completeness and accuracy of information.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Completeness and accuracy of information. 60.10 Section 60.10 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN... provided to the Administrator of the appropriate Regional Office within two working days of identifying the...

10 CFR 71.7 - Completeness and accuracy of information.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Completeness and accuracy of information. 71.7 Section 71.7 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PACKAGING AND TRANSPORTATION OF RADIOACTIVE.... Notification must be provided to the Administrator of the appropriate Regional Office within 2 working days of...

10 CFR 60.10 - Completeness and accuracy of information.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Completeness and accuracy of information. 60.10 Section 60.10 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN... provided to the Administrator of the appropriate Regional Office within two working days of identifying the...

10 CFR 60.10 - Completeness and accuracy of information.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Completeness and accuracy of information. 60.10 Section 60.10 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN... provided to the Administrator of the appropriate Regional Office within two working days of identifying the...

10 CFR 71.7 - Completeness and accuracy of information.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Completeness and accuracy of information. 71.7 Section 71.7 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PACKAGING AND TRANSPORTATION OF RADIOACTIVE.... Notification must be provided to the Administrator of the appropriate Regional Office within 2 working days of...

10 CFR 71.7 - Completeness and accuracy of information.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Completeness and accuracy of information. 71.7 Section 71.7 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PACKAGING AND TRANSPORTATION OF RADIOACTIVE.... Notification must be provided to the Administrator of the appropriate Regional Office within 2 working days of...

10 CFR 63.10 - Completeness and accuracy of information.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Completeness and accuracy of information. 63.10 Section 63.10 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN A.... Notification must be provided to the Director of Nuclear Material Safety and Safeguards, U.S. Nuclear...

10 CFR 63.10 - Completeness and accuracy of information.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Completeness and accuracy of information. 63.10 Section 63.10 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN A.... Notification must be provided to the Director of Nuclear Material Safety and Safeguards, U.S. Nuclear...

10 CFR 63.10 - Completeness and accuracy of information.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Completeness and accuracy of information. 63.10 Section 63.10 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN A.... Notification must be provided to the Director of Nuclear Material Safety and Safeguards, U.S. Nuclear...

10 CFR 71.7 - Completeness and accuracy of information.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Completeness and accuracy of information. 71.7 Section 71.7 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PACKAGING AND TRANSPORTATION OF RADIOACTIVE.... Notification must be provided to the Administrator of the appropriate Regional Office within 2 working days of...

10 CFR 60.10 - Completeness and accuracy of information.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Completeness and accuracy of information. 60.10 Section 60.10 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN... provided to the Administrator of the appropriate Regional Office within two working days of identifying the...

10 CFR 63.10 - Completeness and accuracy of information.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Completeness and accuracy of information. 63.10 Section 63.10 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN A.... Notification must be provided to the Director of Nuclear Material Safety and Safeguards, U.S. Nuclear...

Quantitative and qualitative analysis of study-related patient information sheets in randomised neuro-oncology phase III-trials.

PubMed

Reinert, Christiane; Kremmler, Lukas; Burock, Susen; Bogdahn, Ulrich; Wick, Wolfgang; Gleiter, Christoph H; Koller, Michael; Hau, Peter

2014-01-01

In randomised controlled trials (RCTs), patient informed consent documents are an essential cornerstone of the study flow. However, these documents are often oversized in format and content. Clinical experience suggests that study information sheets are often not used as an aid to decision-making due to their complexity. We analysed nine patient informed consent documents from clinical neuro-oncological phase III-studies running at a German Brain Tumour Centre with the objective to investigate the quality of these documents. Text length, formal layout, readability, application of ethical and legal requirements, scientific evidence and social aspects were used as rating categories. Results were assessed quantitatively by two independents investigators and were depicted using net diagrams. All patient informed consent documents were of insufficient quality in all categories except that ethical and legal requirements were fulfilled. Notably, graduate levels were required to read and understand five of nine consent documents. Quality deficits were consistent between the individual study information texts. Irrespective of formal aspects, a document that is intended to inform and motivate patients to participate in a study needs to be well-structured and understandable. We therefore strongly mandate to re-design patient informed consent documents in a patient-friendly way. Specifically, standardised components with a scientific foundation should be provided that could be retrieved at various times, adapted to the mode of treatment and the patient's knowledge, and could weigh information dependent of the stage of treatment decision. Copyright © 2013 Elsevier Ltd. All rights reserved.

Radioactive seed migration following parotid gland interstitial brachytherapy.

