Science.gov

Sample records for radiation safety criteria

  1. Laser Safety Inspection Criteria

    SciTech Connect

    Barat, K

    2005-02-11

    A responsibility of the Laser Safety Officer (LSO) is to perform laser safety audits. The American National Standard Z136.1 Safe use of Lasers references this requirement in several sections: (1) Section 1.3.2 LSO Specific Responsibilities states under Hazard Evaluation, ''The LSO shall be responsible for hazards evaluation of laser work areas''; (2) Section 1.3.2.8, Safety Features Audits, ''The LSO shall ensure that the safety features of the laser installation facilities and laser equipment are audited periodically to assure proper operation''; and (3) Appendix D, under Survey and Inspections, it states, ''the LSO will survey by inspection, as considered necessary, all areas where laser equipment is used''. Therefore, for facilities using Class 3B and or Class 4 lasers, audits for laser safety compliance are expected to be conducted. The composition, frequency and rigueur of that inspection/audit rests in the hands of the LSO. A common practice for institutions is to develop laser audit checklists or survey forms. In many institutions, a sole Laser Safety Officer (LSO) or a number of Deputy LSO's perform these audits. For that matter, there are institutions that request users to perform a self-assessment audit. Many items on the common audit list and the associated findings are subjective because they are based on the experience and interest of the LSO or auditor in particular items on the checklist. Beam block usage is an example; to one set of eyes a particular arrangement might be completely adequate, while to another the installation may be inadequate. In order to provide more consistency, the National Ignition Facility Directorate at Lawrence Livermore National Laboratory (NIF-LLNL) has established criteria for a number of items found on the typical laser safety audit form. These criteria are distributed to laser users, and they serve two broad purposes: first, it gives the user an expectation of what will be reviewed by an auditor, and second, it is an

  2. Laser Safety Inspection Criteria

    SciTech Connect

    Barat, K

    2005-06-13

    A responsibility of the Laser Safety Officer (LSO) is to perform laser audits. The American National Standard Z136.1 Safe Use of Lasers references this requirement through several sections. One such reference is Section 1.3.2.8, Safety Features Audits, ''The LSO shall ensure that the safety features of the laser installation facilities and laser equipment are audited periodically to assure proper operation''. The composition, frequency and rigor of that inspection/audit rests in the hands of the LSO. A common practice for institutions is to develop laser audit checklists or survey forms It is common for audit findings from one inspector or inspection to the next to vary even when reviewing the same material. How often has one heard a comment, ''well this area has been inspected several times over the years and no one ever said this or that was a problem before''. A great number of audit items, and therefore findings, are subjective because they are based on the experience and interest of the auditor to particular items on the checklist. Beam block usage, to one set of eyes might be completely adequate, while to another, inadequate. In order to provide consistency, the Laser Safety Office of the National Ignition Facility Directorate has established criteria for a number of items found on the typical laser safety audit form. The criteria are distributed to laser users. It serves two broad purposes; first, it gives the user an expectation of what will be reviewed by an auditor. Second, it is an opportunity to explain audit items to the laser user and thus the reasons for some of these items, such as labelling of beam blocks.

  3. Aerostructural safety factor criteria

    NASA Technical Reports Server (NTRS)

    Verderaime, V.

    1992-01-01

    The present modification of the conventional safety factor method for aircraft structures evaluation involves the expression of deterministic safety factors in probabilistic tolerance limit ratios; these are found to involve a total of three factors that control the interference of applied and resistive stress distributions. The deterministic expression is extended so that it may furnish a 'relative ultimate safety' index that encompasses all three distribution factors. Operational reliability is developed on the basis of the applied and the yield stress distribution interferences. Industry standards are suggested to be derivable from factor selections that are based on the consequences of failure.

  4. Radiation Safety Compliance.

    PubMed

    Koth, Jana; Smith, Marcia Hess

    2016-05-01

    This article discusses radiation safety programs, including the members of the radiation safety team, their roles, and the challenges they face, with a focus on the radiation safety officer's duties. Agencies that regulate radiation safety also are described. The importance of minimizing patient dose, ensuring that dosimetry badges are worn correctly, and using therapeutic radioactive materials safely are addressed. Finally, radiologic technologists' role in using radiation safely is discussed, and the principles of time, distance, and shielding are reviewed. PMID:27146175

  5. Ferrocyanide Safety Program: Safety criteria for ferrocyanide watch list tanks

    SciTech Connect

    Postma, A.K.; Meacham, J.E.; Barney, G.S.

    1994-01-01

    This report provides a technical basis for closing the ferrocyanide Unreviewed Safety Question (USQ) at the Hanford Site. Three work efforts were performed in developing this technical basis. The efforts described herein are: 1. The formulation of criteria for ranking the relative safety of waste in each ferrocyanide tank. 2. The current classification of tanks into safety categories by comparing available information on tank contents with the safety criteria; 3. The identification of additional information required to resolve the ferrocyanide safety issue.

  6. Discussions about safety criteria and guidelines for radioactive waste management.

    PubMed

    Yamamoto, Masafumi

    2011-07-01

    In Japan, the clearance levels for uranium-bearing waste have been established by the Nuclear Safety Commission (NSC). The criteria for uranium-bearing waste disposal are also necessary; however, the NSC has not concluded the discussion on this subject. Meanwhile, the General Administrative Group of the Radiation Council has concluded the revision of its former recommendation 'Regulatory exemption dose for radioactive solid waste disposal', the dose criteria after the institutional control period for a repository. The Standardization Committee on Radiation Protection in the Japan Health Physics Society (The Committee) also has developed the relevant safety criteria and guidelines for existing exposure situations, which are potentially applicable to uranium-bearing waste disposal. A new working group established by The Committee was initially aimed at developing criteria and guidelines specifically for uranium-bearing waste disposal; however, the aim has been shifted to broader criteria applicable to any radioactive wastes. PMID:21531746

  7. Radiation design criteria handbook. [design criteria for electronic parts applications

    NASA Technical Reports Server (NTRS)

    Stanley, A. G.; Martin, K. E.; Douglas, S.

    1976-01-01

    Radiation design criteria for electronic parts applications in space environments are provided. The data were compiled from the Mariner/Jupiter Saturn 1977 electronic parts radiation test program. Radiation sensitive device types were exposed to radiation environments compatible with the MJS'77 requirements under suitable bias conditions. A total of 189 integrated circuits, transistors, and other semiconductor device types were tested.

  8. Radiation Safety System

    SciTech Connect

    Vylet, Vaclav; Liu, James C.; Walker, Lawrence S.; /Los Alamos

    2012-04-04

    The goal of this work is to provide an overview of a Radiation safety system (RSS) designed for protection from prompt radiation hazard at accelerator facilities. RSS design parameters, functional requirements and constraints are derived from hazard analysis and risk assessment undertaken in the design phase of the facility. The two main subsystems of a RSS are access control system (ACS) and radiation control system (RCS). In this text, a common approach to risk assessment, typical components of ACS and RCS, desirable features and general design principles applied to RSS are described.

  9. Nuclear safety criteria and specifications for space nuclear reactors

    SciTech Connect

    Not Available

    1982-08-01

    The purpose of this document is to define safety criteria which must be met to implement US safety policy for space fission reactors. These criteria provide the bases for decisions on the acceptability of specific mission and reactor design proposals. (JDH)

  10. 10 CFR 32.23 - Same: Safety criteria.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 1 2014-01-01 2014-01-01 false Same: Safety criteria. 32.23 Section 32.23 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES TO MANUFACTURE OR TRANSFER CERTAIN ITEMS CONTAINING BYPRODUCT MATERIAL Exempt Concentrations and Items § 32.23 Same: Safety criteria. An applicant for a...

  11. 10 CFR 32.27 - Same: Safety criteria.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 1 2013-01-01 2013-01-01 false Same: Safety criteria. 32.27 Section 32.27 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES TO MANUFACTURE OR TRANSFER CERTAIN ITEMS CONTAINING BYPRODUCT MATERIAL Exempt Concentrations and Items § 32.27 Same: Safety criteria. An applicant for a...

  12. 10 CFR 32.27 - Same: Safety criteria.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 1 2012-01-01 2012-01-01 false Same: Safety criteria. 32.27 Section 32.27 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES TO MANUFACTURE OR TRANSFER CERTAIN ITEMS CONTAINING BYPRODUCT MATERIAL Exempt Concentrations and Items § 32.27 Same: Safety criteria. An applicant for a...

  13. 10 CFR 32.27 - Same: Safety criteria.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 1 2014-01-01 2014-01-01 false Same: Safety criteria. 32.27 Section 32.27 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES TO MANUFACTURE OR TRANSFER CERTAIN ITEMS CONTAINING BYPRODUCT MATERIAL Exempt Concentrations and Items § 32.27 Same: Safety criteria. An applicant for a...

  14. 10 CFR 32.23 - Same: Safety criteria.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 1 2013-01-01 2013-01-01 false Same: Safety criteria. 32.23 Section 32.23 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES TO MANUFACTURE OR TRANSFER CERTAIN ITEMS CONTAINING BYPRODUCT MATERIAL Exempt Concentrations and Items § 32.23 Same: Safety criteria. An applicant for a...

  15. 10 CFR 32.23 - Same: Safety criteria.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 1 2012-01-01 2012-01-01 false Same: Safety criteria. 32.23 Section 32.23 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES TO MANUFACTURE OR TRANSFER CERTAIN ITEMS CONTAINING BYPRODUCT MATERIAL Exempt Concentrations and Items § 32.23 Same: Safety criteria. An applicant for a...

  16. 10 CFR 32.27 - Same: Safety criteria.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false Same: Safety criteria. 32.27 Section 32.27 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES TO MANUFACTURE OR TRANSFER CERTAIN ITEMS CONTAINING BYPRODUCT MATERIAL Exempt Concentrations and Items § 32.27 Same: Safety criteria. An applicant for a...

  17. 10 CFR 32.23 - Same: Safety criteria.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Same: Safety criteria. 32.23 Section 32.23 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES TO MANUFACTURE OR TRANSFER CERTAIN ITEMS CONTAINING BYPRODUCT MATERIAL Exempt Concentrations and Items § 32.23 Same: Safety criteria. An applicant for a...

  18. 10 CFR 32.27 - Same: Safety criteria.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Same: Safety criteria. 32.27 Section 32.27 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES TO MANUFACTURE OR TRANSFER CERTAIN ITEMS CONTAINING BYPRODUCT MATERIAL Exempt Concentrations and Items § 32.27 Same: Safety criteria. An applicant for a...

  19. 10 CFR 32.23 - Same: Safety criteria.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false Same: Safety criteria. 32.23 Section 32.23 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES TO MANUFACTURE OR TRANSFER CERTAIN ITEMS CONTAINING BYPRODUCT MATERIAL Exempt Concentrations and Items § 32.23 Same: Safety criteria. An applicant for a...

  20. Safety goals and functional performance criteria. [Advanced Reactor Design

    SciTech Connect

    Youngblood, R.W.; Pratt, W.T. ); Hardin, W.B. . Div. of Regulatory Applications)

    1990-01-01

    This report discusses a possible approach to the development of functional performance criteria to be applied to evolutionary LWR designs. Key safety functions are first identified; then, criteria are drawn up for each individual function, based on the premise that no single function's projected unreliability should be allowed to exhaust the safety goal frequencies. In the area of core damage prevention, functional criteria are cast in terms of necessary levels of redundancy and diversity of critical equipment. In the area of core damage mitigation (containment), functional performance criteria are cast with the aim of mitigating post-core-melt phenomena with sufficient assurance to eliminate major uncertainties in containment performance. 9 refs.

  1. Licensed reactor nuclear safety criteria applicable to DOE reactors

    SciTech Connect

    Not Available

    1993-11-01

    This document is a compilation and source list of nuclear safety criteria that the Nuclear Regulatory Commission (NRC) applies to licensed reactors; it can be used by DOE and DOE contractors to identify NRC criteria to be evaluated for application to the DOE reactors under their cognizance. The criteria listed are those that are applied to the areas of nuclear safety addressed in the safety analysis report of a licensed reactor. They are derived from federal regulations, USNRC regulatory guides, Standard Review Plan (SRP) branch technical positions and appendices, and industry codes and standards.

  2. Radiation Safety in Pediatric Orthopaedics.

    PubMed

    Caird, Michelle S

    2015-01-01

    Patients, surgeons, and staff are exposed to ionizing radiation in pediatric orthopaedic surgery from diagnostic studies and imaging associated with procedures. Estimating radiation dose to pediatric patients is based on complex algorithms and dose to surgeons and staff is based on dosimeter monitoring. Surgeons can decrease radiation exposure to patients with careful and thoughtful ordering of diagnostic studies and by minimizing exposure intraoperatively. Surgeon and staff radiation exposure can be minimized with educational programs, proper shielding and positioning intraoperatively, and prudent use of intraoperative imaging. Overall, better awareness among pediatric orthopaedic surgeons of our role in radiation exposure can lead to improvements in radiation safety. PMID:26049299

  3. Nuclear-safety criteria and specifications for space nuclear reactors

    SciTech Connect

    Not Available

    1982-08-01

    The policy of the United States for all US nuclear power sources in space is to ensure that the probability of release of radioactive material and the amounts released are such that an undue risk is not presented, considering the benefits of the mission. The objective of this document is to provide safety criteria which a mission/reactor designer can use to help ensure that the design is acceptable from a radiological safety standpoint. These criteria encompass mission design, reactor design, and radiological impact limitation requirements for safety, and the documentation required. They do not address terrestrial operations, occupational safety or system reliability except where the systems are important for radiological safety. Specific safety specifications based on these criteria shall also be generated and made part of contractual requirements.

  4. 76 FR 20070 - Commercial Space Transportation Safety Approval Performance Criteria

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-04-11

    ... Federal Aviation Administration Commercial Space Transportation Safety Approval Performance Criteria... received, a safety approval for the ability of its Space Training System: Model 400 (STS-400) to replicate....19 (a)(4). NASTAR's ] STS-400 suborbital space flight simulator (a multi-axis centrifuge) is...

  5. Explosive safety criteria at a Department of Energy contractor facility

    NASA Astrophysics Data System (ADS)

    Krach, F.

    1984-08-01

    Monsanto Research Corporation (MRC) operates the Mound facility in Miamisburg, Ohio, for the Department of Energy. Small explosive components are manufactured at MRC, and stringent explosive safety criteria have been developed for their manufacturing. The goals of these standards are to reduce employee injuries and eliminate fenceline impacts resulting from accidental detonations. The manner in which these criteria were developed and what DOD standards were incorporated into MRC's own design criteria are described. These design requirements are applicable to all new construction at MRC. An example of the development of the design of a Component Test Facility is presented to illustrate the application of the criteria.

  6. Licensed reactor nuclear safety criteria applicable to DOE reactors

    SciTech Connect

    Not Available

    1991-04-01

    The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC (Nuclear Regulatory Commission) licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor.

  7. Risk-based versus deterministic explosives safety criteria

    SciTech Connect

    Wright, R.E.

    1996-12-01

    The Department of Defense Explosives Safety Board (DDESB) is actively considering ways to apply risk-based approaches in its decision- making processes. As such, an understanding of the impact of converting to risk-based criteria is required. The objectives of this project are to examine the benefits and drawbacks of risk-based criteria and to define the impact of converting from deterministic to risk-based criteria. Conclusions will be couched in terms that allow meaningful comparisons of deterministic and risk-based approaches. To this end, direct comparisons of the consequences and impacts of both deterministic and risk-based criteria at selected military installations are made. Deterministic criteria used in this report are those in DoD 6055.9-STD, `DoD Ammunition and Explosives Safety Standard.` Risk-based criteria selected for comparison are those used by the government of Switzerland, `Technical Requirements for the Storage of Ammunition (TLM 75).` The risk-based criteria used in Switzerland were selected because they have been successfully applied for over twenty-five years.

  8. 10 CFR 72.124 - Criteria for nuclear criticality safety.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Criteria for nuclear criticality safety. 72.124 Section 72.124 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...

  9. 10 CFR 72.124 - Criteria for nuclear criticality safety.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Criteria for nuclear criticality safety. 72.124 Section 72.124 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...

  10. 10 CFR 72.124 - Criteria for nuclear criticality safety.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Criteria for nuclear criticality safety. 72.124 Section 72.124 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...

  11. 10 CFR 72.124 - Criteria for nuclear criticality safety.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Criteria for nuclear criticality safety. 72.124 Section 72.124 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...

  12. 10 CFR 72.124 - Criteria for nuclear criticality safety.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Criteria for nuclear criticality safety. 72.124 Section 72.124 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...

  13. PWR-2 Blanket Fuel Assembly Removal Safety Basis Criteria Document

    SciTech Connect

    BUSHORE, R.P.

    2001-01-22

    This criteria document describes the proposed format, content, and schedule for the preparation of an amendment to the Interim Safety Basis for Solid Waste Facilities (T Plant) (ISB), (HNF-SD-WM-ISB-006), and to the T Plant Interim Operational Safety Requirements (IOSR) (''F-SD-WM-TSR-003). The amendments to these documents are intended to authorize removal of spent nuclear fuel (SNF) assemblies from the spent fuel pool in the Solid Waste Treatment Facility 221-T canyon for interim storage in the Canister Storage Building (CSB). The amendments will include a stand-alone safety assessment as well as revisions to these safety documents as needed to reflect the changes in work scope not currently authorized to accomplish the expected end-state of the Fuel Removal Project for the 221-T Facility.

  14. Safety-related operator actions: methodology for developing criteria

    SciTech Connect

    Kozinsky, E.J.; Gray, L.H.; Beare, A.N.; Barks, D.B.; Gomer, F.E.

    1984-03-01

    This report presents a methodology for developing criteria for design evaluation of safety-related actions by nuclear power plant reactor operators, and identifies a supporting data base. It is the eleventh and final NUREG/CR Report on the Safety-Related Operator Actions Program, conducted by Oak Ridge National Laboratory for the US Nuclear Regulatory Commission. The operator performance data were developed from training simulator experiments involving operator responses to simulated scenarios of plant disturbances; from field data on events with similar scenarios; and from task analytic data. A conceptual model to integrate the data was developed and a computer simulation of the model was run, using the SAINT modeling language. Proposed is a quantitative predictive model of operator performance, the Operator Personnel Performance Simulation (OPPS) Model, driven by task requirements, information presentation, and system dynamics. The model output, a probability distribution of predicted time to correctly complete safety-related operator actions, provides data for objective evaluation of quantitative design criteria.

  15. Safety analysis, risk assessment, and risk acceptance criteria

    SciTech Connect

    Jamali, K.; Stack, D.W.; Sullivan, L.H.; Sanzo, D.L.

    1997-08-01

    This paper discusses a number of topics that relate safety analysis as documented in the Department of Energy (DOE) safety analysis reports (SARs), probabilistic risk assessments (PRA) as characterized primarily in the context of the techniques that have assumed some level of formality in commercial nuclear power plant applications, and risk acceptance criteria as an outgrowth of PRA applications. DOE SARs of interest are those that are prepared for DOE facilities under DOE Order 5480.23 and the implementing guidance in DOE STD-3009-94. It must be noted that the primary area of application for DOE STD-3009 is existing DOE facilities and that certain modifications of the STD-3009 approach are necessary in SARs for new facilities. Moreover, it is the hazard analysis (HA) and accident analysis (AA) portions of these SARs that are relevant to the present discussions. Although PRAs can be qualitative in nature, PRA as used in this paper refers more generally to all quantitative risk assessments and their underlying methods. HA as used in this paper refers more generally to all qualitative risk assessments and their underlying methods that have been in use in hazardous facilities other than nuclear power plants. This discussion includes both quantitative and qualitative risk assessment methods. PRA has been used, improved, developed, and refined since the Reactor Safety Study (WASH-1400) was published in 1975 by the Nuclear Regulatory Commission (NRC). Much debate has ensued since WASH-1400 on exactly what the role of PRA should be in plant design, reactor licensing, `ensuring` plant and process safety, and a large number of other decisions that must be made for potentially hazardous activities. Of particular interest in this area is whether the risks quantified using PRA should be compared with numerical risk acceptance criteria (RACs) to determine whether a facility is `safe.` Use of RACs requires quantitative estimates of consequence frequency and magnitude.

  16. Occupational safety and health criteria for responsible development of nanotechnology.

    PubMed

    Schulte, P A; Geraci, C L; Murashov, V; Kuempel, E D; Zumwalde, R D; Castranova, V; Hoover, M D; Hodson, L; Martinez, K F

    2014-01-01

    Organizations around the world have called for the responsible development of nanotechnology. The goals of this approach are to emphasize the importance of considering and controlling the potential adverse impacts of nanotechnology in order to develop its capabilities and benefits. A primary area of concern is the potential adverse impact on workers, since they are the first people in society who are exposed to the potential hazards of nanotechnology. Occupational safety and health criteria for defining what constitutes responsible development of nanotechnology are needed. This article presents five criterion actions that should be practiced by decision-makers at the business and societal levels-if nanotechnology is to be developed responsibly. These include (1) anticipate, identify, and track potentially hazardous nanomaterials in the workplace; (2) assess workers' exposures to nanomaterials; (3) assess and communicate hazards and risks to workers; (4) manage occupational safety and health risks; and (5) foster the safe development of nanotechnology and realization of its societal and commercial benefits. All these criteria are necessary for responsible development to occur. Since it is early in the commercialization of nanotechnology, there are still many unknowns and concerns about nanomaterials. Therefore, it is prudent to treat them as potentially hazardous until sufficient toxicology, and exposure data are gathered for nanomaterial-specific hazard and risk assessments. In this emergent period, it is necessary to be clear about the extent of uncertainty and the need for prudent actions. PMID:24482607

  17. Health, safety and environmental criteria for siting of laboratory facilities.

    PubMed

    Lees, P S; Corn, M

    1983-04-01

    The development of applicable criteria for assessing the suitability of a site for construction of full and partial containment laboratories for the analysis of unknown and highly toxic chemicals is described. The criteria, based on considerations of health, safety and environmental factors, are used to define critical considerations in site selection to minimize the risk to non-laboratory personnel and the surrounding environment. Criteria are synthesized from several sources using the assumption of a worst-case chemical release. Mechanical failures, human failures, critical events and social/legal limitations are investigated, as are the characteristics of a site which may limit construction of such a facility. A detailed description is made of the various types of laboratories and the types of samples analyzed in them. The final recommendations are summarized for five typical laboratory settings; they are based primarily on the potential impacts on people, property and natural resources. A single occupancy building in a rural setting is recommended as the most suitable site for a full containment laboratory. A single occupancy building in an industrial park setting is acceptable, while multiple occupancy buildings and sites which are more highly developed are unacceptable. Similar recommendations are made for partial containment and conventional laboratories. PMID:6858856

  18. Application of the Supreme Court's Daubert criteria in radiation litigation.

    PubMed

    Merwin, S E; Moeller, D W; Kennedy, W E; Moeller, M P

    2001-12-01

    In 1993, the U.S. Supreme Court set forth the standard for determining the admissibility of expert scientific evidence in litigation. This standard is known as the Daubert criteria, named after the pertinent case, Daubert v. Merrell Dow Pharmaceuticals, Inc. The Daubert criteria require the courts to determine whether an expert's testimony reflects scientific knowledge, whether his/her findings are derived by the scientific method, and whether the work product is based on good science. The Daubert criteria are especially important in radiation litigation because issues involving radiation doses and effects are often complex and thus a jury will typically rely heavily on the analysis and opinions of experts. According to the Daubert criteria, scientific opinions must be based on a methodology that has a valid, testable hypothesis; has been subject to peer review; and is generally accepted in the scientific community. Additionally, the expert must be qualified to present opinions based on the methodology. Although the application of the Daubert criteria in radiation litigation is highly dependent on the specific court and judge presiding over the case, there have been recent high-profile cases in which application of the criteria has resulted in the dismissal of analysis and opinions offered by scientific experts. Reasons for the dismissals have included basic scientific errors such as failure of the expert to consider all possible explanations for an observed phenomenon, the selective use of data by the expert, and the failure to acknowledge and resolve inconsistencies between the expert's results and those of other investigators. This paper reviews the Daubert criteria as they apply to radiation litigation and provides examples of the application of the criteria from recent judgments involving the Three Mile Island and Hanford Downwinders cases. PMID:11725885

  19. 21 CFR 70.42 - Criteria for evaluating the safety of color additives.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 21 Food and Drugs 1 2010-04-01 2010-04-01 false Criteria for evaluating the safety of color additives. 70.42 Section 70.42 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL COLOR ADDITIVES Safety Evaluation § 70.42 Criteria for evaluating the safety of...

  20. 10 CFR 835.901 - Radiation safety training.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 4 2013-01-01 2013-01-01 false Radiation safety training. 835.901 Section 835.901 Energy DEPARTMENT OF ENERGY OCCUPATIONAL RADIATION PROTECTION Radiation Safety Training § 835.901 Radiation safety training. (a) Each individual shall complete radiation safety training on the topics established at §...

  1. 10 CFR 835.901 - Radiation safety training.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 4 2014-01-01 2014-01-01 false Radiation safety training. 835.901 Section 835.901 Energy DEPARTMENT OF ENERGY OCCUPATIONAL RADIATION PROTECTION Radiation Safety Training § 835.901 Radiation safety training. (a) Each individual shall complete radiation safety training on the topics established at §...

  2. 10 CFR 835.901 - Radiation safety training.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 4 2011-01-01 2011-01-01 false Radiation safety training. 835.901 Section 835.901 Energy DEPARTMENT OF ENERGY OCCUPATIONAL RADIATION PROTECTION Radiation Safety Training § 835.901 Radiation safety training. (a) Each individual shall complete radiation safety training on the topics established at §...

  3. 10 CFR 835.901 - Radiation safety training.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 4 2010-01-01 2010-01-01 false Radiation safety training. 835.901 Section 835.901 Energy DEPARTMENT OF ENERGY OCCUPATIONAL RADIATION PROTECTION Radiation Safety Training § 835.901 Radiation safety training. (a) Each individual shall complete radiation safety training on the topics established at § 835.901(c) commensurate with the...

  4. 10 CFR 835.901 - Radiation safety training.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 4 2012-01-01 2012-01-01 false Radiation safety training. 835.901 Section 835.901 Energy DEPARTMENT OF ENERGY OCCUPATIONAL RADIATION PROTECTION Radiation Safety Training § 835.901 Radiation safety training. (a) Each individual shall complete radiation safety training on the topics established at §...

  5. Radiation safety for anesthesia providers.

    PubMed

    Phillips, Gillian; Monaghan, W Patrick

    2011-06-01

    Many modern diagnostic and surgical procedures rely heavily on the use of ionizing radiation. These procedures include computed tomography, nuclear medicine procedures, interventional radiology, and cardiac catheterization and electrophysiology procedures. Recent trends toward increased patient visits and patients with multiple challenging comorbidities have meant that anesthesia providers are increasingly required to provide services in the ancillary areas using ionizing radiation. As a result, anesthesia providers are at a greater-than-ever risk for excessive radiation doses. An overview of some of the basic principles of radiation biology, radiation physics, and radiation protection and specific guidelines related to radiation exposure and pregnancy are described. The effects of radiation exposure are cumulative and permanent, and an understanding of these principles and practices will help anesthesia providers keep their occupational exposure to a minimum. PMID:21751695

  6. Industrial irradiator radiation safety program assessments

    NASA Astrophysics Data System (ADS)

    Smith, Mark A.

    2000-03-01

    Considerable attention is typically given to radiation safety in the design of irradiators and initially establishing the program. However, one component that may not receive enough attention is applying the continuous improvement philosophy to the radiation safety program. Periodic total program assessments of radiation safety can ensure that the design and implementation of the program continues to be applicable to the operations. The first step in the process must be to determine what is to be covered in the program assessment. While regulatory compliance audits are a component, the most useful evaluation will extend beyond looking only at compliance and determine whether the radiation safety program is the most appropriate for the particular operation. Several aspects of the irradiator operation, not all of which may routinely be considered "radiation safety", per se, should be included: Design aspects of the irradiator and operating system, system controls, and maintenance procedures, as well as the more traditional radiation safety program components such as surveys, measurements and training.

  7. 49 CFR Appendix A to Part 385 - Explanation of Safety Audit Evaluation Criteria

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 5 2011-10-01 2011-10-01 false Explanation of Safety Audit Evaluation Criteria A Appendix A to Part 385 Transportation Other Regulations Relating to Transportation (Continued) FEDERAL MOTOR CARRIER SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION FEDERAL MOTOR CARRIER SAFETY REGULATIONS SAFETY FITNESS PROCEDURES Pt. 385,...

  8. 10 CFR 32.31 - Certain industrial devices containing byproduct material: Safety criteria.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 1 2014-01-01 2014-01-01 false Certain industrial devices containing byproduct material: Safety criteria. 32.31 Section 32.31 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES TO... Certain industrial devices containing byproduct material: Safety criteria. (a) An applicant for a...

  9. 10 CFR 32.31 - Certain industrial devices containing byproduct material: Safety criteria.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 1 2013-01-01 2013-01-01 false Certain industrial devices containing byproduct material: Safety criteria. 32.31 Section 32.31 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES TO... Certain industrial devices containing byproduct material: Safety criteria. (a) An applicant for a...

  10. Radiation Safety Considerations for LHD Experiments

    NASA Astrophysics Data System (ADS)

    Uda, T.; Yamanishi, H.; Miyake, H.; Kodaira, J.; Sakuma, Y.; Hirabayashi, H.; Obayashi, H.; Yamada, H.; Motojima, O.

    1997-06-01

    For experiments with the Large Helical Device (LHD) which is now under construction at the Toki site in Japan, radiation safety issues were discussed. In the course of plasma experiments, radiations such as X-rays, induced γ-rays, and neutrons increase. From a safety point of view, these radiation exposures to the environment should be controlled to limit the annual dose to less than 50 μSv at the site boundary. In order to meet this, an area monitoring system named RMSAFE (Radiation Monitoring System Applicable to Fusion Experiments) has been developed and partly installed. This can discriminate and measure radiations including burst-like emissions due to plasma shots from natural radiations. For the present period, this system is operating to monitor the natural radiation levels before the LHD operation. It was observed that the radiation levels strongly depend on rain levels and ground state. An indoor area monitoring system has already been implemented on site, to measure radiations from NBI and ECH test shots, and it shows good monitoring ability. Also, thermoluminescence dosimetry has been applied. The importance of investigating the radiological behavior under natural conditions with continuous monitoring is shown.

  11. Radiation safety content guide for safety analysis reports

    SciTech Connect

    Not Available

    1989-08-01

    US Department of Energy-Savannah River Operations Office (DOE-SR) facilities develop Safety Analysis Reports (SARs) to permit evaluation of potential hazards to the health and safety of the public and employees and potential hazards to government property and the environment. The SAR is the primary vehicle by which the Operating Contractor provides information to demonstrate that the facility can be operated safely. The Savannah River Operations Office independently reviews SARs to determine their technical integrity and completeness. In order to make the review process most efficient, SARs must be prepared in a consistent manner and contain all required information. This document provides guidance on the content of the radiation safety information to be included in SARs. It is not within the scope of this guide to address the entire Safety Analysis Report. 53 refs.

  12. Lunar lava tube radiation safety analysis.

    PubMed

    De Angelis, Giovanni; Wilson, J W; Clowdsley, M S; Nealy, J E; Humes, D H; Clem, J M

    2002-12-01

    For many years it has been suggested that lava tubes on the Moon could provide an ideal location for a manned lunar base, by providing shelter from various natural hazards, such as cosmic radiation, meteorites, micrometeoroids, and impact crater ejecta, and also providing a natural environmental control, with a nearly constant temperature, unlike that of the lunar surface showing extreme variation in its diurnal cycle. An analysis of radiation safety issues on lunar lava tubes has been performed by considering radiation from galactic cosmic rays (GCR) and Solar Particle Events (SPE) interacting with the lunar surface, modeled as a regolith layer and rock. The chemical composition has been chosen as typical of the lunar regions where the largest number of lava tube candidates are found. Particles have been transported all through the regolith and the rock, and received particles flux and doses have been calculated. The radiation safety of lunar lava tubes environments has been demonstrated. PMID:12793728

  13. Lunar lava tube radiation safety analysis

    NASA Technical Reports Server (NTRS)

    De Angelis, Giovanni; Wilson, J. W.; Clowdsley, M. S.; Nealy, J. E.; Humes, D. H.; Clem, J. M.

    2002-01-01

    For many years it has been suggested that lava tubes on the Moon could provide an ideal location for a manned lunar base, by providing shelter from various natural hazards, such as cosmic radiation, meteorites, micrometeoroids, and impact crater ejecta, and also providing a natural environmental control, with a nearly constant temperature, unlike that of the lunar surface showing extreme variation in its diurnal cycle. An analysis of radiation safety issues on lunar lava tubes has been performed by considering radiation from galactic cosmic rays (GCR) and Solar Particle Events (SPE) interacting with the lunar surface, modeled as a regolith layer and rock. The chemical composition has been chosen as typical of the lunar regions where the largest number of lava tube candidates are found. Particles have been transported all through the regolith and the rock, and received particles flux and doses have been calculated. The radiation safety of lunar lava tubes environments has been demonstrated.

  14. Radiation Safety Systems for Accelerator Facilities

    SciTech Connect

    Liu, James C

    2001-10-17

    The Radiation Safety System (RSS) of an accelerator facility is used to protect people from prompt radiation hazards associated with accelerator operation. The RSS is a fully interlocked, engineered system with a combination of passive and active elements that are reliable, redundant, and fail-safe. The RSS consists of the Access Control System (ACS) and the Radiation Containment System (RCS). The ACS is to keep people away from the dangerous radiation inside the shielding enclosure. The RCS limits and contains the beam/radiation conditions to protect people from the prompt radiation hazards outside the shielding enclosure in both normal and abnormal operations. The complexity of a RSS depends on the accelerator and its operation, as well as associated hazard conditions. The approaches of RSS among different facilities can be different. This report gives a review of the RSS for accelerator facilities.

  15. Radiation Safety Systems for Accelerator Facilities

    SciTech Connect

    James C. Liu; Jeffrey S. Bull; John Drozdoff; Robert May; Vaclav Vylet

    2001-10-01

    The Radiation Safety System (RSS) of an accelerator facility is used to protect people from prompt radiation hazards associated with accelerator operation. The RSS is a fully interlocked, engineered system with a combination of passive and active elements that are reliable, redundant, and fail-safe. The RSS consists of the Access Control System (ACS) and the Radiation Containment System (RCS). The ACS is to keep people away from the dangerous radiation inside the shielding enclosure. The RCS limits and contains the beam/radiation conditions to protect people from the prompt radiation hazards outside the shielding enclosure in both normal and abnormal operations. The complexity of a RSS depends on the accelerator and its operation, as well as associated hazard conditions. The approaches of RSS among different facilities can be different. This report gives a review of the RSS for accelerator facilities.

  16. Photovoltaic system criteria documents. Volume 5: Safety criteria for photovoltaic applications

    NASA Technical Reports Server (NTRS)

    Koenig, John C.; Billitti, Joseph W.; Tallon, John M.

    1979-01-01

    Methodology is described for determining potential safety hazards involved in the construction and operation of photovoltaic power systems and provides guidelines for the implementation of safety considerations in the specification, design and operation of photovoltaic systems. Safety verification procedures for use in solar photovoltaic systems are established.

  17. Radiation Safety System for Stanford Synchrotron Radiation Laboratory

    SciTech Connect

    Liu, J

    2004-03-12

    Radiation Safety System (RSS) at the Stanford Synchrotron Radiation Laboratory is summarized and reviewed. The RSS, which is designed to protect people from prompt radiation hazards from accelerator operation, consists of the Access Control System (ACS) and the Beam Containment System (BCS). The ACS prevents people from being exposed to the lethal radiation level inside the shielding housing (called a PPS area at SLAC). The ACS for a PPS area consists of the shielding housing, beam inhibiting devices, and a standard entry module at each entrance. The BCS protects people from the prompt radiation hazards outside a PPS area under both normal and abnormal beam loss situations. The BCS consists of the active power (current/energy) limiting devices, beam stoppers, shielding, and an active radiation monitor system. The policies and practices in setting up the RSS at SLAC are illustrated.

  18. Radiation safety in fluoroscopy for neuraxial injections.

    PubMed

    Fink, Gerry E

    2009-08-01

    Certified Registered Nurse Anesthetists (CRNAs) perform epidural steroid injections for chronic back and extremity pain. Placing epidural needles using fluoroscopy and confirming the needle placement by epidurogram has been suggested as a means to increase the efficacy of epidural injections while decreasing complications. Because of the risk of radiation injury to patients and staff when using fluoroscopy, the purpose of this article is to review the concepts of fluoroscopy and radiation safety for CRNAs. Following a literature search using keywords such as fluoroscopy, radiation injury, and radiation safety, relevant articles were identified. In addition, the reference lists of these articles were reviewed to identify other pertinent sources regarding this topic. The risks of stochastic and deterministic effects from radiation exposure necessitate the need for practitioners who are knowledgeable in equipment, patient, and procedure related factors that influence radiation exposure. Practitioner conduct, using the as-low-as-reasonably achievable (ALARA) principle, results in choices regarding these factors that minimize the time and intensity of radiation exposure to patients, anesthesia providers, and staff. PMID:19731844

  19. 32 CFR 636.33 - Vehicle safety inspection criteria.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... above the vehicle manufacturer's designated height (49 CFR 570.8). (b) The criteria listed in paragraph... starburst or spider webbing effect greater than 3 inches by 3 inches. No opaque or solid material...

  20. 32 CFR 636.33 - Vehicle safety inspection criteria.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... above the vehicle manufacturer's designated height (49 CFR 570.8). (b) The criteria listed in paragraph... starburst or spider webbing effect greater than 3 inches by 3 inches. No opaque or solid material...

  1. 32 CFR 636.33 - Vehicle safety inspection criteria.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... above the vehicle manufacturer's designated height (49 CFR 570.8). (b) The criteria listed in paragraph... starburst or spider webbing effect greater than 3 inches by 3 inches. No opaque or solid material...

  2. 32 CFR 636.33 - Vehicle safety inspection criteria.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... above the vehicle manufacturer's designated height (49 CFR 570.8). (b) The criteria listed in paragraph... starburst or spider webbing effect greater than 3 inches by 3 inches. No opaque or solid material...

  3. 32 CFR 636.33 - Vehicle safety inspection criteria.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... above the vehicle manufacturer's designated height (49 CFR 570.8). (b) The criteria listed in paragraph... starburst or spider webbing effect greater than 3 inches by 3 inches. No opaque or solid material...

  4. Developing Criteria and Judgment of Safety for Crossing Streets with Gaps in Traffic.

    ERIC Educational Resources Information Center

    Sauerburger, Dona

    1999-01-01

    Discusses using the Timing Method for Assessing the Detection of Vehicles (TMAD) to help individuals with visual impairments develop the ability to judge their safety for crossing streets with no traffic control. Functional criteria for assessing risks are discussed. (CR)

  5. Structural deterministic safety factors selection criteria and verification

    NASA Technical Reports Server (NTRS)

    Verderaime, V.

    1992-01-01

    Though current deterministic safety factors are arbitrarily and unaccountably specified, its ratio is rooted in resistive and applied stress probability distributions. This study approached the deterministic method from a probabilistic concept leading to a more systematic and coherent philosophy and criterion for designing more uniform and reliable high-performance structures. The deterministic method was noted to consist of three safety factors: a standard deviation multiplier of the applied stress distribution; a K-factor for the A- or B-basis material ultimate stress; and the conventional safety factor to ensure that the applied stress does not operate in the inelastic zone of metallic materials. The conventional safety factor is specifically defined as the ratio of ultimate-to-yield stresses. A deterministic safety index of the combined safety factors was derived from which the corresponding reliability proved the deterministic method is not reliability sensitive. The bases for selecting safety factors are presented and verification requirements are discussed. The suggested deterministic approach is applicable to all NASA, DOD, and commercial high-performance structures under static stresses.

  6. HRIBF Tandem Accelerator Radiation Safety System Upgrade

    SciTech Connect

    Blankenship, J.L.; Juras, R.C.