PubMed

Fan, Yi; Huang, Ming-Wei; Zhao, Yi-Jiao; Gao, Hong; Zhang, Jian-Guo

To evaluate the incidence and associated factors of pulmonary seed migration after parotid brachytherapy using a novel migrated seed detection technique. Patients diagnosed with parotid cancer who underwent permanent parotid brachytherapy from January 2006 to December 2011 were reviewed retrospectively. Head and neck CT scans and chest X-rays were evaluated during routine follow-up. Mimics software and Geomagic Studio software were used for seed reconstruction and migrated seed detection from the original implanted region, respectively. Postimplant dosimetry analysis was performed after seeds migration if the seeds were still in their emitting count. Adverse clinical sequelae from seed embolization to the lung were documented. The radioactive seed implants were identified on chest X-rays in 6 patients. The incidence rate of seed migration in 321 parotid brachytherapy patients was 1.87% (6/321) and that of individual seed migration was 0.04% (6/15218 seeds). All migrated seeds were originally from the retromandibular region. No adverse dosimetric consequences were found in the target region. Pulmonary symptoms were not reported by any patient in this study. In our patient set, migration of radioactive seeds with an initial radioactivity of 0.6-0.7 mCi to the chest following parotid brachytherapy was rare. Late migration of a single seed from the central target region did not affect the dosimetry significantly, and patients did not have severe short-term complications. This study proposed a novel technique to localize the anatomical origin of the migrated seeds during brachytherapy. Our evidence suggested that placement of seeds adjacent to blood vessels was associated with an increased likelihood of seed migration to the lungs. Copyright © 2017 American Brachytherapy Society. Published by Elsevier Inc. All rights reserved.

Satisfying the needs of Japanese cancer patients: a comparative study of detailed and standard informed consent documents.

PubMed

Sato, Keiko; Watanabe, Toru; Katsumata, Noriyuki; Sato, Tosiya; Ohashi, Yasuo

2014-02-01

Simplified informed consent forms have been successful in improving patient satisfaction and decreasing patient anxiety. However, unsolved problems remain about whether these documents improve comprehension and satisfaction of patients with standard literacy skills. s To investigate whether a detailed consent form explaining the key elements of informed consent, in comparison to a standard consent form, would increase the comprehension and satisfaction of adult cancer patients. Patients who were eligible for the National Surgical Adjuvant Study of Breast Cancer (protocol 01(N-SAS/BC-01)) were randomly selected to receive one of the following four versions: detailed document with graphics, detailed document without graphics, standard document with graphics, and standard document without graphics. The forms were written in plain language from the patients' point of view. A total of 85 patients were administered questionnaires via interview to assess levels of comprehension, satisfaction, and anxiety. Patients demonstrated a strong understanding of information regarding treatment and research. Patient comprehension did not differ significantly between the detailed document arms and the standard document arms. Patient satisfaction level increased according to the amount of information presented in the consent form; most patients preferred the detailed document with graphics. Anxiety and accrual rates in the parent study were not affected by informed consent procedures. Findings were limited to adults who had standard literacy skills and may not be generalizable to a population with lower literacy. Informed consent can be a significant experience for a population with standard literacy skills, as long as the document is easily comprehensible. Such information should be provided in a format that corresponds with patient needs, education levels, and preferences.

77 FR 65706 - Agency Information Collection Activities: Request for the Return of Original Documents, Form...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-10-30

...-0100] Agency Information Collection Activities: Request for the Return of Original Documents, Form... Collection. (2) Title of the Form/Collection: Request for the Return of Original Documents. (3) Agency form... obtain original document(s) contained in an alien file. (5) An estimate of the total number of...

77 FR 47426 - Agency Information Collection Activities: Request for the Return of Original Documents, Form...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-08-08

...-0100] Agency Information Collection Activities: Request for the Return of Original Documents, Form.... (2) Title of the Form/Collection: Request for the Return of Original Documents. (3) Agency form... obtain original document(s) contained in an alien file. (5) An estimate of the total number of...

An updated look at document security: from initiation to storage or shredder.

PubMed

McConnell, Charles R

2014-01-01

In these days of close attention to security of information handled electronically, there is often a tendency to overlook the security of hard-copy documents. Document security can involve many areas of business, but the health care department manager's concerns are primarily for patient records and employee documentation. Document security is closely related to growing concerns for individual privacy; guidelines are furnished for protecting employee privacy by separating retention practices for business information from personal information. Sensitive documentation requires rules and procedures for processing, retaining, accessing, storing, and eventually destroying. Also, documents that are missing or incomplete at times present unique problems for the organization. The department manager is provided with some simple rules for safeguarding employee and patient documentation.

7 CFR 1423.6 - Financial information documentation requirements.

Code of Federal Regulations, 2010 CFR

2010-01-01

... CORPORATION APPROVED WAREHOUSES § 1423.6 Financial information documentation requirements. To be approved under this part, a warehouse operator shall submit a current financial statement at the time of... 7 Agriculture 10 2010-01-01 2010-01-01 false Financial information documentation requirements...

47 CFR 6.11 - Information, documentation, and training.

Code of Federal Regulations, 2010 CFR

2010-10-01

... 47 Telecommunication 1 2010-10-01 2010-10-01 false Information, documentation, and training. 6.11 Section 6.11 Telecommunication FEDERAL COMMUNICATIONS COMMISSION GENERAL ACCESS TO TELECOMMUNICATIONS... Obligations-What Must Covered Entities Do? § 6.11 Information, documentation, and training. (a) Manufacturers...

2nd Quarter Transportation Report FY 2014

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

Gregory, L.

2014-07-01

This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the second quarter of fiscal year (FY) 2014 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. This report also includes annual summaries for FY 2014 in Tables 4 and 5. Tabular summaries are provided which includemore » the following: Sources of and carriers for LLW and MLLW shipments to and from the NNSS; Number and external volume of LLW and MLLW shipments; Highway routes used by carriers; and Incident/accident data applicable to LLW and MLLW shipments. In this report shipments are accounted for upon arrival at the NNSS, while disposal volumes are accounted for upon waste burial. The disposal volumes presented in this report do not include minor volumes of non-radioactive materials that were approved for disposal. Volume reports showing cubic feet (ft3) generated using the Low-Level Waste Information System may vary slightly due to differing rounding conventions.« less

Hydrogen Production in Radioactive Solutions in the Defense Waste Processing Facility

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

CRAWFORD, CHARLES L.

2004-05-26

In the radioactive slurries and solutions to be processed in the Defense Waste Processing Facility (DWPF), hydrogen will be produced continuously by radiolysis. This production results from alpha, beta, and gamma rays from decay of radionuclides in the slurries and solutions interacting with the water. More than 1000 research reports have published data concerning this radiolytic production. The results of these studies have been reviewed in a comprehensive monograph. Information about radiolytic hydrogen production from the different process tanks is necessary to determine air purge rates necessary to prevent flammable mixtures from accumulating in the vapor spaces above these tanks.more » Radiolytic hydrogen production rates are usually presented in terms of G values or molecules of hydrogen produced per 100ev of radioactive decay energy absorbed by the slurry or solution. With the G value for hydrogen production, G(H2), for a particular slurry and the concentrations of radioactive species in that slurry, the rate of H2 production for that slurry can be calculated. An earlier investigation estimated that the maximum rate that hydrogen could be produced from the sludge slurry stream to the DWPF is with a G value of 0.45 molecules per 100ev of radioactive decay energy sorbed by the slurry.« less

Determination of gamma-emitting radionuclides in the inter-tidal sediments off Balochistan (Pakistan) Coast, Arabian Sea.

PubMed

Akram, M; Qureshi, Riffat M; Ahmad, Nasir; Solaija, Tariq Jamal

2007-01-01

Natural radionuclide contents of 226Ra, 228Ra and (40)K were studied for inter-tidal sediments collected from selected locations off the745 km long Balochistan Coast using HPGe detector based gamma-spectrometry system. The sampling zone extends from the beaches of Sonmiani (near Karachi metropolis) through Jiwani (close to the border of Iran). The natural radioactivity levels detected in various sediment samples range from 14.4 +/- 2.5 to 36.6 +/- 3.8 Bq kg(-1) for 226Ra, 9.8 +/- 1.2 to 35.2 +/- 2.0 Bq kg(-1) for (228)Ra and 144.6 +/- 9.4 to 610.5 +/- 23.9 Bq kg(-1) for (40)K. No artificial radionuclide was detected in any of the marine coastal sediment samples. 137Cs, (60)Co, 106Ru and 144Ce contents in sediment samples were below the limit of detection. The measured radioactivity levels are compared with those reported in the literature for coastal sediments in other parts of the world. The information presented in this paper will serve as the first ever local radioactivity database for the Balochistan/Makran Coastal belt of Pakistan. The presented data will also contribute to the IAEA's, Asia-Pacific Marine Radioactivity Database (ASPAMARD) and the Global Marine Radioactivity Database (GLOMARD).