    1998-11-04

    The HRIBF Tandem Accelerator Radiation Safety System was designed to permit experimenters and operations staff controlled access to beam transport and experiment areas with accelerated beam present. Neutron-Gamma detectors are mounted in eaeh area at points of maximum dose rate and the resulting signals are integrated by redundan~ circuitry; beam is stopped if dose rate or integrated dose exceeds established limits. This paper will describe the system, in use for several vears at the HRIBF, and discuss changes recently made to modernize the system and to make the system compliant with DOE Order 5480.25 and related ORNL updated safety rules.

  7. HRIBF Tandem Accelerator Radiation Safety System Upgrade

    NASA Astrophysics Data System (ADS)

    Juras, R. C.; Blankenship, J. L.

    1999-06-01

    The HRIBF Tandem Accelerator Radiation Safety System was designed to permit experimenters and operations staff controlled access to beam transport and experiment areas with accelerated beam present. Neutron-Gamma detectors are mounted in each area at points of maximum dose rate and the resulting signals are integrated by redundant circuitry; beam is stopped if dose rate or integrated dose exceeds established limits. This paper will describe the system, in use for several years at the HRIBF, and discuss changes recently made to modernize the system and to make the system compliant with DOE Order 5480.25 and related ORNL updated safety rules.

  8. Evaluation of proposed German safety criteria for high-temperature gas-cooled reactors

    SciTech Connect

    Barsell, A.W.

    1980-05-01

    This work reviews proposed safety criteria prepared by the German Bundesministerium des Innern (BMI) for future licensing of gas-cooled high-temperature reactor (HTR) concepts in the Federal Republic of Germany. Comparison is made with US General Design Criteria (GDCs) in 10CFR50 Appendix A and with German light water reactor (LWR) criteria. Implications for the HTR design relative to the US design and safety approach are indicated. Both inherent characteristics and design features of the steam cycle, gas turbine, and process heat concepts are taken into account as well as generic design options such as a pebble bed or prismatic core.

  9. 78 FR 64030 - Monitoring Criteria and Methods To Calculate Occupational Radiation Doses

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-10-25

    ... monitoring and calculating occupational radiation doses. On December 4, 2007 (72 FR 68043), the NRC revised... COMMISSION Monitoring Criteria and Methods To Calculate Occupational Radiation Doses AGENCY: Nuclear... Criteria and Methods to Calculate Occupational Radiation Doses.'' This guide describes methods that the...

  10. Updating of Safety Criteria for Basic Diagnostic Indicators of Dam at the Sayano-Shushenskaya HPP

    SciTech Connect

    Gordon, L. A.; Skvortsova, A. E.

    2013-09-15

    Values of diagnostic indicators [K]-limitations placed on radial displacements and turn angles of horizontal sections of the dam - which are permitted for each upper-pool level within the range from 520 to 539 m are determined and proposed for inclusion in the Declaration of Safety. Empirical relationships used to develop safety criteria K1 and K2 are modified.

  11. Radiation detectors for occupational safety measurements

    NASA Astrophysics Data System (ADS)

    Kaase, Heinrich; Chen, Mai; Grothmann, Knut

    1995-09-01

    The effective radiant exposures for artificial and natural UV-sources are determined by temporal integration over an 8 h working day. Therefore the spectrally weighted integration of the spectral irradiance from the radiation source in the plane of the exposure is to measure. Such measaurements are made with two different detector systems: measurements of UV radiation according to the integral method should be possible according to a quasi partial filtering method using different individually filtered photodiodes. A spectroradiometer for UV radiation analysis was tested due to its application in field measurements for meteorology, medicin, and occupational safety. The optical part of this compact instrument consists of a cosentrance optic, a monochromator and detector system. A comparison with commercial instruments is described.

  12. The dragon's tail: Radiation safety in the Manhattan Project

    SciTech Connect

    Hacker, B.C.

    1987-01-01

    The book's contents are: Introduction: radiation safety in World War II. Foundations of Manhattan Project radiation safety. Role of the Chicago Health Division. Radiation safety at Los Alamos, Trinity. From Japan to Bikini. Crossroads. Epilogue: continuity and change in radiation safety. Appendix: chronological index of radiation exposure standards. Index. The United States Department of Energy and the Energy Research and Development Administration financially supported this book which provides a historical account of radiological safety in nuclear weapons testing during World War II. The author relied on archival sources and the oral testimony of participants and eyewitnesses. He provides a bibliography with full citations.

  13. Performance Criteria and Evaluation System

    Energy Science and Technology Software Center (ESTSC)

    1992-06-18

    The Performance Criteria and Evaluation System (PCES) was developed in order to make a data base of criteria accessible to radiation safety staff. The criteria included in the package are applicable to occupational radiation safety at DOE reactor and nonreactor nuclear facilities, but any data base of criteria may be created using the Criterion Data Base Utiliity (CDU). PCES assists personnel in carrying out oversight, line, and support activities.

  14. Uncertainties in the effects of burnup and their impact on criticality safety licensing criteria

    SciTech Connect

    Carlson, R.W.; Fisher, L.E.

    1990-07-13

    Current criteria for criticality safety for spent fuel shipping and storage casks are conservative because no credit is permitted for the effects of burnup of the fuel inside the cask. Cask designs that will transport and store large numbers of fuel assemblies (20 or more) must devote a substantial part of their payload to criticality control measures if they are to meet this criteria. The Department of Energy is developing the data necessary to support safety analyses that incorporate the effects of burnup for the next generation of spent fuel shipping casks. The efforts described here are devoted to the development of acceptance criteria that will be the basis for accepting safety analyses. Preliminary estimates of the uncertainties of the effects of burnup have been developed to provide a basis for the consideration of critically safety criteria. The criticality safety margins in a spent fuel shipping or storage cask are dominated by the portions of a fuel assembly that are in low power regions of a reactor core, and the reactor operating conditions are very different from spent fuel storage or transport cask conditions. Consequently, the experience that has been gathered during years of reactor operation does not apply directly to the prediction of criticality safety margins for spent fuel shipping or storage casks. The preliminary estimates of the uncertainties presented in this paper must be refined by both analytical and empirical studies that address both the magnitude of the uncertainties and their interdependence. 9 refs., 5 figs.

  15. Radiation Safety System for SPIDER Neutral Beam Accelerator

    NASA Astrophysics Data System (ADS)

    Sandri, S.; Coniglio, A.; D'Arienzo, M.; Poggi, C.

    2011-12-01

    SPIDER (Source for Production of Ion of Deuterium Extracted from RF Plasma only) and MITICA (Megavolt ITER Injector Concept Advanced) are the ITER neutral beam injector (NBI) testing facilities of the PRIMA (Padova Research Injector Megavolt Accelerated) Center. Both injectors accelerate negative deuterium ions with a maximum energy of 1 MeV for MITICA and 100 keV for SPIDER with a maximum beam current of 40 A for both experiments. The SPIDER facility is classified in Italy as a particle accelerator. At present, the design of the radiation safety system for the facility has been completed and the relevant reports have been presented to the Italian regulatory authorities. Before SPIDER can operate, approval must be obtained from the Italian Regulatory Authority Board (IRAB) following a detailed licensing process. In the present work, the main project information and criteria for the SPIDER injector source are reported together with the analysis of hypothetical accidental situations and safety issues considerations. Neutron and photon nuclear analysis is presented, along with special shielding solutions designed to meet Italian regulatory dose limits. The contribution of activated corrosion products (ACP) to external exposure of workers has also been assessed. Nuclear analysis indicates that the photon contribution to worker external exposure is negligible, and the neutron dose can be considered by far the main radiation protection issue. Our results confirm that the injector has no important radiological impact on the population living around the facility.

  16. Radiation Safety System for SPIDER Neutral Beam Accelerator

    SciTech Connect

    Sandri, S.; Poggi, C.; Coniglio, A.; D'Arienzo, M.

    2011-12-13

    SPIDER (Source for Production of Ion of Deuterium Extracted from RF Plasma only) and MITICA (Megavolt ITER Injector Concept Advanced) are the ITER neutral beam injector (NBI) testing facilities of the PRIMA (Padova Research Injector Megavolt Accelerated) Center. Both injectors accelerate negative deuterium ions with a maximum energy of 1 MeV for MITICA and 100 keV for SPIDER with a maximum beam current of 40 A for both experiments. The SPIDER facility is classified in Italy as a particle accelerator. At present, the design of the radiation safety system for the facility has been completed and the relevant reports have been presented to the Italian regulatory authorities. Before SPIDER can operate, approval must be obtained from the Italian Regulatory Authority Board (IRAB) following a detailed licensing process. In the present work, the main project information and criteria for the SPIDER injector source are reported together with the analysis of hypothetical accidental situations and safety issues considerations. Neutron and photon nuclear analysis is presented, along with special shielding solutions designed to meet Italian regulatory dose limits. The contribution of activated corrosion products (ACP) to external exposure of workers has also been assessed. Nuclear analysis indicates that the photon contribution to worker external exposure is negligible, and the neutron dose can be considered by far the main radiation protection issue. Our results confirm that the injector has no important radiological impact on the population living around the facility.

  17. Temperature rise and safety considerations for radiation force ultrasound imaging

    NASA Astrophysics Data System (ADS)

    Herman, Bruce A.; Harris, Gerald R.

    2002-11-01

    Current models for estimating temperature increase during ultrasound exposure calculate the steady-state rise, using time-averaged acoustic output, as the worst case for safety consideration. While valid for the typically very short (microsecond) pulses used by conventional diagnostic techniques, this analysis does not necessarily correspond to a worst case scenario for the longer pulses or pulse bursts used by a new method, radiation force imaging. Radiation force imaging, employing ultrasound pulse durations up to hundreds of milliseconds, produces and detects motion in solid tissue or acoustic streaming in fluids via a high intensity beam. Models that calculate the transient temperature rise from these pulses are developed for both the bone at focus and soft tissue cases. Based on accepted time-temperature dose criteria, it is shown that for pulse lengths and intensities utilized by this technique, temperature may increase to levels that raise safety concerns for bone at the focus of the ultrasound beam. Also, the impact on this modality of the current U.S. Food and Drug Administration output limits for diagnostic ultrasound devices is discussed.

  18. Safety criteria for flying E-sail through solar eclipse

    NASA Astrophysics Data System (ADS)

    Janhunen, Pekka; Toivanen, Petri

    2015-09-01

    The electric solar wind sail (E-sail) propellantless propulsion device uses long, charged metallic tethers to tap momentum from the solar wind to produce spacecraft propulsion. If flying through planetary or moon eclipse, the long E-sail tethers can undergo significant thermal contraction and expansion. Rapid shortening of the tether increases its tension due to inertia of the tether and a Remote Unit that is located on the tether tip (a Remote Unit is part of typical E-sail designs). We analyse by numerical simulation the conditions under which eclipse induced stresses are safe for E-sail tethers. We calculate the closest safe approach distances for Earth, Moon, Venus, Mars, Jupiter, Ceres and an exemplary 300 km main belt asteroid Interamnia for circular, parabolic and hyperbolic orbits. We find that any kind of eclipsing is safe beyond approximately 2.5 au distance, but for terrestrial planets safety depends on the parameters of the orbit. For example, for Mars the safe distance with 20 km E-sail tether lies between Phobos and Deimos orbits.

  19. DEVELOPMENT OF RISK-BASED AND TECHNOLOGY-INDEPENDENT SAFETY CRITERIA FOR GENERATION IV SYSTEMS

    SciTech Connect

    William E. Kastenberg; Edward Blandford; Lance Kim

    2009-03-31

    This project has developed quantitative safety goals for Generation IV (Gen IV) nuclear energy systems. These safety goals are risk based and technology independent. The foundations for a new approach to risk analysis has been developed, along with a new operational definition of risk. This project has furthered the current state-of-the-art by developing quantitative safety goals for both Gen IV reactors and for the overall Gen IV nuclear fuel cycle. The risk analysis approach developed will quantify performance measures, characterize uncertainty, and address a more comprehensive view of safety as it relates to the overall system. Appropriate safety criteria are necessary to manage risk in a prudent and cost-effective manner. This study is also important for government agencies responsible for managing, reviewing, and for approving advanced reactor systems because they are charged with assuring the health and safety of the public.

  20. Addressing a radiation safety sentinel event alert: one state's experience.

    PubMed

    Temme, James B; Lane, Thomas; Rutar, Frank; McGowan, Ann

    2012-01-01

    The Joint Commission issued a Sentinel Event Alert in August 2011 to address the radiation risks related to diagnostic medical imaging. The University of Nebraska Medical Center (UNMC) and Nebraska Coalition for Patient Safety (NCPS) sent a survey to Nebraska hospital radiology departments in May 2012 to solicit responses regarding radiation safety management practices. Survey results demonstrate that Nebraska hospitals perform well in many radiation safety efforts, but lack in others, as well as the need for additional research to track or compare progress. Nebraska's experience can serve as a model for other states to perform similar radiation safety management research. PMID:23270117

  1. Evaluation of a Radiation Worker Safety Training Program at a nuclear facility

    SciTech Connect

    Lindsey, J.E.

    1993-05-01

    A radiation safety course was evaluated using the Kirkpatrick criteria of training evaluation as a guide. Thirty-nine employees were given the two-day training course and were compared with 15 employees in a control group who did not receive the training. Cognitive results show an immediate gain in knowledge, and substantial retention at 6 months. Implications of the results are discussed in terms of applications to current radiation safety training was well as follow-on training research and development requirements.

  2. 49 CFR Appendix C to Part 236 - Safety Assurance Criteria and Processes

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 49 Transportation 4 2013-10-01 2013-10-01 false Safety Assurance Criteria and Processes C Appendix C to Part 236 Transportation Other Regulations Relating to Transportation (Continued) FEDERAL RAILROAD ADMINISTRATION, DEPARTMENT OF TRANSPORTATION RULES, STANDARDS, AND INSTRUCTIONS GOVERNING THE INSTALLATION, INSPECTION, MAINTENANCE, AND REPAIR...

  3. 49 CFR Appendix C to Part 236 - Safety Assurance Criteria and Processes

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 49 Transportation 4 2014-10-01 2014-10-01 false Safety Assurance Criteria and Processes C Appendix C to Part 236 Transportation Other Regulations Relating to Transportation (Continued) FEDERAL RAILROAD ADMINISTRATION, DEPARTMENT OF TRANSPORTATION RULES, STANDARDS, AND INSTRUCTIONS GOVERNING THE INSTALLATION, INSPECTION, MAINTENANCE, AND REPAIR...

  4. 14 CFR 414.19 - Technical criteria for reviewing a safety approval application.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Technical criteria for reviewing a safety approval application. 414.19 Section 414.19 Aeronautics and Space COMMERCIAL SPACE TRANSPORTATION, FEDERAL... customized by the manufacturer that intends to produce the system, system component, or part. The...

  5. NCRP Program Area Committee 2: Operational Radiation Safety.

    PubMed

    Goldin, Eric M; Pryor, Kathryn H

    2016-02-01

    Program Area Committee 2 of the National Council on Radiation Protection and Measurements provides guidance for radiation safety in occupational settings in a variety of industries and activities. The Committee completed three reports in recent years covering recommendations for the development and administration of radiation safety programs for smaller educational institutions, requirements for self-assessment programs that improve radiation safety and identify and correct deficiencies, and a comprehensive process for effective investigation of radiological incidents. Ongoing work includes a report on sealed radioactive source controls and oversight of a report on radioactive nanomaterials focusing on gaps within current radiation safety programs. Future efforts may deal with operational radiation safety programs in fields such as the safe use of handheld and portable x-ray fluorescence analyzers, occupational airborne radioactive contamination, unsealed radioactive sources, or industrial accelerators. PMID:26717157

  6. Provisional standards of radiation safety during flights

    NASA Technical Reports Server (NTRS)

    1977-01-01

    Radiation effects during space flights are discussed in the context of the sources and dangers of such radiation and the radiobiological prerequisites for establishing safe levels of radiation dosage. Standard safe levels of radiation during space flight are established.

  7. 12 CFR 747.3003 - Review of order reclassifying a corporate credit union on safety and soundness criteria.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... credit union on safety and soundness criteria. 747.3003 Section 747.3003 Banks and Banking NATIONAL CREDIT UNION ADMINISTRATION REGULATIONS AFFECTING CREDIT UNIONS ADMINISTRATIVE ACTIONS, ADJUDICATIVE... corporate credit union on safety and soundness criteria. (a) Notice of proposed reclassification based...

  8. 12 CFR 747.3003 - Review of order reclassifying a corporate credit union on safety and soundness criteria.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... credit union on safety and soundness criteria. 747.3003 Section 747.3003 Banks and Banking NATIONAL CREDIT UNION ADMINISTRATION REGULATIONS AFFECTING CREDIT UNIONS ADMINISTRATIVE ACTIONS, ADJUDICATIVE... corporate credit union on safety and soundness criteria. (a) Notice of proposed reclassification based...

  9. Training course for radiation safety technicians

    NASA Technical Reports Server (NTRS)

    Lasuk, S. R.; Moe, H. J.

    1967-01-01

    Course of instruction includes sections on basic information, natural radioactivity, properties of alpha, beta, gamma, X rays, and neutrons, concepts of radiation units and dose determinations, shielding, biological effects, background radiation, radiation protection standards, and internal dose calculation.

  10. Radiation safety considerations in proton aperture disposal.

    PubMed

    Walker, Priscilla K; Edwards, Andrew C; Das, Indra J; Johnstone, Peter A S

    2014-04-01

    Beam shaping in scattered and uniform scanned proton beam therapy (PBT) is made commonly by brass apertures. Due to proton interactions, these devices become radioactive and could pose safety issues and radiation hazards. Nearly 2,000 patient-specific devices per year are used at Indiana University Cyclotron Operations (IUCO) and IU Health Proton Therapy Center (IUHPTC); these devices require proper guidelines for disposal. IUCO practice has been to store these apertures for at least 4 mo to allow for safe transfer to recycling contractors. The devices require decay in two staged secure locations, including at least 4 mo in a separate building, at which point half are ready for disposal. At 6 mo, 20-30% of apertures require further storage. This process requires significant space and manpower and should be considered in the design process for new clinical facilities. More widespread adoption of pencil beam or spot scanning nozzles may obviate this issue, as apertures then will no longer be necessary. PMID:24562073

  11. Radiation safety for health care workers in the bronchoscopy suite.

    PubMed

    Jain, P; Fleming, P; Mehta, A C

    1999-03-01

    Increased use of fluoroscopy during flexible bronchoscopy has raised concerns about radiation safety of health care workers in the bronchoscopy suite. We review the potential health risks associated with occupational radiation exposure, the monitoring devices available, and discuss the measures to reduce radiation exposure during flexible bronchoscopy. PMID:10205715

  12. Institutional Radiation Safety Committee--Nuclear Regulatory Commission. Final rule.

    PubMed

    1982-09-13

    The Nuclear Regulatory Commission (NRC) is amending its regulations regarding hospitals licensed to use radioactive byproduct material for human applications. Currently, such a license requires that the hospital have a Medical Isotopes Committee to review clinical aspects of the use of radioactive materials within the hospital. The amendment requires instead a Radiation Safety Committee with a simplified membership that will focus on the radiation safety of workers and the general public. The rule change acknowledges the Food and Drug Administration's role in regulating the safety and effectiveness of radioactive drugs with respect to the patient. The membership of the new Radiation Safety Committee will include the hospital management and the nursing staff in decisions affecting radiation safety at the hospital and will be easier for smaller hospitals to recruit. PMID:10259789

  13. Criticality safety criteria for license review of low-level waste facilities

    SciTech Connect

    Hopper, C.M.; Odegaarden, R.H.; Parks, C.V.; Fox, P.B.

    1995-03-01

    The handling and burial of specified quantities of special nuclear material (SNM) at low-level-waste (LLW) facilities require a license from the Nuclear Regulatory Commission (NRC). With assistance from Oak Ridge National Laboratory (ORNL) staff, the NRC Office of Nuclear Material Safety and Safeguards, Low-Level-Waste and Decommissioning Projects Branch, has developed technical specifications for the nuclear criticality safety of {sup 235}U and {sup 239}Pu in LLW facilities. The objective of the development of these technical specifications was to establish a set of review criteria that are rigorously defensible that can be applied uniformly to all license applications, and that conservatively ensures that buried SNM will not pose a criticality safety concern.

  14. Comparison of radiation safety and nuclear explosive safety disciplines

    SciTech Connect

    Winstanley, J. L.