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

Wacker, John F.; Curry, Michael

The interpretation of data from the nuclear forensic analysis of illicit nuclear material of unknown origin requires comparative data from samples of known origin. One way to provide such comparative data is to create a system of national nuclear forensics libraries, in which each participating country stores information about nuclear or other radioactive material that either resides in or was manufactured by that country. Such national libraries could provide an authoritative record of the material located in or produced by a particular country, and thus forms an essential prerequisite for a government to investigate illicit uses of nuclear or othermore » radioactive material within its borders. We describe the concept of the national nuclear forensic library, recommendations for content and structure, and suggested querying methods for utilizing the information for addressing nuclear smuggling.« less

Critical Infrastructure References: Documented Literature Search

DTIC Science & Technology

2012-10-01

the literature search document can be a resource for DRDC and external partners. Future plans: At present, the electronic copies of the reference...Personal Information Protection and Electronic Documents Act (S.C. 2000, c. 5) Title: Personal Information Protection and Electronic Documents Act (S.C...2011 Overview: • "An Act to support and promote electronic commerce by protecting personal information that is collected, used or disclosed in

Prospective implementation of a software application for pre-disposal L/ILW waste management activities in Romania

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

Fako, Raluca; Sociu, Florin; Stan, Camelia

Romania is actively engaged to update the Medium and Long Term National Strategy for Safe Management of Radioactive Waste and to approve the Road Map for Geological Repository Development. Considering relevant documents to be further updated, about 122,000 m{sup 3} SL-LILW are to be disposed in a near surface facility that will have room, also, for quantities of VLLW. Planned date for commissioning is under revision. Taking into account that in this moment there are initiated several actions for the improvement of the technical capability for LILW treatment and conditioning, several steps for the possible use of SAFRAN software weremore » considered. In view of specific data for Romanian radioactive waste inventory, authors are trying to highlight the expected limitations and unknown data related with the implementation of SAFRAN software for the foreseen pre-disposal waste management activities. There are challenges that have to be faced in the near future related with clear definition of the properties of each room, area and waste management activity. This work has the aim to address several LILW management issues in accordance with national and international regulatory framework for the assurance of nuclear safety. Also, authors intend to develop their institutional capability for the safety demonstration of the existent and future radioactive waste management facilities and activities. (authors)« less

Automated management of radioactive sources in Saudi Arabia

NASA Astrophysics Data System (ADS)

Al-Kheliewi, Abdullah S.; Jamil, M. F.; Basar, M. R.; Tuwaili, W. R.

2014-09-01

For usage of radioactive substances, any facility has to register and take license from relevant authority of the country in which such facility is operating. In the Kingdom of Saudi Arabia (KSA), the authority for managing radioactive sources and providing licenses to organizations for its usage is the National Center of Radiation Protection (NCRP). This paper describes the system that automates registration and licensing process of the National Center of Radiation Protection. To provide 24×7 accesses to all the customers of NCRP, system is developed as web-based application that provide facility to online register, request license, renew license, check request status, view historical data and reports etc. and other features are provided as Electronic Services that would be accessible to users via internet. The system also was designed to streamline and optimize internal operations of NCRP besides providing ease of access to its customers by implementing a defined workflow through which every registration and license request will be routed. In addition to manual payment option, the system would also be integrated with SADAD (online payment system) that will avoid lengthy and cumbersome procedures associated with manual payment mechanism. Using SADAD payment option license fee could be paid through internet/ATM machine or branch of any designated bank, Payment will be instantly notified to NCRP hence delay in funds transfer and verification of invoice could be avoided, SADAD integration is discussed later in the document.

Test report dot 7A type a liquid packaging

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

Ketusky, E. T.; Brandjes, C.; Benoit, T. J.

This test report documents the performance of Savannah River National Laboratory’s (SRNL’s) U.S. Department of Transportation (DOT) Specification 7A; General Packaging, Type A shielded liquid shipping packaging and compliance with the regulatory requirements of Title 49 of the Code of Federal Regulations (CFR). The primary use of this packaging design is for the transport of radioactive liquids of up to 1.3 liters in an unshielded configuration and up to 113 mL of radioactive liquids in a shielded configuration, with no more than an A2 quantity in either configuration, over public highways and/or commercial aircraft. The contents are liquid radioactive materialsmore » sufficiently shielded and within the activity limits specified in173.435 or 173.433 for A2 (normal form) materials, as well as within the analyzed thermal heat limits. Any contents must be compatibly packaged and must be compatible with the packaging. The basic packaging design is based on the U.S. Department of Energy’s (DOE’s) Model 9979 Type A fissile shipping packaging designed and tested by SRNL. The shielded liquid configuration consists of the outer and inner drums of the 9979 package with additional low density polyethylene (LDPE) dunnage nesting a tungsten shielded cask assembly (WSCA) within the 30-gallon inner drum. The packaging model for the DOT Specification 7A, Type A liquids packaging is HVYTAL.« less