    1998-10-10

    In August 1945, U.S. Navy Captain William Parsons served as the weaponeer aboard the Enola Gay for the mission to Hiroshima (Shelton 1988). In view of the fact that four B-29s had crashed and burned on takeoff from Tinian the night before, Captain Parsons made the decision to arm the gun-type weapon after takeoff for safety reasons (15 kilotons of TNT equivalent). Although he had no control over the success of the takeoff, he could prevent the possibility of a nuclear detonation on Tinian by controlling what we now call the nuclear explosive. As head of the Ordnance Division at Los Alamos and a former gunnery officer, Captain Parsons clearly understood the role of safety in his work. The advent of the pre-assembled implosion weapon where the high explosive and nuclear materials are always in an intimate configuration meant that nuclear explosive safety became a reality at a certain point in development and production not just at the time of delivery by the military. This is the only industry where nuclear materials are intentionally put in contact with high explosives. The agency of the U.S. Government responsible for development and production of U.S. nuclear weapons is the Department of Energy (DOE) (and its predecessor agencies). This paper will be limited to nuclear explosive safety as it is currently practiced within the DOE nuclear weapons

  15. The maternal early warning criteria: a proposal from the national partnership for maternal safety.

    PubMed

    Mhyre, Jill M; D'Oria, Robyn; Hameed, Afshan B; Lappen, Justin R; Holley, Sharon L; Hunter, Stephen K; Jones, Robin L; King, Jeffrey C; D'Alton, Mary E

    2014-01-01

    Case reviews of maternal death have revealed a concerning pattern of delay in recognition of hemorrhage, hypertensive crisis, sepsis, venous thromboembolism, and heart failure. Early-warning systems have been proposed to facilitate timely recognition, diagnosis, and treatment for women developing critical illness. A multidisciplinary working group convened by the National Partnership for Maternal Safety used a consensus-based approach to define The Maternal Early Warning Criteria, a list of abnormal parameters that indicate the need for urgent bedside evaluation by a clinician with the capacity to escalate care as necessary in order to pursue diagnostic and therapeutic interventions. This commentary reviews the evidence supporting the use of early-warning systems, describes The Maternal Early Warning Criteria, and provides considerations for local implementation. PMID:25203897

  16. The maternal early warning criteria: a proposal from the national partnership for maternal safety.

    PubMed

    Mhyre, Jill M; DʼOria, Robyn; Hameed, Afshan B; Lappen, Justin R; Holley, Sharon L; Hunter, Stephen K; Jones, Robin L; King, Jeffrey C; DʼAlton, Mary E

    2014-10-01

    Case reviews of maternal death have revealed a concerning pattern of delay in recognition of hemorrhage, hypertensive crisis, sepsis, venous thromboembolism, and heart failure. Early-warning systems have been proposed to facilitate timely recognition, diagnosis, and treatment for women developing critical illness. A multidisciplinary working group convened by the National Partnership for Maternal Safety used a consensus-based approach to define The Maternal Early Warning Criteria, a list of abnormal parameters that indicate the need for urgent bedside evaluation by a clinician with the capacity to escalate care as necessary in order to pursue diagnostic and therapeutic interventions. This commentary reviews the evidence supporting the use of early-warning systems and describes The Maternal Early Warning Criteria, along with considerations for local implementation. PMID:25198266

  17. Radiation safety and nuclear medicine policies and procedures.

    PubMed

    Berman, C G

    1999-07-01

    There is a growing concern over possible adverse effects from medical applications of ionizing radiation. Hospital personnel must be educated in procedures to minimize exposure to themselves and their patients. Basic radiation safety procedures to protect personnel and patients are discussed. Examples of the nuclear medicine policies and procedures used for lymphatic mapping are provided. PMID:10448699

  18. RADIATION ACCESS ZONE AND VENTILATION CONFINEMENT ZONE CRITERIA FOR THE MGR SURFACE FACILITIES

    SciTech Connect

    D. A. Padula

    2000-09-13

    The objectives of this technical report are to: (1) Establish the criteria for Radiation Access Zone (RAZ) designation. (2) Establish the criteria for the Ventilation Confinement Zone (VCZ) designation. The scope will be to formulate the RAZ and VCZ zoning designation for the Monitored Geologic Repository (MGR) surface facilities and to apply the zoning designations to the current Waste Handling Building (WHB), Waste Treatment Building (WTB), and Carrier Preparation Building (CPB) configurations.

  19. Safety review of the design, operation, and radiation sections of the General Electric Morris Operation Consolidated Safety Analysis Report

    SciTech Connect

    McBride, J.P.

    1981-01-30

    A safety review was made of Sections 4 through 9 of the Consolidated Safety Analysis Report (CSAR) for the GE Morris Operation spent-fuel storage facility. The sections reviewed include Design Criteria and Compliance, Facility Design and Description, Radiation Protection, Accident Analysis, and Conduct of Operations. The safety review was performed in accordance with the Code of Federal Regulations, Title 10, Part 72, ''Licensing Requirements for the Storage of Spent Fuel in an Independent Spent Fuel Storage Installation'' and contains independent estimations of source terms and dose-commitments from postulated accidents in the storage facility and a structural analysis of the Morris Operation cranes as an appendix. The review confirms that the features of the facility as described in Sections 4 through 9 of the CSAR fulfilled the safety requirements of 10 CFR 72, and it is concluded that spent-fuel handling and storage at the Morris Operation do not present significant risks to public health and safety. 15 refs., 3 tabs.

  20. 12 CFR 747.2003 - Review of order reclassifying a credit union on safety and soundness criteria.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 12 Banks and Banking 7 2014-01-01 2014-01-01 false Review of order reclassifying a credit union on safety and soundness criteria. 747.2003 Section 747.2003 Banks and Banking NATIONAL CREDIT UNION... Corrective Action § 747.2003 Review of order reclassifying a credit union on safety and soundness...

  1. 12 CFR 747.2003 - Review of order reclassifying a credit union on safety and soundness criteria.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 12 Banks and Banking 6 2010-01-01 2010-01-01 false Review of order reclassifying a credit union on safety and soundness criteria. 747.2003 Section 747.2003 Banks and Banking NATIONAL CREDIT UNION... Corrective Action § 747.2003 Review of order reclassifying a credit union on safety and soundness...

  2. 12 CFR 747.2003 - Review of order reclassifying a credit union on safety and soundness criteria.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 12 Banks and Banking 6 2011-01-01 2011-01-01 false Review of order reclassifying a credit union on safety and soundness criteria. 747.2003 Section 747.2003 Banks and Banking NATIONAL CREDIT UNION... Corrective Action § 747.2003 Review of order reclassifying a credit union on safety and soundness...

  3. Radiation safety: what can happen in an accident.

    PubMed

    Scully, C; de Almeida, O P

    1992-04-11

    Radiation hazards in dental practice have long been recognized, and the dangers from ionising radiation during dental radiography are discussed elsewhere. Continuing legislation will undoubtedly help reduce the risk of over-exposure and accidents. Nevertheless, it is of some concern that radiation safety is still ignored by some: for example, one recent survey in the UK showed that not all radiography sets conformed to modern safety standards. However, the profession also has reason to be concerned about more public radiation hazards that may affect them, and their families and others, and may, without denying the importance of dental radiation protection, have far greater effects on health. Well-known examples of domestic radon exposure occurred in the UK, particularly in the Lake District and the South West, and the nuclear reactor accidents--notably at Chernobyl in 1986. PMID:1576019

  4. [RADIATION SAFETY DURING REMEDIATION OF THE "SEVRAO" FACILITIES].

    PubMed

    Shandala, N K; Kiselev, S M; Titov, A V; Simakov, A V; Seregin, V A; Kryuchkov, V P; Bogdanova, L S; Grachev, M I

    2015-01-01

    Within a framework of national program on elimination of nuclear legacy, State Corporation "Rosatom" is working on rehabilitation at the temporary waste storage facility at Andreeva Bay (Northwest Center for radioactive waste "SEVRAO"--the branch of "RosRAO"), located in the North-West of Russia. In the article there is presented an analysis of the current state of supervision for radiation safety of personnel and population in the context of readiness of the regulator to the implementation of an effective oversight of radiation safety in the process of radiation-hazardous work. Presented in the article results of radiation-hygienic monitoring are an informative indicator of the effectiveness of realized rehabilitation measures and characterize the radiation environment in the surveillance zone as a normal, without the tendency to its deterioration. PMID:26625607

  5. Preliminary safety criteria for organic watch list tanks at the Hanford site

    SciTech Connect

    Webb, A.B.; Stewart, J.L.; Turner, O.A.; Plys, M.G.; Malinovic, B.; Grigsby, J.M.; Camaioni, D.M.; Heasler, P.G.; Samuels, W.O.; Toth, J.J.

    1995-11-01

    Condensed-phase, rapid reactions of organic salts with nitrates/nitrites in Hanford High Level Radioactive Waste single-shell tanks could lead to structural failure of the tanks resulting in significant releases of radionuclides and toxic materials. This report establishes appropriate preliminary safety criteria to ensure that tank wastes will be maintained safe. These criteria show that if actual dry wastes contain less than 1.2 MJ/kg of reactants reaction energy or less 4.5 wt % of total organic carbon, then the waste will be safe and will not propagate if ignited. Waste moisture helps to retard reactions; when waste moisture exceeds 20 wt %, rapid reactions are prevented, regardless of organic carbon concentrations. Aging and degradation of waste materials has been considered to predict the types and amounts to organic compounds present in the waste. Using measurements of 3 waste phases (liquid, salt cake, and sludge) obtained from tank waste samples analyzed in the laboratory, analysis of variance (ANOVA) models were used to estimate waste states for unmeasured tanks. The preliminary safety criteria are based upon calorimetry and propagation testing of likely organic compounds which represent actual tank wastes. These included sodium salts of citrate, formate, acetate and hydroxyethylethylenediaminetricetate (HEDTA). Hot cell tests of actual tank wastes are planned for the future to confirm propagation tests performed in the laboratory. The effects of draining liquids from the tanks which would remove liquids and moisture were considered because reactive waste which is too dry may propagate. Evaporation effects which could remove moisture from the tanks were also calculated. The various ways that the waste could be heated or ignited by equipment failures or tank operations activities were considered and appropriate monitoring and controls were recommended.

  6. Radiation safety at accelerator facilities NCRP activities

    NASA Astrophysics Data System (ADS)

    Kase, Kenneth R.

    1997-02-01

    The National Council on Radiation Protection and Measurements (NCRP) has issued 13 reports, dating back to 1949, giving guidance and recommendations for radiation protection at accelerator facilities. There are six current reports on the topics of neutron radiation; facility and shielding design; alarms and access control systems; and equipment design, performance, and use. Scientific Committee 46 (SC 46) is currently overseeing the development of two reports that will provide up-to-date guidance for the design of medical accelerator facilities and shielding. SC 46 has also proposed that a report be written to provide guidance for the design and shielding of industrial accelerator and large irradiator facilities. This paper describes the status and contents of these reports.

  7. [Depleted uranium: radiation and ecological safety aspects].

    PubMed

    Ushakov, I B; Afanas'ev, R V; Berezin, G I; Zuev, V G

    2003-01-01

    The authors have analyzed the ecological, sanitary-and-hygienic and medicobiologic aspects of using the impoverished uranium in armaments and military equipment. The influence of impoverished uranium on human body (600 cases) was studied using medicobiologic investigation. It was shown that the particles of aerosol of mixed uranium oxide cause the radiation and chemical damage of kidneys, lungs and other internals. Uranium's alpha-radiation is very effective in induction of biologic effects during internal irradiation. Taking into account that bone tissue is the critical organ for uranium isotopes the medullar tissue is exposed to alpha-radiation. In the armed conflicts of the last decade wide use of armour-piercing means with elements consisted of impoverished uranium has led to the appearance of new technogenic risk factor for the environment and the man. PMID:12825370

  8. Radiation safety training for accelerator facilities

    SciTech Connect

    Trinoskey, P.A.

    1997-02-01

    In November 1992, a working group was formed within the U.S. Department of Energy`s (DOE`s) accelerator facilities to develop a generic safety training program to meet the basic requirements for individuals working in accelerator facilities. This training, by necessity, includes sections for inserting facility-specific information. The resulting course materials were issued by DOE as a handbook under its technical standards in 1996. Because experimenters may be at a facility for only a short time and often at odd times during the day, the working group felt that computer-based training would be useful. To that end, Lawrence Livermore National Laboratory (LLNL) and Argonne National Laboratory (ANL) together have developed a computer-based safety training program for accelerator facilities. This interactive course not only enables trainees to receive facility- specific information, but time the training to their schedule and tailor it to their level of expertise.

  9. Criteria for development of a database for safety evaluation of fragrance ingredients.

    PubMed

    Ford, R A; Domeyer, B; Easterday, O; Maier, K; Middleton, J

    2000-04-01

    Over 2000 different ingredients are used in the manufacture of fragrances. The majority of these ingredients have been used for many decades. Despite this long history of use, all of these ingredients need continued monitoring to ensure that each ingredient meets acceptable safety standards. As with other large databases of existing chemicals, fulfilling this need requires an organized approach to identify the most important potential hazards. One such approach, specifically considering the dermal route of exposure as the most relevant one for fragrance ingredients, has been developed. This approach provides a rational selection of materials for review and gives guidance for determining the test data that would normally be considered necessary for the elevation of safety under intended conditions of use. As a first step, the process takes into account the following criteria: quantity of use, consumer exposure, and chemical structure. These are then used for the orderly selection of materials for review with higher quantity, higher exposure, and the presence of defined structural alerts all contributing to a higher priority for review. These structural alerts along with certain exposure and volume limits are then used to develop guidelines for determining the quality and quantity of data considered necessary to support an adequate safety evaluation of the chosen materials, taking into account existing data on the substance itself as well as on closely related analogs. This approach can be considered an alternative to testing; therefore, it is designed to be conservative but not so much so as to require excessive effort when not justified. PMID:10854123

  10. Computer-based and web-based radiation safety training

    SciTech Connect

    Owen, C., LLNL

    1998-03-01

    The traditional approach to delivering radiation safety training has been to provide a stand-up lecture of the topic, with the possible aid of video, and to repeat the same material periodically. New approaches to meeting training requirements are needed to address the advent of flexible work hours and telecommuting, and to better accommodate individuals learning at their own pace. Computer- based and web-based radiation safety training can provide this alternative. Computer-based and web- based training is an interactive form of learning that the student controls, resulting in enhanced and focused learning at a time most often chosen by the student.

  11. The controversy over radiation safety. A historical overview.

    PubMed

    Walker, J S

    1989-08-01

    The hazards of ionizing radiation have aroused concern since a short time after the discovery of x-rays and natural radioactivity in the 1890s. Misuse of x-rays and radium prompted efforts to encourage radiation safety and to set limits on exposure, culminating in the first recommended "tolerance doses" in 1934. After World War II, the problems of radiation protection became more complex because of the growing number of people subjected to radiation injury and the creation of radioactive elements that had never existed before the achievement of atomic fission. Judging the hazards of radiation became a matter of spirited controversy. Major public debates over the dangers of radioactive fallout from atmospheric bomb testing in the 1950s and early 1960s and the risks of nuclear power generation in later periods focused attention on the uncertainties about the consequences of exposure to low-level radiation and the difficulties of resolving them. PMID:2664237

  12. A Criteria Standard for Conflict Resolution: A Vision for Guaranteeing the Safety of Self-Separation in NextGen

    NASA Technical Reports Server (NTRS)

    Munoz, Cesar; Butler, Ricky; Narkawicz, Anthony; Maddalon, Jeffrey; Hagen, George

    2010-01-01

    Distributed approaches for conflict resolution rely on analyzing the behavior of each aircraft to ensure that system-wide safety properties are maintained. This paper presents the criteria method, which increases the quality and efficiency of a safety assurance analysis for distributed air traffic concepts. The criteria standard is shown to provide two key safety properties: safe separation when only one aircraft maneuvers and safe separation when both aircraft maneuver at the same time. This approach is complemented with strong guarantees of correct operation through formal verification. To show that an algorithm is correct, i.e., that it always meets its specified safety property, one must only show that the algorithm satisfies the criteria. Once this is done, then the algorithm inherits the safety properties of the criteria. An important consequence of this approach is that there is no requirement that both aircraft execute the same conflict resolution algorithm. Therefore, the criteria approach allows different avionics manufacturers or even different airlines to use different algorithms, each optimized according to their own proprietary concerns.

  13. Radiation safety at the West Valley Demonstration Project

    SciTech Connect

    Hoffman, R.L.

    1997-05-06

    This is a report on the Radiation Safety Program at the West Valley Demonstration Project (WVDP). This Program covers a number of activities that support high-level waste solidification, stabilization of facilities, and decontamination and decommissioning activities at the Project. The conduct of the Program provides confidence that all occupational radiation exposures received during operational tasks at the Project are within limits, standards, and program requirements, and are as low as reasonably achievable.

  14. Space Weather Nowcasting of Atmospheric Ionizing Radiation for Aviation Safety

    NASA Technical Reports Server (NTRS)

    Mertens, Christopher J.; Wilson, John W.; Blattnig, Steve R.; Solomon, Stan C.; Wiltberger, J.; Kunches, Joseph; Kress, Brian T.; Murray, John J.

    2007-01-01

    There is a growing concern for the health and safety of commercial aircrew and passengers due to their exposure to ionizing radiation with high linear energy transfer (LET), particularly at high latitudes. The International Commission of Radiobiological Protection (ICRP), the EPA, and the FAA consider the crews of commercial aircraft as radiation workers. During solar energetic particle (SEP) events, radiation exposure can exceed annual limits, and the number of serious health effects is expected to be quite high if precautions are not taken. There is a need for a capability to monitor the real-time, global background radiations levels, from galactic cosmic rays (GCR), at commercial airline altitudes and to provide analytical input for airline operations decisions for altering flight paths and altitudes for the mitigation and reduction of radiation exposure levels during a SEP event. The Nowcast of Atmospheric Ionizing Radiation for Aviation Safety (NAIRAS) model is new initiative to provide a global, real-time radiation dosimetry package for archiving and assessing the biologically harmful radiation exposure levels at commercial airline altitudes. The NAIRAS model brings to bear the best available suite of Sun-Earth observations and models for simulating the atmospheric ionizing radiation environment. Observations are utilized from ground (neutron monitors), from the atmosphere (the METO analysis), and from space (NASA/ACE and NOAA/GOES). Atmospheric observations provide the overhead shielding information and the ground- and space-based observations provide boundary conditions on the GCR and SEP energy flux distributions for transport and dosimetry simulations. Dose rates are calculated using the parametric AIR (Atmospheric Ionizing Radiation) model and the physics-based HZETRN (High Charge and Energy Transport) code. Empirical models of the near-Earth radiation environment (GCR/SEP energy flux distributions and geomagnetic cut-off rigidity) are benchmarked

  15. A Radiation Safety Analysis for Lunar Lava Tubes

    NASA Technical Reports Server (NTRS)

    DeAngelis, G.; Wilson, J. W.; Clowdsley, M. S.; Nealy, J. E.; Humes, D. H.; Clem, J. M.

    2002-01-01

    The purpose of this work is an assessment of the lunar lava tubes physical characteristics and an evaluation of the their actual safety features from the point of view of the ionizing radiation environment as potential habitats for future lunar exploration crews. Additional information is contained in the original extended abstract.

  16. Corporate Functional Management Evaluation of the LLNL Radiation Safety Organization

    SciTech Connect

    Sygitowicz, L S

    2008-03-20

    A Corporate Assess, Improve, and Modernize review was conducted at Lawrence Livermore National Laboratory (LLNL) to evaluate the LLNL Radiation Safety Program and recommend actions to address the conditions identified in the Internal Assessment conducted July 23-25, 2007. This review confirms the findings of the Internal Assessment of the Institutional Radiation Safety Program (RSP) including the noted deficiencies and vulnerabilities to be valid. The actions recommended are a result of interviews with about 35 individuals representing senior management through the technician level. The deficiencies identified in the LLNL Internal Assessment of the Institutional Radiation Safety Program were discussed with Radiation Safety personnel team leads, customers of Radiation Safety Program, DOE Livermore site office, and senior ES&H management. There are significant issues with the RSP. LLNL RSP is not an integrated, cohesive, consistently implemented program with a single authority that has the clear roll and responsibility and authority to assure radiological operations at LLNL are conducted in a safe and compliant manner. There is no institutional commitment to address the deficiencies that are identified in the internal assessment. Some of these deficiencies have been previously identified and corrective actions have not been taken or are ineffective in addressing the issues. Serious funding and staffing issues have prevented addressing previously identified issues in the Radiation Calibration Laboratory, Internal Dosimetry, Bioassay Laboratory, and the Whole Body Counter. There is a lack of technical basis documentation for the Radiation Calibration Laboratory and an inadequate QA plan that does not specify standards of work. The Radiation Safety Program lack rigor and consistency across all supported programs. The implementation of DOE Standard 1098-99 Radiological Control can be used as a tool to establish this consistency across LLNL. The establishment of a site

  17. A new standard for core training in radiation safety

    SciTech Connect

    Trinoskey, P.A.

    1997-02-01

    A new American National Standard for radiation worker training was recently developed. The standard emphasizes performance-based training and establishing a training program rather than simply prescribing objectives. The standard also addresses basic criteria, including instructor qualifications. The standard is based on input from a wide array of regulatory agencies, universities, national laboratories, and nuclear power entities. This paper presents an overview of the new standard and the philosophy behind it. The target audience includes radiation workers, management and supervisory personnel, contractors, students, emergency personnel, and visitors.

  18. A management system integrating radiation protection and safety supporting safety culture in the hospital.

    PubMed

    Almén, A; Lundh, C

    2015-04-01

    Quality assurance has been identified as an important part of radiation protection and safety for a considerable time period. A rational expansion and improvement of quality assurance is to integrate radiation protection and safety in a management system. The aim of this study was to explore factors influencing the implementing strategy when introducing a management system including radiation protection and safety in hospitals and to outline benefits of such a system. The main experience from developing a management system is that it is possible to create a vast number of common policies and routines for the whole hospital, resulting in a cost-efficient system. One of the key benefits is the involvement of management at all levels, including the hospital director. Furthermore, a transparent system will involve staff throughout the organisation as well. A management system supports a common view on what should be done, who should do it and how the activities are reviewed. An integrated management system for radiation protection and safety includes key elements supporting a safety culture. PMID:25429027

  19. Radiation Safety of Sealed Radioactive Sources

    SciTech Connect

    Pryor, Kathryn H.

    2015-01-29

    Sealed radioactive sources are used in a wide variety of occupational settings and under differing regulatory/licensing structures. The definition of a sealed radioactive source varies between US regulatory authorities and standard-setting organizations. Potential problems with sealed sources cover a range of risks and impacts. The loss of control of high activity sealed sources can result in very high or even fatal doses to members of the public who come in contact with them. Sources that are not adequately sealed, and that fail, can cause spread of contamination and potential intake of radioactive material. There is also the possibility that sealed sources may be (or threatened to be) used for terrorist purposes and disruptive opportunities. Until fairly recently, generally-licensed sealed sources and devices received little, if any, regulatory oversight, and were often forgotten, lost or unaccounted for. Nonetheless, generally licensed devices can contain fairly significant quantities of radioactive material and there is some potential for exposure if a device is treated in a way that it was never designed. Industrial radiographers use and handle high activity and/or high-dose rate sealed sources in the field with a high degree of independence and minimal regulatory oversight. Failure to follow operational procedures and properly handle radiography sources can and has resulted in serious injuries and death. Industrial radiographers have experienced a disproportionately large fraction of incidents that result in unintended exposure to radiation. Sources do not have to contain significant quantities of radioactive material to cause problems in the event of their failure. A loss of integrity can cause the spread of contamination and potential exposure to workers and members of the public. The NCRP has previously provided recommendations on select aspects of sealed source programs. Future efforts to provide recommendations for sealed source programs are discussed.

  20. Radiation Safety Design for SSRL Storage Ring

    SciTech Connect

    Khater, Hesham; Liu, James; Fasso, Alberto; Prinz, Alyssa; Rokni, Sayed; /SLAC

    2007-02-12

    In 2003, the Stanford Synchrotron Radiation Laboratory (SSRL) has upgraded its storage ring to a 3rd generation storage ring (SPEAR3). SPEAR3 is deigned to operate at 500 mA stored beam current and 3 GeV energy. The 234-meter circumference SPEAR3 ring utilizes 60-cm-thick concrete lateral walls, 30-cm-thick concrete roof, as well as 60-cm or 90-cm-thick concrete ratchet walls. A total of 3.5 x 10{sup 15} e{sup -}/y will be injected into the ring with an injection power of 4 W and an injection efficiency of 75%. Normal beam losses occur due to both injection and stored beam operations in the total of 20 low loss as well as 3 high loss limiting apertures. During the 6-minutes injection period, an instantaneous power loss of 0.05 W occurs at each low loss aperture. When averaged over the operational year, the loss of both the injection and stored beams is equivalent to an average loss of 2 mW at each low loss aperture. On the other hand, the average losses in the high loss apertures are 16 mW for the injection septum, 47 mW for the beam abort dump, and 13 mW for the ring stoppers. The shielding requirements for losses in the new ring were based on a generic approach that used both FLUKA Monte Carlo particle generation and transport code and empirical computer codes and formulae.

  1. Radiation safety of crew and passengers of air transportation in civil aviation. Provisional standards

    SciTech Connect

    Aksenov, A.F.; Burnazyan, A.I.

    1985-03-01

    The purpose and application of the provisional standards for radiation safety of crew and passengers in civil aviation are given. The radiation effect of cosmic radiation in flight on civil aviation air transport is described. Standard levels of radiation and conditions of radiation safety are discussed.

  2. Radiation safety of crew and passengers of air transportation in civil aviation. Provisional standards

    NASA Technical Reports Server (NTRS)

    Aksenov, A. F.; Burnazyan, A. I.

    1985-01-01

    The purpose and application of the provisional standards for radiation safety of crew and passengers in civil aviation are given. The radiation effect of cosmic radiation in flight on civil aviation air transport is described. Standard levels of radiation and conditions of radiation safety are discussed.

  3. Improved Performance of Energy Window Ratio Criteria Obtained Using Multiple Windows at Radiation Portal Monitoring Sites

    SciTech Connect

    Weier, Dennis R.; Lopresti, Charles A.; Ely, James H.; Bates, Derrick J.; Kouzes, Richard T.

    2006-06-07

    Radiation portal monitors are being used to detect radioactive target materials in vehicles transporting cargo. As vehicles pass through the portal monitors, they generate count profiles over time that can be compared to the average panel background counts obtained just prior to the time the vehicle entered the area of the monitors. Pacific Northwest National Laboratory, in support of U.S. Customs and Border Protection (CBP) and U.S. Domestic Nuclear Detection Office (DNDO) under the U.S. Department of Homeland Security (DHS), has accumulated considerable data regarding such background radiation and vehicle profiles from portal installations. Energy window criteria have been shown to increase sensitivity to certain types of target radioactive sources while also controlling to a manageable level the rate of false or nuisance alarms. First generation equipment had only two-window capability, and while energy windowing for such systems was shown to be useful for detecting certain types of sources, it was subsequently found that improved performance could be obtained with more windows. Second generation equipment instead has more windows and can thus support additional energy window criteria which can be shown to be sensitive to a wider set of target sources. Detection likelihoods are generated for various sources and energy window criteria, as well as for gross count decision criteria, based on computer simulated injections of sources into archived vehicle profiles. (PIET-43741-TM-534)

  4. Safety, effectiveness and economic evaluation of intra-operative radiation therapy: a systematic review

    PubMed Central

    Najafipour, Farshad; Hamouzadeh, Pejman; Arabloo, Jalal; Mobinizadeh, Mohammadreza; Norouzi, Amir

    2015-01-01

    Background: Intra-operative radiation therapy (IORT) is the transfer of a single large radiation dose to the tumor bed during surgery with the final goal of improving regional tumor control. This study aimed to investigate the safety, effectiveness and economic evaluation of intra-operative radiation therapy. Methods: The scientific literature was searched in the main biomedical databases (Centre for Reviews and Dissemination, Cochrane Library and PubMed) up to March 2014. Two independent reviewers selected the papers based on pre-established inclusion criteria, with any disagreements being resolved by consensus. Data were then extracted and summarized in a structured form. Results from studies were analyzed and discussed within a descriptive synthesis. Results: Sixteen studies met the inclusion criteria. It seems that outcomes from using intraoperative radiation therapy can be considered in various kinds of cancers like breast, pancreatic and colorectal cancers. The application of this method may provide significant survival increase only for colorectal cancer, but this increase was not significant for other types of cancer. This technology had low complications; and it is relatively safe. Using intra-operative radiation therapy could potentially be accounted as a cost-effective strategy for controlling and managing breast cancer. Conclusion: According to the existing evidences, that are the highest medical evidences for using intra-operative radiation therapy, one can generally conclude that intra-operative radiation therapy is considered as a relatively safe and cost-effective method for managing early-stage breast cancer and it can significantly increase the survival of patients with colorectal cancer. Also, the results of this study have policy implications with respect to the reimbursement of this technology. PMID:26793649

  5. 12 CFR 747.3003 - Review of order reclassifying a corporate credit union on safety and soundness criteria.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... the record nor the Uniform Rules of Practice and Procedure (12 CFR part 747) will apply to an informal... HEARINGS, RULES OF PRACTICE AND PROCEDURE, AND INVESTIGATIONS Issuance, Review and Enforcement of Orders... corporate credit union on safety and soundness criteria. (a) Notice of proposed reclassification based...

  6. 12 CFR 747.3003 - Review of order reclassifying a corporate credit union on safety and soundness criteria.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... the record nor the Uniform Rules of Practice and Procedure (12 CFR part 747) will apply to an informal... HEARINGS, RULES OF PRACTICE AND PROCEDURE, AND INVESTIGATIONS Issuance, Review and Enforcement of Orders... corporate credit union on safety and soundness criteria. (a) Notice of proposed reclassification based...

  7. Problems and conception of ensuring radiation safety during Mars missions.

    PubMed

    Petrov, V M

    2004-01-01

    The Mars mission differs from near-Earth manned space flights by radiation environment and duration. The importance of effective using the weight of the spacecraft increases greatly because all the necessary things for the mission must be included in its starting weight. For this reason the development of optimal systems of radiation safety ensuring (RSES) acquires especial importance. It is the result of sharp change of radiation environment in the interplanetary space as compared to the one in the near-Earth orbits and significant increase of the interplanetary flight duration. The demand of a harder limitation of unfavorable factors effects should lead to radiation safety (RS) standards hardening. The main principles of ensuring the RS of the Mars mission (optimizing, radiation risk, ALARA) and the conception of RSES, developed on the basis of the described approach and the experience obtained during orbital flights are presented in the report. The problems that can impede the ensuring of the crew members' RS are also given here. PMID:15881790

  8. Thyroid cancer radioiodine therapy: health service performance and radiation safety.

    PubMed

    Vogiatzi, S; Liossis, A; Lamprinakou, M

    2015-07-01

    Greek Atomic Energy Commission collected data related to radioiodine I-131 therapy (RAIT) delivery to differentiated thyroid carcinoma patients, for the period 2003-13, corresponding to 100 % of hospitals at national level. Radiation safety and health service performance outcome indicators were assessed. The numbers of hospitals and nuclear medicine (NM) therapy wards, as well as RAIT annual frequencies, have increased. Geographical inhomogeneous distribution of existing infrastructure is recorded. In some cases, the observed inefficient use of NM therapy wards seems to be due to lack of human resources (e.g. nurses). Regular assessment of appropriate key indicators could serve as a useful tool for radiation safety monitoring and health service performance improvement. PMID:25809109

  9. 21 CFR 14.120 - Establishment of the Technical Electronic Product Radiation Safety Standards Committee (TEPRSSC).

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... Radiation Safety Standards Committee (TEPRSSC). 14.120 Section 14.120 Food and Drugs FOOD AND DRUG... Technical Electronic Products Radiation Safety Standards Committee § 14.120 Establishment of the Technical Electronic Product Radiation Safety Standards Committee (TEPRSSC). The Technical Electronic Product...

  10. 21 CFR 14.120 - Establishment of the Technical Electronic Product Radiation Safety Standards Committee (TEPRSSC).

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... Radiation Safety Standards Committee (TEPRSSC). 14.120 Section 14.120 Food and Drugs FOOD AND DRUG... Technical Electronic Products Radiation Safety Standards Committee § 14.120 Establishment of the Technical Electronic Product Radiation Safety Standards Committee (TEPRSSC). The Technical Electronic Product...

  11. 21 CFR 14.120 - Establishment of the Technical Electronic Product Radiation Safety Standards Committee (TEPRSSC).

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... Radiation Safety Standards Committee (TEPRSSC). 14.120 Section 14.120 Food and Drugs FOOD AND DRUG... Technical Electronic Products Radiation Safety Standards Committee § 14.120 Establishment of the Technical Electronic Product Radiation Safety Standards Committee (TEPRSSC). The Technical Electronic Product...

  12. 21 CFR 14.120 - Establishment of the Technical Electronic Product Radiation Safety Standards Committee (TEPRSSC).

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... Radiation Safety Standards Committee (TEPRSSC). 14.120 Section 14.120 Food and Drugs FOOD AND DRUG... Technical Electronic Products Radiation Safety Standards Committee § 14.120 Establishment of the Technical Electronic Product Radiation Safety Standards Committee (TEPRSSC). The Technical Electronic Product...

  13. Compliance of Bhabhatron-II telecobalt unit with IEC standard - Radiation safety.

    PubMed

    Sahani, G; Kumar, Munish; Dash Sharma, P K; Sharma, D N; Chhokra, Kanta; Mishra, Bibekananda; Agarwal, S P; Kher, R K

    2009-01-01

    Bhabha Atomic Research Centre, Mumbai, India designed and developed a telecobalt unit, which was named as Bhabhatron-II. In this paper, the results pertaining to radiation safety of indigenously developed Bhabhatron-II telecobalt unit are reported. The various tests were carried out as per requirements of International Electrotechnical Commission standard and acceptance criteria developed nationally. Various devices such as CaSO4:Dy based thermoluminescent dosimeters, farmer type ionization chamber, water phantom and radiographic films were used. All the parameters pertaining to radiation leakage/transmission were within the tolerance limits as per IEC-60601-2-11 standard except the collimator transmission through X collimators (upper jaw), which marginally exceeds the tolerance limit. PMID:19458599

  14. Developing the radiation protection safety culture in the UK.

    PubMed

    Cole, P; Hallard, R; Broughton, J; Coates, R; Croft, J; Davies, K; Devine, I; Lewis, C; Marsden, P; Marsh, A; McGeary, R; Riley, P; Rogers, A; Rycraft, H; Shaw, A

    2014-06-01

    In the UK, as elsewhere, there is potential to improve how radiological challenges are addressed through improvement in, or development of, a strong radiation protection (RP) safety culture. In preliminary work in the UK, two areas have been identified as having a strong influence on UK society: the healthcare and nuclear industry sectors. Each has specific challenges, but with many overlapping common factors. Other sectors will benefit from further consideration.In order to make meaningful comparisons between these two principal sectors, this paper is primarily concerned with cultural aspects of RP in the working environment and occupational exposures rather than patient doses.The healthcare sector delivers a large collective dose to patients each year, particularly for diagnostic purposes, which continues to increase. Although patient dose is not the focus, it must be recognised that collective patient dose is inevitably linked to collective occupational exposure, especially in interventional procedures.The nuclear industry faces major challenges as work moves from operations to decommissioning on many sites. This involves restarting work in the plants responsible for the much higher radiation doses of the 1960/70s, but also performing tasks that are considerably more difficult and hazardous than those original performed in these plants.Factors which influence RP safety culture in the workplace are examined, and proposals are considered for a series of actions that may lead to an improvement in RP culture with an associated reduction in dose in many work areas. These actions include methods to improve knowledge and awareness of radiation safety, plus ways to influence management and colleagues in the workplace. The exchange of knowledge about safety culture between the nuclear industry and medical areas may act to develop RP culture in both sectors, and have a wider impact in other sectors where exposures to ionising radiations can occur. PMID:24894330

  15. Laser sources in dentistry and radiation safety regulations

    NASA Astrophysics Data System (ADS)

    De Luca, D.; Gaeta, G. M.; Lepore, M.

    2007-02-01

    Nowadays laser sources are largely adopted in dentistry due to their unique properties making them good candidates to substitute traditional scalpel and conventional diamond bur in the surgery of the soft and hard oral tissue, respectively. The large use of laser sources outside the research laboratories without the need of highly specialized personnel can ask for a widespread knowledge of safety issues related to this kind of equipment. The main hazard of accidental exposures regards eyes injury but increasing the power of the laser beam also skin can be involved. Safety legislations in Europe and U.S.A. take into account non ionizing radiations and laser radiation for the hazards for the health deriving from physical agents. Laser safety standards introduce 3 useful parameters for hazard characterization: "Accessible Emission Limit" (AEL), "Maximum Permissible Exposure" (MPE) and "Nominal Ocular Hazard Distance" (NOHD). We measured the MPE and NOHD for Er:YAG and other laser sources currently adopted in dentistry and we compared our results with data elaborated from standards in order to single out safe and comfortable working conditions. In fact an experimental assessment of the hazard parameters and the comparison with those of reference from safety standards turns out to be useful in order to estimate the residual hazard that can be still present after applying all the engineering protection and administrative rules.

  16. Radiation safety issues related to radiolabeled antibodies. [Contains glossary

    SciTech Connect

    Barber, D.E.; Baum, J.W.; Meinhold, C. B. )

    1991-03-01

    Techniques related to the use of radiolabeled antibodies in humans are reviewed and evaluated in this report. It is intended as an informational resource for the US Nuclear Regulatory Commission (NRC) and NRC licensees. Descriptions of techniques and health and safety issues are provided. Principal methods for labeling antibodies are summarized to help identify related radiation safety problems in the preparation of dosages for administration to patients. The descriptions are derived from an extensive literature review and consultations with experts in the field. A glossary of terms and acronyms is also included. An assessment was made of the extent of the involvement of organizations (other than the NRC) with safety issues related to radiolabeled antibodies, in order to identify regulatory issues which require attention. Federal regulations and guides were also reviewed for their relevance. A few (but significant) differences between the use of common radiopharmaceuticals and radiolabeled antibodies were observed. The clearance rate of whole, radiolabeled immunoglobulin is somewhat slower than common radiopharmaceuticals, and new methods of administration are being used. New nuclides are being used or considered (e.g., Re-186 and At-211) for labeling antibodies. Some of these nuclides present new dosimetry, instrument calibration, and patient management problems. Subjects related to radiation safety that require additional research are identified. 149 refs., 3 figs., 20 tabs.

  17. Optimizing Radiation Safety in the Cardiac Catheterization Laboratory: A Practical Approach.

    PubMed

    Christopoulos, Georgios; Makke, Lorenza; Christakopoulos, Georgios; Kotsia, Anna; Rangan, Bavana V; Roesle, Michele; Haagen, Donald; Kumbhani, Dharam J; Chambers, Charles E; Kapadia, Samir; Mahmud, Ehtisham; Banerjee, Subhash; Brilakis, Emmanouil S

    2016-02-01

    Reducing radiation exposure during cardiovascular catheterization is of paramount importance for both patient and staff safety. Over the years, advances in equipment and application of radiation safety protocols have significantly reduced patient dose and operator exposure. This review examines the current status of radiation protection in the cardiac and vascular catheterization laboratory and summarizes best practices for minimizing radiation exposure. PMID:26526181

  18. Multi-criteria analysis on how to select solar radiation hydrogen production system

    SciTech Connect

    Badea, G.; Naghiu, G. S. Felseghi, R.-A.; Giurca, I.; Răboacă, S.; Aşchilean, I.

    2015-12-23

    The purpose of this article is to present a method of selecting hydrogen-production systems using the electric power obtained in photovoltaic systems, and as a selecting method, we suggest the use of the Advanced Multi-Criteria Analysis based on the FRISCO formula. According to the case study on how to select the solar radiation hydrogen production system, the most convenient alternative is the alternative A4, namely the technical solution involving a hydrogen production system based on the electrolysis of water vapor obtained with concentrated solar thermal systems and electrical power obtained using concentrating photovoltaic systems.

  19. Multi-criteria analysis on how to select solar radiation hydrogen production system

    NASA Astrophysics Data System (ADS)

    Badea, G.; Naghiu, G. S.; Felseghi, R.-A.; Rǎboacǎ, S.; Aşchilean, I.; Giurca, I.

    2015-12-01

    The purpose of this article is to present a method of selecting hydrogen-production systems using the electric power obtained in photovoltaic systems, and as a selecting method, we suggest the use of the Advanced Multi-Criteria Analysis based on the FRISCO formula. According to the case study on how to select the solar radiation hydrogen production system, the most convenient alternative is the alternative A4, namely the technical solution involving a hydrogen production system based on the electrolysis of water vapor obtained with concentrated solar thermal systems and electrical power obtained using concentrating photovoltaic systems.

  20. Radiation exposure and safety practices during pediatric central line placement

    PubMed Central

    Saeman, Melody R.; Burkhalter, Lorrie S.; Blackburn, Timothy J.; Murphy, Joseph T.

    2015-01-01

    Purpose Pediatric surgeons routinely use fluoroscopy for central venous line (CVL) placement. We examined radiation safety practices and patient/surgeon exposure during fluoroscopic CVL. Methods Fluoroscopic CVL procedures performed by 11 pediatric surgeons in 2012 were reviewed. Fluoroscopic time (FT), patient exposure (mGy), and procedural data were collected. Anthropomorphic phantom simulations were used to calculate scatter and dose (mSv). Surgeons were surveyed regarding safety practices. Results 386 procedures were reviewed. Median FT was 12.8 seconds. Median patient estimated effective dose was 0.13 mSv. Median annual FT per surgeon was 15.4 minutes. Simulations showed no significant difference (p = 0.14) between reported exposures (median 3.5 mGy/min) and the modeled regression exposures from the C-arm default mode (median 3.4 mGy/min). Median calculated surgeon exposure was 1.5 mGy/year. Eight of 11 surgeons responded to the survey. Only three reported 100% lead protection and frequent dosimeter use. Conclusion We found non-standard radiation training, safety practices, and dose monitoring for the 11 surgeons. Based on simulations, the C-arm default setting was typically used instead of low dose. While most CVL procedures have low patient/surgeon doses, every effort should be used to minimize patient and occupational exposure, suggesting the need for formal hands-on training for non-radiologist providers using fluoroscopy. PMID:25837269

  1. Criteria for onsite transfers of radioactive material

    SciTech Connect

    Opperman, E.K.; Jackson, E.J.; Eggers, A.G.

    1992-12-31

    A general description of the requirements for making onsite transfers of radioactive material is provided in Chapter 2, along with the required sequencey of activities. Various criteria for package use are identified in Chapters 3-13. These criteria provide protection against undue radiation exposure. Package shielding, containment, and surface contamination requirements are established. Criteria for providing criticality safety are enumerated in Chapter 6. Criteria for providing hazards information are established in Chapter 13. A glossary is provided.

  2. Enhancing Credibility of Chemical Safety Studies: Emerging Consensus on Key Assessment Criteria

    PubMed Central

    Conrad, James W.; Becker, Richard A.

    2011-01-01

    Objectives We examined the extent to which consensus exists on the criteria that should be used for assessing the credibility of a scientific work, regardless of its funding source, and explored how these criteria might be implemented. Data sources Three publications, all presented at a session of the 2009 annual meeting of the Society for Risk Analysis, have proposed a range of criteria for evaluating the credibility of scientific studies. At least two other similar sets of criteria have recently been proposed elsewhere. Data extraction/synthesis In this article we review these criteria, highlight the commonalities among them, and integrate them into a list of 10 criteria. We also discuss issues inherent in any attempt to implement the criteria systematically. Conclusions Recommendations by many scientists and policy experts converge on a finite list of criteria for assessing the credibility of a scientific study without regard to funding source. These criteria should be formalized through a consensus process or a governmental initiative that includes discussion and pilot application of a system for reproducibly implementing them. Formal establishment of such a system should enable the debate regarding chemical studies to move beyond funding issues and focus on scientific merit. PMID:21163723

  3. 21 CFR 70.42 - Criteria for evaluating the safety of color additives.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... experiments to determine its safety, the Commissioner will advise a person who wishes to establish the safety of a color additive whether he believes the experiments planned will yield data adequate for...

  4. 21 CFR 70.42 - Criteria for evaluating the safety of color additives.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... experiments to determine its safety, the Commissioner will advise a person who wishes to establish the safety of a color additive whether he believes the experiments planned will yield data adequate for...

  5. 21 CFR 70.42 - Criteria for evaluating the safety of color additives.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... experiments to determine its safety, the Commissioner will advise a person who wishes to establish the safety of a color additive whether he believes the experiments planned will yield data adequate for...

  6. 21 CFR 70.42 - Criteria for evaluating the safety of color additives.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... experiments to determine its safety, the Commissioner will advise a person who wishes to establish the safety of a color additive whether he believes the experiments planned will yield data adequate for...

  7. Update on radiation safety and dose reduction in pediatric neuroradiology.

    PubMed

    Mahesh, Mahadevappa

    2015-09-01

    The number of medical X-ray imaging procedures is growing exponentially across the globe. Even though the overall benefit from medical X-ray imaging procedures far outweighs any associated risks, it is crucial to take all necessary steps to minimize radiation risks to children without jeopardizing image quality. Among the X-ray imaging studies, except for interventional fluoroscopy procedures, CT studies constitute higher dose and therefore draw considerable scrutiny. A number of technological advances have provided ways for better and safer CT imaging. This article provides an update on the radiation safety of patients and staff and discusses dose optimization in medical X-ray imaging within pediatric neuroradiology. PMID:26346142

  8. 49 CFR Appendix to Subpart H of... - Explanation of Pre-Authorization Safety Audit Evaluation Criteria for Non-North America-Domiciled...

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... Evaluation Criteria for Non-North America-Domiciled Motor Carriers Appendix to Subpart H of Part 385... America-Domiciled Motor Carriers I. General (a) FMCSA will perform a safety audit of each non-North...-North America-domiciled carrier's basic safety management controls. (b) The safety audit is a review...

  9. Radiation safety system (RSS) backbones: Design, engineering, fabrication and installation

    SciTech Connect

    Wilmarth, J.E.; Sturrock, J.C.; Gallegos, F.R.

    1998-12-01

    The Radiation Safety System (RSS) Backbones are part of an electrical/electronic/mechanical system insuring safe access and exclusion of personnel to areas at the Los Alamos Neutron Science Center (LANSCE) accelerator. The RSS Backbones control the safety fusible beam plugs which terminate transmission of accelerated ion beams in response to predefined conditions. Any beam or access fault of the backbone inputs will cause insertion of the beam plugs in the low energy beam transport. The Backbones serve the function of tying the beam plugs to the access control systems, beam spill monitoring systems and current-level limiting systems. In some ways the Backbones may be thought of as a spinal column with beam plugs at the head and nerve centers along the spinal column. The two Linac Backbone segments and experimental area segments form a continuous cable plant over 3,500 feet from beam plugs to the tip on the longest tail. The Backbones were installed in compliance with current safety standards, such as installation of the two segments in separate conduits or tray. Monitoring for ground-faults and input wiring verification was an added enhancement to the system. The system has the capability to be tested remotely.

  10. Radiation Safety System (RSS) backbones: Design, engineering, fabrication, and installation

    SciTech Connect

    Wilmarth, J. E.; Sturrock, J. C.; Gallegos, F. R.

    1998-12-10

    The Radiation Safety System (RSS) backbones are part of an electrical/electronic/mechanical system ensuring safe access and exclusion of personnel to areas at the Los Alamos Neutron Science Center (LANSCE) accelerator. The RSS backbones control the safety-fusible beam plugs which terminate transmission of accelerated ion beams in response to predefined conditions. Any beam or access fault of the backbone inputs will cause insertion of the beam plugs in the low-energy beam transport. The backbones serve the function of tying the beam plugs to the access control systems, beam spill monitoring systems and current-level limiting systems. In some ways the backbones may be thought of as a spinal column with beam plugs at the head and nerve centers along the spinal column. The two linac backbone segments and the experimental area segments form a continuous cable plant over 3500 feet from the beam plugs to the tip on the longest tail. The backbones were installed in compliance with current safety standards, such as installation of the two segments in separate conduits or tray. Monitoring for ground-faults and input wiring verification was an added enhancement to the system. The system has the capability to be tested remotely.

  11. Radiation Safety System (RSS) backbones: Design, engineering, fabrication, and installation

    NASA Astrophysics Data System (ADS)

    Wilmarth, J. E.; Sturrock, J. C.; Gallegos, F. R.

    1998-12-01

    The Radiation Safety System (RSS) backbones are part of an electrical/electronic/mechanical system ensuring safe access and exclusion of personnel to areas at the Los Alamos Neutron Science Center (LANSCE) accelerator. The RSS backbones control the safety-fusible beam plugs which terminate transmission of accelerated ion beams in response to predefined conditions. Any beam or access fault of the backbone inputs will cause insertion of the beam plugs in the low-energy beam transport. The backbones serve the function of tying the beam plugs to the access control systems, beam spill monitoring systems and current-level limiting systems. In some ways the backbones may be thought of as a spinal column with beam plugs at the head and nerve centers along the spinal column. The two linac backbone segments and the experimental area segments form a continuous cable plant over 3500 feet from the beam plugs to the tip on the longest tail. The backbones were installed in compliance with current safety standards, such as installation of the two segments in separate conduits or tray. Monitoring for ground-faults and input wiring verification was an added enhancement to the system. The system has the capability to be tested remotely.

  12. Radiation Safety System (RSS) backbones: Design, engineering, fabrication, and installation

    SciTech Connect

    Wilmarth, J.E.; Sturrock, J.C.; Gallegos, F.R.

    1998-12-01

    The Radiation Safety System (RSS) backbones are part of an electrical/electronic/mechanical system ensuring safe access and exclusion of personnel to areas at the Los Alamos Neutron Science Center (LANSCE) accelerator. The RSS backbones control the safety-fusible beam plugs which terminate transmission of accelerated ion beams in response to predefined conditions. Any beam or access fault of the backbone inputs will cause insertion of the beam plugs in the low-energy beam transport. The backbones serve the function of tying the beam plugs to the access control systems, beam spill monitoring systems and current-level limiting systems. In some ways the backbones may be thought of as a spinal column with beam plugs at the head and nerve centers along the spinal column. The two linac backbone segments and the experimental area segments form a continuous cable plant over 3500 feet from the beam plugs to the tip on the longest tail. The backbones were installed in compliance with current safety standards, such as installation of the two segments in separate conduits or tray. Monitoring for ground-faults and input wiring verification was an added enhancement to the system. The system has the capability to be tested remotely. {copyright} {ital 1998 American Institute of Physics.}

  13. Importance of Bladder Radioactivity for Radiation Safety in Nuclear Medicine

    PubMed Central

    Gültekin, Salih Sinan; Şahmaran, Turan

    2013-01-01

    Objective: Most of the radiopharmaceuticals used in nuclear medicine are excreted via the urinary system. This study evaluated the importance of a reduction in bladder radioactivity for radiation safety. Methods: The study group of 135 patients underwent several organ scintigraphies [40/135; thyroid scintigraphy (TS), 30/135; whole body bone scintigraphy (WBS), 35/135; myocardial perfusion scintigraphy (MPS) and 30/135; renal scintigraphy (RS)] by a technologist within 1 month. In full and empty conditions, static bladder images and external dose rate measurements at 0.25, 0.50, 1, 1.5 and 2 m distances were obtained and decline ratios were calculated from these two data sets. Results: External radiation dose rates were highest in patients undergoing MPS. External dose rates at 0.25 m distance for TS, TKS, MPS and BS were measured to be 56, 106, 191 and 72 μSv h-1 for full bladder and 29, 55, 103 and 37 μSv h-1 for empty bladder, respectively. For TS, WBS, MPS and RS, respectively, average decline ratios were calculated to be 52%, 55%, 53% and 54% in the scintigraphic assessment and 49%, 51%, 49%, 50% and 50% in the assessment with Geiger counter. Conclusion: Decline in bladder radioactivity is important in terms of radiation safety. Patients should be encouraged for micturition after each scintigraphic test. Spending time together with radioactive patients at distances less than 1 m should be kept to a minimum where possible. Conflict of interest:None declared. PMID:24416625

  14. 49 CFR Appendix C to Part 236 - Safety Assurance Criteria and Processes

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... improperly designed human-machine interface; installation and maintenance errors; and errors associated with... Applications: Specification and Demonstration of Reliability, Availability, Maintainability and Safety...

  15. PCES 2.0. Performance Criteria and Evaluation System v. 2.0

    SciTech Connect

    Jackson, L.L.

    1992-04-01

    The Performance Criteria and Evaluation System (PCES) was developed in order to make a data base of criteria accessible to radiation safety staff. The criteria included in the package are applicable to occupational radiation safety at DOE reactor and nonreactor nuclear facilities, but any data base of criteria may be created using the Criterion Data Base Utiliity (CDU). PCES assists personnel in carrying out oversight, line, and support activities.

  16. 49 CFR Appendix C to Part 236 - Safety Assurance Criteria and Processes

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    .... The product design must sufficiently incorporate human factors engineering that is appropriate to the... principles when designing and demonstrating the safety of products covered by subpart H or I of this part. In... associated with the design principle not followed. (1) System safety under normal operating conditions....

  17. 49 CFR Appendix C to Part 236 - Safety Assurance Criteria and Processes

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... results of system safety analyses provided in the RSPP, PSP, PTCIP, PTCDP, and PTCSP documents as appropriate. An analysis performed under this appendix must: (1) Address each of the safety principles of... system operation. Hazards categorized as unacceptable, which are determined by hazard analysis, must...

  18. Data base management system for a radiation safety program

    SciTech Connect

    McKetty, M.H.; Roach, D.M. )

    1991-03-01

    A data base management system (DBMS) has been developed that simplifies the retrieval of data concerning radioisotope use at a university and hospital. The system customizes software that is commercially available to perform several functions. Reports can be developed concerning receipt of radioactive materials, radioactive waste disposal, and research proposals submitted by investigators. Reports can be prepared that utilize the software's ability to perform numerical calculations. The main advantage of the DBMS is that it allows the easy retrieval of information that is used in the day-to-day operation of a radiation safety office; it also provides easy access and manipulation of data for the preparation of reports, budget proposals, and justifications for purchases.

  19. ACR Appropriateness Criteria Retreatment of Recurrent Head and Neck Cancer After Prior Definitive Radiation

    SciTech Connect

    McDonald, Mark W.; Lawson, Joshua; Garg, Madhur Kumar; Quon, Harry; Ridge, John A.; Saba, Nabil; Salama, Joseph K.; Smith, Richard V.; Yeung, Anamaria Reyna; Yom, Sue S.; Beitler, Jonathan J.

    2011-08-01

    Recurrent and second primary head-and-neck squamous cell carcinomas arising within or in close proximity to previously irradiated fields are a common clinical challenge. Whereas surgical salvage therapy is recommended for resectable disease, randomized data support the role of postoperative reirradiation in high-risk patients. Definitive reirradiation is an established approach for patients with recurrent disease who are medically or technically inoperable or decline radical surgery. The American College of Radiology Expert Panel on Head and Neck Cancer reviewed the relevant literature addressing re-treatment after prior definitive radiation and developed appropriateness criteria for representative clinical scenarios. Examples of unresectable recurrent disease and microscopic residual disease after salvage surgery were addressed. The panel evaluated the appropriateness of reirradiation, the integration of concurrent chemotherapy, radiation technique, treatment volume, dose, and fractionation. The panel emphasized the importance of patient selection and recommended evaluation and treatment at tertiary-care centers with a head-and-neck oncology team equipped with the resources and experience to manage the complexities and toxicities of re-treatment.

  20. Replanning Criteria and Timing Definition for Parotid Protection-Based Adaptive Radiation Therapy in Nasopharyngeal Carcinoma

    PubMed Central

    Yao, Wei-Rong; Xu, Shou-Ping; Liu, Bo; Cao, Xiu-Tang; Ren, Gang; Du, Lei; Zhou, Fu-Gen; Feng, Lin-Chun; Qu, Bao-Lin; Xie, Chuan-Bin; Ma, Lin

    2015-01-01

    The goal of this study was to evaluate real-time volumetric and dosimetric changes of the parotid gland so as to determine replanning criteria and timing for parotid protection-based adaptive radiation therapy in nasopharyngeal carcinoma. Fifty NPC patients were treated with helical tomotherapy; volumetric and dosimetric (Dmean, V1, and D50) changes of the parotid gland at the 1st, 6th, 11th, 16th, 21st, 26th, 31st, and 33rd fractions were evaluated. The clinical parameters affecting these changes were studied by analyses of variance methods for repeated measures. Factors influencing the actual parotid dose were analyzed by a multivariate logistic regression model. The cut-off values predicting parotid overdose were developed from receiver operating characteristic curves and judged by combining them with a diagnostic test consistency check. The median absolute value and percentage of parotid volume reduction were 19.51 cm3 and 35%, respectively. The interweekly parotid volume varied significantly (p < 0.05). The parotid Dmean, V1, and D50 increased by 22.13%, 39.42%, and 48.45%, respectively. The actual parotid dose increased by an average of 11.38% at the end of radiation therapy. Initial parotid volume, initial parotid Dmean, and weight loss rate are valuable indicators for parotid protection-based replanning. PMID:26793717

  1. 78 FR 28275 - Office of Commercial Space Transportation; Safety Approval Performance Criteria

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-14

    ... Federal Aviation Administration Office of Commercial Space Transportation; Safety Approval Performance... hypobaric chamber training for crew and space flight participants to experience and demonstrate knowledge of...), FAA Office of Commercial Space Transportation (AST), 800 Independence Avenue SW., Room 331,...

  2. 77 FR 58607 - Office of Commercial Space Transportation Safety Approval Performance Criteria

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-09-21

    ... Federal Aviation Administration Office of Commercial Space Transportation Safety Approval Performance..., Licensing and Evaluation Division (AST-200), FAA Office of Commercial Space Transportation (AST), 800... Space Transportation. BILLING CODE 4910-13-P...

  3. 10 CFR 35.50 - Training for Radiation Safety Officer.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... radioactivity, radiation biology, and radiation dosimetry; or (2)(i) Hold a master's or doctor's degree in... the use and measurement of radioactivity; (D) Radiation biology; and (E) Radiation dosimetry; and...

  4. 10 CFR 35.50 - Training for Radiation Safety Officer.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... radioactivity, radiation biology, and radiation dosimetry; or (2)(i) Hold a master's or doctor's degree in... the use and measurement of radioactivity; (D) Radiation biology; and (E) Radiation dosimetry; and...

  5. 10 CFR 35.50 - Training for Radiation Safety Officer.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... radioactivity, radiation biology, and radiation dosimetry; or (2)(i) Hold a master's or doctor's degree in... pertaining to the use and measurement of radioactivity; (D) Radiation biology; and (E) Radiation...

  6. 10 CFR 35.50 - Training for Radiation Safety Officer.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... radioactivity, radiation biology, and radiation dosimetry; or (2)(i) Hold a master's or doctor's degree in... to the use and measurement of radioactivity; (D) Radiation biology; and (E) Radiation dosimetry;...

  7. 10 CFR 35.50 - Training for Radiation Safety Officer.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... radioactivity, radiation biology, and radiation dosimetry; or (2)(i) Hold a master's or doctor's degree in... to the use and measurement of radioactivity; (D) Radiation biology; and (E) Radiation dosimetry;...

  8. Radiation safety in the nuclear medicine department: impact of the UK Ionising Radiations Regulations.

    PubMed

    Harding, L K

    1987-09-01

    The practice of nuclear medicine requires integration of radiation safety with patient care and radiopharmaceutical standards. Nationally there was useful discussion in the UK before the Ionising Radiations Regulations and Approved Code of Practice were published, although such consultation had been lacking when the Medicines Act was implemented. Most of the new considerations relating to nuclear medicine stem from Schedule 6 of the Regulations. Generally, the presence of a single patient does not require a controlled area. However, when several patients are present, or radiopharmaceuticals are being prepared prior to injection, a controlled area is required. Classification of workers is not likely to be required in a typical nuclear medicine department in the UK, although most parts of the nuclear medicine department will need to be controlled areas. These include the radiopharmacy, radionuclide dispensary, injection room, and imaging rooms if patients are injected in them. The importance of finger dose measurements is emphasised. Patient wards, however, need not be controlled areas. A particular concern in nuclear medicine was that patients should not need to be admitted to hospital merely to comply with legislation. This is possibly the case and clarification will probably be available when the Notes for Guidance are published. Most procedures in nuclear medicine departments will remain unchanged. Further information is required, however, on patient waiting rooms, handling flood sources, pregnancy, and breast feeding. Within the hospital, detailed and multidisciplinary discussion will need to take place within the forum of the radiation safety committee. PMID:3664186

  9. THE RADIATION SAFETY INFORMATION COMPUTATIONAL CENTER: A RESOURCE FOR REACTOR DOSIMETRY SOFTWARE AND NUCLEAR DATA

    SciTech Connect

    Kirk, Bernadette Lugue

    2009-01-01

    The Radiation Safety Information Computational Center (RSICC) was established in 1963 to collect and disseminate computational nuclear technology in the form of radiation transport, shielding and safety software and corresponding nuclear cross sections. Approximately 1700 nuclear software and data packages are in the RSICC collection, and the majority are applicable to reactor dosimetry.

  10. The Radiation Safety Information Computational Center:. a Resource for Reactor Dosimetry Software and Nuclear Data

    NASA Astrophysics Data System (ADS)

    Kirk, B. L.

    2009-08-01

    The Radiation Safety Information Computational Center (RSICC) was established in 1963 to collect and disseminate computational nuclear technology in the form of radiation transport, shielding and safety software and corresponding nuclear cross sections. Approximately 1700 nuclear software and data packages are in the RSICC collection, and the majority are applicable to reactor dosimetry.

  11. 49 CFR Appendix A to Subpart E of... - Explanation of Pre-Authorization Safety Audit Evaluation Criteria for Mexico-Domiciled Motor...

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 5 2011-10-01 2011-10-01 false Explanation of Pre-Authorization Safety Audit Evaluation Criteria for Mexico-Domiciled Motor Carriers A Appendix A to Subpart E of Part 365 Transportation Other Regulations Relating to Transportation (Continued) FEDERAL MOTOR CARRIER SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION FEDERAL...

  12. Instructor qualification for radiation safety training at a national laboratory

    SciTech Connect

    Trinoskey, P.A.

    1994-10-01

    Prior to 1993, Health Physics Training (HPT) was conducted by the Lawrence Livermore National Laboratory (LLNL) health physics group. The job requirements specified a Masters Degree and experience. In fact, the majority of Health Physicists in the group were certified by the American Board of Health Physics. Under those circumstances, it was assumed that individuals in the group were technically qualified and the HPT instructor qualification stated that. In late 1993, the Health Physics Group at the LLNL was restructured and the training function was assigned to the training group. Additional requirements for training were mandated by the Department of Energy (DOE), which would necessitate increasing the existing training staff. With the need to hire, and the policy of reassignment of employees during downsizing, it was imperative that formal qualification standards be developed for technical knowledge. Qualification standards were in place for instructional capability. In drafting the new training qualifications for instructors, the requirements of a Certified Health Physicists had to be modified due to supply and demand. Additionally, for many of the performance-based training courses, registration by the National Registry of Radiation Protection Technologists is more desirable. Flexibility in qualification requirements has been incorporated to meet the reality of ongoing training and the compensation for desirable skills of individuals who may not meet all the criteria. The qualification requirements for an instructor rely on entry-level requirements and emphasis on goals (preferred) and continuing development of technical and instructional capabilities.

  13. 10 CFR 72.104 - Criteria for radioactive materials in effluents and direct radiation from an ISFSI or MRS.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... radioactive materials, radon and its decay products excepted, to the general environment, (2) Direct radiation... 10 Energy 2 2012-01-01 2012-01-01 false Criteria for radioactive materials in effluents and direct...) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE,...

  14. 10 CFR 72.104 - Criteria for radioactive materials in effluents and direct radiation from an ISFSI or MRS.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... radioactive materials, radon and its decay products excepted, to the general environment, (2) Direct radiation... 10 Energy 2 2011-01-01 2011-01-01 false Criteria for radioactive materials in effluents and direct...) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE,...

  15. 10 CFR 72.104 - Criteria for radioactive materials in effluents and direct radiation from an ISFSI or MRS.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Criteria for radioactive materials in effluents and direct radiation from an ISFSI or MRS. 72.104 Section 72.104 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...

  16. 10 CFR 72.104 - Criteria for radioactive materials in effluents and direct radiation from an ISFSI or MRS.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... radioactive materials, radon and its decay products excepted, to the general environment, (2) Direct radiation... 10 Energy 2 2014-01-01 2014-01-01 false Criteria for radioactive materials in effluents and direct...) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE,...

  17. 10 CFR 72.104 - Criteria for radioactive materials in effluents and direct radiation from an ISFSI or MRS.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Criteria for radioactive materials in effluents and direct radiation from an ISFSI or MRS. 72.104 Section 72.104 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...

  18. 76 FR 30232 - Office of Commercial Space Transportation Safety Approval Performance Criteria

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-05-24

    ... Federal Aviation Administration Office of Commercial Space Transportation Safety Approval Performance... associated with suborbital space flight. The reduced gravity levels are: --0.00 g 0.05 g for 17 continuous... Division (AST-200), FAA Office of Commercial Space Transportation (AST), 800 Independence Avenue, SW.,...

  19. Neuro-oncology update: radiation safety and nursing care during interstitial brachytherapy

    SciTech Connect

    Randall, T.M.; Drake, D.K.; Sewchand, W.

    1987-12-01

    Radiation control and safety are major considerations for nursing personnel during the care of patients receiving brachytherapy. Since the theory and practice of radiation applications are not part of the routine curriculum of nursing programs, the education of nurses and other health care professionals in radiation safety procedures is important. Regulatory agencies recommend that an annual safety course be given to all persons frequenting, using, or associated with patients containing radioactive materials. This article presents pertinent aspects of the principles and procedures of radiation safety, the role of personnel dose-monitoring devices, and the value of additional radiation control features, such as a lead cubicle, during interstitial brain implants. One institution's protocol and procedures for the care of high-intensity iridium-192 brain implants are discussed. Preoperative teaching guidelines and nursing interventions included in the protocol focus on radiation control principles.

  20. Effects of gamma radiation on raspberries: safety and quality issues.

    PubMed

    Verde, S Cabo; Trigo, M J; Sousa, M B; Ferreira, A; Ramos, A C; Nunes, I; Junqueira, C; Melo, R; Santos, P M P; Botelho, M L

    2013-01-01

    There is an ever-increasing global demand from consumers for high-quality foods with major emphasis placed on quality and safety attributes. One of the main demands that consumers display is for minimally processed, high-nutrition/low-energy natural foods with no or minimal chemical preservatives. The nutritional value of raspberry fruit is widely recognized. In particular, red raspberries are known to demonstrate a strong antioxidant capacity that might prove beneficial to human health by preventing free radical-induced oxidative stress. However, food products that are consumed raw, are increasingly being recognized as important vehicles for transmission of human pathogens. Food irradiation is one of the few technologies that address both food quality and safety by virtue of its ability to control spoilage and foodborne pathogenic microorganisms without significantly affecting sensory or other organoleptic attributes of the food. Food irradiation is well established as a physical, nonthermal treatment (cold pasteurization) that processes foods at or nearly at ambient temperature in the final packaging, reducing the possibility of cross contamination until the food is actually used by the consumer. The aim of this study was to evaluate effects of gamma radiation on raspberries in order to assess consequences of irradiation. Freshly packed raspberries (Rubus idaeus L.) were irradiated in a (60)Co source at several doses (0.5, 1, or 1.5 kGy). Bioburden, total phenolic content, antioxidant activity, physicochemical properties such as texture, color, pH, soluble solids content, and acidity, and sensorial parameters were assessed before and after irradiation and during storage time up to 14 d at 4°C. Characterization of raspberries microbiota showed an average bioburden value of 10(4) colony-forming units (CFU)/g and a diverse microbial population predominantly composed of two morphological types (gram-negative, oxidase-negative rods, 35%, and filamentous fungi, 41

  1. Criteria for the Research Institute for Fragrance Materials, Inc. (RIFM) safety evaluation process for fragrance ingredients.

    PubMed

    Api, A M; Belsito, D; Bruze, M; Cadby, P; Calow, P; Dagli, M L; Dekant, W; Ellis, G; Fryer, A D; Fukayama, M; Griem, P; Hickey, C; Kromidas, L; Lalko, J F; Liebler, D C; Miyachi, Y; Politano, V T; Renskers, K; Ritacco, G; Salvito, D; Schultz, T W; Sipes, I G; Smith, B; Vitale, D; Wilcox, D K

    2015-08-01

    The Research Institute for Fragrance Materials, Inc. (RIFM) has been engaged in the generation and evaluation of safety data for fragrance materials since its inception over 45 years ago. Over time, RIFM's approach to gathering data, estimating exposure and assessing safety has evolved as the tools for risk assessment evolved. This publication is designed to update the RIFM safety assessment process, which follows a series of decision trees, reflecting advances in approaches in risk assessment and new and classical toxicological methodologies employed by RIFM over the past ten years. These changes include incorporating 1) new scientific information including a framework for choosing structural analogs, 2) consideration of the Threshold of Toxicological Concern (TTC), 3) the Quantitative Risk Assessment (QRA) for dermal sensitization, 4) the respiratory route of exposure, 5) aggregate exposure assessment methodology, 6) the latest methodology and approaches to risk assessments, 7) the latest alternatives to animal testing methodology and 8) environmental risk assessment. The assessment begins with a thorough analysis of existing data followed by in silico analysis, identification of 'read across' analogs, generation of additional data through in vitro testing as well as consideration of the TTC approach. If necessary, risk management may be considered. PMID:25510979

  2. ASCO steam generators operating experience. Safety criteria for defect management and effectiveness of preventive measures

    SciTech Connect

    Toribio, E.L.

    1997-02-01

    ASCO NPP is a two W-PWR 930 Mwe Units. Each Unit is provided with three Westinghouse Model D3 steam generators which are of preheater type and Inconel 600 MA as tube material. The Secondary side was designed and erected with copper alloys. Unit I: 81.072 EFPH, and Unit II: 69.720 EFPH. The results of the Eddy Currents Inspections performed during the first refueling outage showed Denting at tube support plates and PWSCC at roll transition zone in Unit I and Denting in Unit II. Later inspections showed other types of damages, such as: (1) ODSCC at tube support plates intersections. (2) Circumferential cracks OD and ID at roll transition zone. (3) Wear at antivibration bars and preheater baffles level. Consequently, in order to limit the plugging rate, A.N. ASCO decided to license new plugging criteria in addition to the 40% depth criterion included in Technical Specification. The new licensing criteria and surveillance requirements, varying with tube zone, are explained in the paper.

  3. Critical Characteristics of Radiation Detection System Components to be Dedicated for use in Safety Class and Safety Significant System

    SciTech Connect

    DAVIS, S.J.

    2000-05-25

    This document identifies critical characteristics of components to be dedicated for use in Safety Class (SC) or Safety Significant (SS) Systems, Structures, or Components (SSCs). This document identifies the requirements for the components of the common radiation area monitor alarm in the WESF pool cell. These are procured as Commercial Grade Items (CGI), with the qualification testing and formal dedication to be performed at the Waste Encapsulation Storage Facility (WESF), in safety class, safety significant systems. System modifications are to be performed in accordance with the instructions provided on ECN 658230. Components for this change are commercially available and interchangeable with the existing alarm configuration This document focuses on the operational requirements for alarm, declaration of the safety classification, identification of critical characteristics, and interpretation of requirements for procurement. Critical characteristics are identified herein and must be verified, followed by formal dedication, prior to the components being used in safety related applications.

  4. Inter-comparison of safety culture within selected practices in Ghana utilising ionising radiation.

    PubMed

    Faanu, A; Schandorf, C; Darko, E O; Boadu, M; Emi-Reynolds, G; Awudu, A R; Gyekye, P K; Kpeglo, D O

    2010-12-01

    The safety culture of selected practices and facilities in Ghana utilising radiation sources or radiation emitting devices has been assessed using a performance indicator, which provided status information on management and operating staff commitment to safety. The questionnaire was based on the following broad areas: general safety considerations, safety policy at the facility level, safety practices at the facility level, definition of responsibility, staff training, safety of the physical structure of the facility and the emergency plans. The analysis showed that the percentage levels of commitment to safety for the respective practices are as follows: conventional radiography, 23.3-90.0%; research reactor, 73.3%; gamma irradiation facility, 53.3%; radiotherapy, 76.7%; X-ray scanner, 80.0%; gamma scanner, 76.7%; industrial radiography 86.7% and nuclear density practice, 78%. None of the practices or facilities was able to satisfy all the requirements that will ensure a 100% level of safety culture. PMID:20699247

  5. A Multi-Criteria Decision Analysis Model to Assess the Safety of Botanicals Utilizing Data on History of Use

    PubMed Central

    Neely, T.; Walsh-Mason, B.; Russell, P.; Horst, A. Van Der; O’Hagan, S.; Lahorkar, P.

    2011-01-01

    Botanicals (herbal materials and extracts) are widely used in traditional medicines throughout the world. Many have an extensive history of safe use over several hundreds of years. There is now a growing consumer interest in food and cosmetic products, which contain botanicals. There are many publications describing the safety assessment approaches for botanicals, based on the history of safe use. However, they do not define what constitutes a history of safe use, a decision that is ultimately a subjective one. The multi-criteria decision analysis (MCDA), is a model that has been developed, which assesses the safety of botanical ingredients using a history of use approach. The model evaluates the similarity of the botanical ingredient of interest to its historic counterpart – the comparator, the evidence supporting the history of use, and any evidence of concern. The assessment made is whether a botanical ingredient is as safe as its comparator botanical, which has a history of use. In order to establish compositional similarity between the botanical ingredient and its comparator, an analytical ‘similarity scoring’ approach has been developed. Applicability of the model is discussed with an example, Brahmi ( Bacopa monnieri). This evolution of the risk assessment of botanicals gives an objective, transparent, and transferable safety assessment approach. PMID:22025816

  6. Ionizing and Nonionizing Radiation Protection. Module SH-35. Safety and Health.

    ERIC Educational Resources Information Center

    Center for Occupational Research and Development, Inc., Waco, TX.

    This student module on ionizing and nonionizing radiation protection is one of 50 modules concerned with job safety and health. This module describes various types of ionizing and nonionizing radiation, and the situations in the workplace where potential hazards from radiation may exist. Following the introduction, 13 objectives (each keyed to a…

  7. Radiation safety analysis of the ISS bone densitometer

    NASA Astrophysics Data System (ADS)

    Todd, Paul; Vellinger, John C.; Barton, Kenneth; Faget, Paul

    A Bone Densitometer (BD) has been developed for installation on the International Space Station (ISS) with delivery by the Space-X Dragon spacecraft planned for mid 2014. After initial tests on orbit the BD will be used in longitudinal measurements of bone mineral density in experimental mice as a means of evaluating countermeasures to bone loss. The BD determines bone mineral density (and other radiographic parameters) by dual energy x-ray absorptiometry (DEXA). In a single mouse DEXA “scan” its 80 kV x-ray tube is operated for 15 seconds at 35 kV and 3 seconds at 80 kV in four repetitions, giving the subject a total dose of 2.5 mSv. The BD is a modification of a commercial mouse DEXA product known as PIXImus(TM). Before qualifying the BD for utilization on ISS it was necessary to evaluate its radiation safety features and any level of risk to ISS crew members. The BD design reorients the PIXImus so that it fits in an EXPRESS locker on ISS with the x-ray beam directed into the crew aisle. ISS regulation SSP 51700 considers the production of ionizing radiation to be a catastrophic-level hazard. Accidental exposure is prevented by three independent levels of on-off control as required for a catastrophic hazard. The ALARA (As Low as Reasonably Achievable) principle was applied to the BD hazard just as would be done on the ground, so deliberate exposure is limited by lead shielding according to ALARA. Hot spots around the BD were identified by environmental dosimetry using a Ludlum 9DP pressurized ionization chamber survey meter. Various thicknesses of lead were applied to the BD housing in areas where highest dose-per-scan readings were made. It was concluded that 0.4 mm of lead shielding at strategic locations, adding only a few kg of mass to the payload, would accomplish ALARA. With shielding in place the BD now exposes a crew member floating 40 cm away to less than 0.08 microSv per mouse scan. There is an upper limit of 20 scans per day, or 1.6 microSv per day

  8. Radiation Safety Training for Industrial Irradiators: What Are We Trying To Accomplish?

    NASA Astrophysics Data System (ADS)

    Smith, M. A.

    1998-06-01

    Radiation safety training at an industrial irradiator facility takes a different approach than the traditional methods and topics used at other facilities. Where the more routine industrial radiation users focus on standard training topics of contamination control, area surveys, and the traditional dogma of time, distance, and shielding, radiation safety in an industrial irradiation facility must be centered on preventing accidents. Because the primary methods for accomplishing that goal are engineering approaches such as safety system interlocks, training provided to facility personnel should address system operation and emergency actions. This presents challenges in delivering radiation safety to an audience of varied educational and technical background where little to no commercially available training material specific to this type of operation exists.

  9. Convex reformulation of biologically-based multi-criteria intensity-modulated radiation therapy optimization including fractionation effects

    NASA Astrophysics Data System (ADS)

    Hoffmann, Aswin L.; den Hertog, Dick; Siem, Alex Y. D.; Kaanders, Johannes H. A. M.; Huizenga, Henk

    2008-11-01

    Finding fluence maps for intensity-modulated radiation therapy (IMRT) can be formulated as a multi-criteria optimization problem for which Pareto optimal treatment plans exist. To account for the dose-per-fraction effect of fractionated IMRT, it is desirable to exploit radiobiological treatment plan evaluation criteria based on the linear-quadratic (LQ) cell survival model as a means to balance the radiation benefits and risks in terms of biologic response. Unfortunately, the LQ-model-based radiobiological criteria are nonconvex functions, which make the optimization problem hard to solve. We apply the framework proposed by Romeijn et al (2004 Phys. Med. Biol. 49 1991-2013) to find transformations of LQ-model-based radiobiological functions and establish conditions under which transformed functions result in equivalent convex criteria that do not change the set of Pareto optimal treatment plans. The functions analysed are: the LQ-Poisson-based model for tumour control probability (TCP) with and without inter-patient heterogeneity in radiation sensitivity, the LQ-Poisson-based relative seriality s-model for normal tissue complication probability (NTCP), the equivalent uniform dose (EUD) under the LQ-Poisson model and the fractionation-corrected Probit-based model for NTCP according to Lyman, Kutcher and Burman. These functions differ from those analysed before in that they cannot be decomposed into elementary EUD or generalized-EUD functions. In addition, we show that applying increasing and concave transformations to the convexified functions is beneficial for the piecewise approximation of the Pareto efficient frontier.

  10. Critical Characteristics of Radiation Detection System Components to be Dedicated for use in Safety Class and Safety Significant System

    SciTech Connect

    DAVIS, S.J.

    2000-12-28

    This document identifies critical characteristics of components to be dedicated for use in Safety Significant (SS) Systems, Structures, or Components (SSCs). This document identifies the requirements for the components of the common, radiation area, monitor alarm in the WESF pool cell. These are procured as Commercial Grade Items (CGI), with the qualification testing and formal dedication to be performed at the Waste Encapsulation Storage Facility (WESF) for use in safety significant systems. System modifications are to be performed in accordance with the approved design. Components for this change are commercially available and interchangeable with the existing alarm configuration This document focuses on the operational requirements for alarm, declaration of the safety classification, identification of critical characteristics, and interpretation of requirements for procurement. Critical characteristics are identified herein and must be verified, followed by formal dedication, prior to the components being used in safety related applications.

  11. Concepts of radiation safety and protection: Beyond BEIR V

    SciTech Connect

    Farman, A.G. )

    1991-01-01

    The publication of an updated report on the biological effects of ionizing radiation (BEIR V) has focused new attention on the potential hazards associated with the use of low doses of ionizing radiation for diagnostic purposes. This article reviews the BEIR V report findings and suggests methods for reducing the risks to dental patients and the operators of dental x-ray equipment.

  12. Radiation safety audit of a high volume Nuclear Medicine Department

    PubMed Central

    Jha, Ashish Kumar; Singh, Abhijith Mohan; Shetye, Bhakti; Shah, Sneha; Agrawal, Archi; Purandare, Nilendu Chandrakant; Monteiro, Priya; Rangarajan, Venkatesh

    2014-01-01

    Introduction: Professional radiation exposure cannot be avoided in nuclear medicine practices. It can only be minimized up to some extent by implementing good work practices. Aim and Objectives: The aim of our study was to audit the professional radiation exposure and exposure rate of radiation worker working in and around Department of nuclear medicine and molecular imaging, Tata Memorial Hospital. Materials and Methods: We calculated the total number of nuclear medicine and positron emission tomography/computed tomography (PET/CT) procedures performed in our department and the radiation exposure to the radiation professionals from year 2009 to 2012. Results: We performed an average of 6478 PET/CT scans and 3856 nuclear medicine scans/year from January 2009 to December 2012. The average annual whole body radiation exposure to nuclear medicine physician, technologist and nursing staff are 1.74 mSv, 2.93 mSv and 4.03 mSv respectively. Conclusion: Efficient management and deployment of personnel is of utmost importance to optimize radiation exposure in a high volume nuclear medicine setup in order to work without anxiety of high radiation exposure. PMID:25400361

  13. Radiation safety for anaesthesia providers in the orthopaedic operating room.

    PubMed

    Rhea, E B; Rogers, T H; Riehl, J T

    2016-04-01

    In many orthopaedic operating rooms, anaesthesia providers routinely wear lead aprons for protection from radiation, but some studies have questioned whether this is needed. We conducted a systematic review to identify studies that measured the amount of radiation that anaesthetists were exposed to in the orthopaedic operating room. Multiple studies have shown that at 1.5 m from the source of radiation, anaesthetists received no radiation, or amounts so small that a person would have to be present in an unreasonable number of operations to receive cumulative doses of any significance. Radiation doses at this distance were often at the limits of the sensitivity of the measuring dosimeter. We question the need to wear lead protection for anaesthesia providers who are routinely at 1.5 m or a greater distance from standard fluoroscopy units. PMID:26874074

  14. The Radiation Safety Information Computational Center (RSICC): A Resource for Nuclear Science Applications

    SciTech Connect

    Kirk, Bernadette Lugue

    2009-01-01

    The Radiation Safety Information Computational Center (RSICC) has been in existence since 1963. RSICC collects, organizes, evaluates and disseminates technical information (software and nuclear data) involving the transport of neutral and charged particle radiation, and shielding and protection from the radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste management. RSICC serves over 12,000 scientists and engineers from about 100 countries.

  15. Radon in the Workplace: the Occupational Safety and Health Administration (OSHA) Ionizing Radiation Standard.

    PubMed

    Lewis, Robert K

    2016-10-01

    On 29 December 1970, the Occupational Safety and Health Act of 1970 established the Occupational Safety and Health Administration (OSHA). This article on OSHA, Title 29, Part 1910.1096 Ionizing Radiation standard was written to increase awareness of the employer, the workforce, state and federal governments, and those in the radon industry who perform radon testing and radon mitigation of the existence of these regulations, particularly the radon relevant aspect of the regulations. This review paper was also written to try to explain what can sometimes be complicated regulations. As the author works within the Radon Division of the Pennsylvania Department of Environmental Protection, Bureau of Radiation Protection, the exclusive focus of the article is on radon. The 1910.1096 standard obviously covers many other aspects of radiation and radiation safety in the work place. PMID:27575350

  16. Provisional standards of radiation safety of flight personnel and passengers in air transport of the civil aviation

    NASA Technical Reports Server (NTRS)

    1977-01-01

    Provisional standards for radiation affecting passenger aircraft are considered. Agencies responsible for seeing that the regulations are enforced are designated while radiation sources and types of radiation are defined. Standard levels of permissible radiation are given and conditions for radiation safety are discussed. Dosimetric equipment on board aircraft is delineated and regulation effective dates are given.

  17. Assessment of radiation safety awareness among nuclear medicine nurses: a pilot study

    NASA Astrophysics Data System (ADS)

    Yunus, N. A.; Abdullah, M. H. R. O.; Said, M. A.; Ch'ng, P. E.

    2014-11-01

    All nuclear medicine nurses need to have some knowledge and awareness on radiation safety. At present, there is no study to address this issue in Malaysia. The aims of this study were (1) to determine the level of knowledge and awareness on radiation safety among nuclear medicine nurses at Putrajaya Hospital in Malaysia and (2) to assess the effectiveness of a training program provided by the hospital to increase the knowledge and awareness of the nuclear medicine nurses. A total of 27 respondents attending a training program on radiation safety were asked to complete a questionnaire. The questionnaire consists 16 items and were categorized into two main areas, namely general radiation knowledge and radiation safety. Survey data were collected before and after the training and were analyzed using descriptive statistics and paired sample t-test. Respondents were scored out of a total of 16 marks with 8 marks for each area. The findings showed that the range of total scores obtained by the nuclear medicine nurses before and after the training were 6-14 (with a mean score of 11.19) and 13-16 marks (with a mean score of 14.85), respectively. Findings also revealed that the mean score for the area of general radiation knowledge (7.59) was higher than that of the radiation safety (7.26). Currently, the knowledge and awareness on radiation safety among the nuclear medicine nurses are at the moderate level. It is recommended that a national study be conducted to assess and increase the level of knowledge and awareness among all nuclear medicine nurses in Malaysia.

  18. Quality and safety of medication use in primary care: consensus validation of a new set of explicit medication assessment criteria and prioritisation of topics for improvement

    PubMed Central

    2012-01-01

    Background Addressing the problem of preventable drug related morbidity (PDRM) in primary care is a challenge for health care systems internationally. The increasing implementation of clinical information systems in the UK and internationally provide new opportunities to systematically identify patients at risk of PDRM for targeted medication review. The objectives of this study were (1) to develop a set of explicit medication assessment criteria to identify patients with sub-optimally effective or high-risk medication use from electronic medical records and (2) to identify medication use topics that are perceived by UK primary care clinicians to be priorities for quality and safety improvement initiatives. Methods For objective (1), a 2-round consensus process based on the RAND/UCLA Appropriateness Method (RAM) was conducted, in which candidate criteria were identified from the literature and scored by a panel of 10 experts for 'appropriateness' and 'necessity'. A set of final criteria was generated from candidates accepted at each level. For objective (2), thematically related final criteria were clustered into 'topics', from which a panel of 26 UK primary care clinicians identified priorities for quality improvement in a 2-round Delphi exercise. Results (1) The RAM process yielded a final set of 176 medication assessment criteria organised under the domains 'quality' and 'safety', each classified as targeting 'appropriate/necessary to do' (quality) or 'inappropriate/necessary to avoid' (safety) medication use. Fifty-two final 'quality' assessment criteria target patients with unmet indications, sub-optimal selection or intensity of beneficial drug treatments. A total of 124 'safety' assessment criteria target patients with unmet needs for risk-mitigating agents, high-risk drug selection, excessive dose or duration, inconsistent monitoring or dosing instructions. (2) The UK Delphi panel identified 11 (23%) of 47 scored topics as 'high priority' for quality

  19. What Parents Should Know about Medical Radiation Safety

    MedlinePlus

    ... type of study can be misleading and comparing estimated doses for different exams is confusing. One way ... from different sources using millisievert units (mSv). Source Estimated effective dose (mSv) Natural background radiation.............................................. 3 mSv/ ...

  20. Radiation Dose and Safety in Cardiac Computed Tomography

    PubMed Central

    Gerber, Thomas C; Kantor, Birgit; McCollough, Cynthia H.

    2009-01-01

    Synopsis As a result of the changes in utilization of imaging procedures that rely on ionizing radiation, the collective dose has increased by over 700% and the annual per-capita dose, by almost 600% over recent years. It is certainly possible that this growing use may have significant effects on public health. Although there are uncertainties related to the accuracy of calculated radiation exposure and the estimated biologic risk, there are measures that can be taken to reduce any potential risks while maintaining diagnostic accuracy. This article will review the existing data regarding biological hazards of radiation exposure associated to medical diagnostic testing, the methodology used to estimate radiation exposure and the measures that can be taken to effectively reduce it. PMID:19766923

  1. Safety of {sup 90}Y Radioembolization in Patients Who Have Undergone Previous External Beam Radiation Therapy

    SciTech Connect

    Lam, Marnix G.E.H.; Abdelmaksoud, Mohamed H.K.; Chang, Daniel T.; Eclov, Neville C.; Chung, Melody P.; Koong, Albert C.; Louie, John D.; Sze, Daniel Y.

    2013-10-01

    Purpose: Previous external beam radiation therapy (EBRT) is theoretically contraindicated for yttrium-90 ({sup 90}Y) radioembolization (RE) because the liver has a lifetime tolerance to radiation before becoming vulnerable to radiation-induced liver disease. We analyzed the safety of RE as salvage treatment in patients who had previously undergone EBRT. Methods and Materials: Between June 2004 and December 2010, a total of 31 patients who had previously undergone EBRT were treated with RE. Three-dimensional treatment planning with dose–volume histogram (DVH) analysis of the liver was used to calculate the EBRT liver dose. Liver-related toxicities including RE-induced liver disease (REILD) were reviewed and classified according to Common Terminology Criteria for Adverse Events version 4.02. Results: The mean EBRT and RE liver doses were 4.40 Gy (range, 0-23.13 Gy) and 57.9 Gy (range, 27.0-125.9 Gy), respectively. Patients who experienced hepatotoxicity (≥grade2; n=12) had higher EBRT mean liver doses (7.96 ± 8.55 Gy vs 1.62 ± 3.39 Gy; P=.037), the only independent predictor in multivariate analysis. DVH analysis showed that the fraction of liver exposed to ≥30 Gy (V30) was the strongest predictor of hepatotoxicity (10.14% ± 12.75% vs 0.84% ± 3.24%; P=.006). All patients with V30 >13% experienced hepatotoxicity. Fatal REILD (n=2) occurred at the 2 highest EBRT mean liver doses (20.9 Gy and 23.1 Gy) but also at the highest cumulative liver doses (91.8 Gy and 149 Gy). Conclusions: Prior exposure of the liver to EBRT may lead to increased liver toxicity after RE treatment, depending on fractional liver exposure and dose level. The V30 was the strongest predictor of toxicity. RE appears to be safe for the treatment of hepatic malignancies only in patients who have had limited hepatic exposure to prior EBRT.

  2. MOX LTA Fuel Cycle Analyses: Nuclear and Radiation Safety

    SciTech Connect

    Pavlovitchev, A.M.

    2001-09-28

    Tasks of nuclear safety assurance for storage and transport of fresh mixed uranium-plutonium fuel of the VVER-1000 reactor are considered in the view of 3 MOX LTAs introduction into the core. The precise code MCU that realizes the Monte Carlo method is used for calculations.

  3. Radiation dose assessment methodology and preliminary dose estimates to support US Department of Energy radiation control criteria for regulated treatment and disposal of hazardous wastes and materials

    SciTech Connect

    Aaberg, R.L.; Baker, D.A.; Rhoads, K.; Jarvis, M.F.; Kennedy, W.E. Jr.

    1995-07-01

    This report provides unit dose to concentration levels that may be used to develop control criteria for radionuclide activity in hazardous waste; if implemented, these criteria would be developed to provide an adequate level of public and worker health protection, for wastes regulated under U.S, Environmental Protection Agency (EPA) requirements (as derived from the Resource Conservation and Recovery Act [RCRA] and/or the Toxic Substances Control Act [TSCA]). Thus, DOE and the US Nuclear Regulatory Commission can fulfill their obligation to protect the public from radiation by ensuring that such wastes are appropriately managed, while simultaneously reducing the current level of dual regulation. In terms of health protection, dual regulation of very small quantities of radionuclides provides no benefit.

  4. [Experience of justification of hygienic standards of food safety with the use of criteria for the risk population health].

    PubMed

    Zaytseva, N V; Tutelyan, V A; Shur, P Z; Khotimchenko, S A; Sheveleva, S A

    2014-01-01

    In the article there is presented the experience of justification of hygienic standards of food safety with the use of criteria for the risk for population health. Health risk assessment under the impact of tetracyclines with food showed that the content of residual amounts of these antibiotics at the level of 10 mg/kg (permissible residual tetracycline accepted in Customs Union Member Countries (CUMC) will not increase the risk to public health, including the most sensitive groups of the population. The assessment ofthe health risk associated with the receipt of ractopamine with food, showed that eating foods containing ractopamine at ADI level (0-1 mg/kg body weight), and even at the limit of quantification levels in meat products, is inadmissible because of unacceptable risk of functional disorders and diseases of the cardiovascular system. The results of the substantiation of the permissible levels of nitrates content in crop production showed that at the level of exposure according to hygienic standards established in the CUMC as at the recommended and actual consumption levels of products ofplant origin, the health risk as carcinogenic and non-carcinogenic, does not exceed acceptable levels. The results of the assessment of the risk associated with the permissible levels of L. monocytogenes in certain food groups showed that an exposure level of hygienic standards established in the CUMC, standards of Codex Alimentarius Commission and EU documents (before release to the market by the manufacturer) the health risk does not exceed the maximum permissible level of the appearance of serious diseases. Adoption of standards of Codex Alimentarius Commission and the EU (for handling products in the market) is not acceptable because it can lead to an unacceptable risk of listeriosis for the population of the Russian Federation as a whole, and for the most sensitive groups. PMID:25831934

  5. US Department of Energy standardized radiation safety training

    SciTech Connect

    Trinoskey, P.A.

    1997-02-01

    The following working groups were formed under the direction of a radiological training coordinator: managers, supervisors, DOE auditors, ALARA engineers/schedulers/planners, radiological control personnel, radiation-generating device operators, emergency responders, visitors, Pu facilities, U facilities, tritium facilities, accelerator facilities, biomedical researchers. General courses for these groups are available, now or soon, in the form of handbooks.

  6. Radiation Belt Storm Probes (RBSP) Payload Safety Introduction Briefing

    NASA Technical Reports Server (NTRS)

    Loftin, Chuck; Lampert, Dianna; Herrburger, Eric; Smith, Clay; Hill, Stuart; VonMehlem, Judi

    2008-01-01

    Mission of the Geospace Radiation Belt Storm Probes (RBSP) is: Gain s cientific understanding (to the point of predictability) of how populations of relativistic electrons and ions in space form or change in response to changes in solar activity and the solar wind.

  7. Academic training in radiation safety awareness and practice among Iranian residents/fellows

    PubMed Central

    Safi, Morteza; Aerab-Sheibani, Hossein; Namazi, Mohammad Hassan; Vakili, Hossein; Saadat, Habibollah

    2014-01-01

    Objective To determine the current state of radiation safety awareness and practice among Iranian radiology/cardiology residents. Methods In this cross-sectional study, 725 Iranian cardiology/radiology fellows/residents (685 residents and 40 fellows) were studied. Radiation safety awareness and practice were assessed using a 13-item survey questionnaire. Based on academic trainings provided in their medical centres, the subjects were divided into two groups (trained vs untrained). Results Trained residents/fellows had better performance compared with untrained ones regarding awareness of radiation dealing instructions, knowing safety experts of their centres (43.8% vs 20.1%, p<0.001) and their contact information (38.4% vs 11.4%, p<0.001), date of the last CBC (complete blood count) checking (15.1% vs 2.5%, p<0.001), use of lead glass (61.6% vs 41.8%, p=0.003), apron (94.5% vs 90%, p=0.016) and radiation shield (71.2% vs 46.2%, p<0.001). Conclusions Awareness/practice of Iranian cardiology/radiology residents/fellows about radiation exposure safety issues is not acceptable currently. Those who received formal training courses at their academic centres about the safety measures had significantly better knowledge compared with those who did not. It is suggested that radiation safety training be offered at the beginning of residency/fellowship for residents/fellows in a comprehensive and uniform way throughout medical universities. PMID:27326189

  8. Radiation safety aspects of commercial high-speed flight transportation

    NASA Astrophysics Data System (ADS)

    Wilson, John W.; Nealy, John E.; Cucinotta, Francis A.; Shinn, Judy L.; Hajnal, Ferenc; Reginatto, Marcel; Goldhagen, Paul

    1995-05-01

    High-speed commercial flight transportation is being studied for intercontinental operations in the 21st century, the projected operational characteristics for these aircraft are examined, the radiation environment as it is now known is presented, and the relevant health issues are discussed. Based on a critical examination of the data, a number of specific issues need to be addressed to ensure an adequate knowledge of the ionizing radiation health risks of these aircraft operations. Large uncertainties in our knowledge of the physical fields for high-energy neutrons and multiply-charged ion components need to be reduced. Improved methods for estimating risks in prenatal exposure need to be developed. A firm basis for solar flare monitoring and forecasting needs to be developed with means of exposure abatement.

  9. Radiation safety aspects of commercial high-speed flight transportation

    NASA Technical Reports Server (NTRS)

    Wilson, John W.; Nealy, John E.; Cucinotta, Francis A.; Shinn, Judy L.; Hajnal, Ferenc; Reginatto, Marcel; Goldhagen, Paul

    1995-01-01

    High-speed commercial flight transportation is being studied for intercontinental operations in the 21st century, the projected operational characteristics for these aircraft are examined, the radiation environment as it is now known is presented, and the relevant health issues are discussed. Based on a critical examination of the data, a number of specific issues need to be addressed to ensure an adequate knowledge of the ionizing radiation health risks of these aircraft operations. Large uncertainties in our knowledge of the physical fields for high-energy neutrons and multiply-charged ion components need to be reduced. Improved methods for estimating risks in prenatal exposure need to be developed. A firm basis for solar flare monitoring and forecasting needs to be developed with means of exposure abatement.

  10. Using tablet technology in operational radiation safety applications.

    PubMed

    Phillips, Andrew; Linsley, Mark; Houser, Mike

    2013-11-01

    Tablet computers have become a mainstream product in today's personal, educational, and business worlds. These tablets offer computing power, storage, and a wide range of available products to meet nearly every user need. To take advantage of this new computing technology, a system was developed for the Apple iPad (Apple Inc. 1 Infinite Loop Cupertino, CA 95014) to perform health and safety inspections in the field using editable PDFs and saving them to a database while keeping the process easy and paperless. PMID:24077083

  11. Radiation Safety System of the B-Factory at the Stanford Linear Accelerator Center

    SciTech Connect

    Liu, James C

    1998-10-12

    The radiation safety system (RSS) of the B-Factory accelerator facility at the Stanford Linear Accelerator Center (SLAC) is described. The RSS, which is designed to protect people from prompt radiation exposure due to beam operation, consists of the access control system (ACS) and the radiation containment system (RCS). The ACS prevents people from being exposed to the very high radiation levels inside a beamline shielding housing. The ACS consists of barriers, a standard entry module at every entrance, and beam stoppers. The RCS prevents people from being exposed to the radiation outside a shielding housing, due to either normal or abnormal operation. The RCS consists of power limiting devices, shielding, dump/collimator, and an active radiation monitor system. The inter-related system elements for the ACS and RCS, as well as the associated interlock network, are described. The policies and practices in setting up the RSS are also compared with the regulatory requirements.

  12. Modernisation and consolidation of the European radiation protection legislation: the new Euratom Basic Safety Standards Directive.

    PubMed

    Mundigl, Stefan

    2015-04-01

    With the publication of new basic safety standards for the protection against the dangers arising from exposure to ionising radiation, foreseen in Article 2 and Article 30 of the Euratom Treaty, the European Commission modernises and consolidates the European radiation protection legislation. A revision of the Basic Safety Standards was needed in order (1) to take account of the scientific and technological progress since 1996 and (2) to consolidate the existing set of Euratom radiation protection legislation, merging five Directives and upgrading a recommendation to become legally binding. The new Directive offers in a single coherent document basics safety standards for radiation protection, which take account of the most recent advances in science and technology, cover all relevant radiation sources, including natural radiation sources, integrate protection of workers, members of the public, patients and the environment, cover all exposure situations, planned, existing, emergency, and harmonise numerical values with international standards. After the publication of the Directive in the beginning of 2014, Member States have 4 y to transpose the Directive into national legislation and to implement the requirements therein. PMID:25227437

  13. US Food and Drug Administration Regulation of Medical Devices and Radiation Oncology: Can Reform Improve Safety?

    PubMed Central

    Hattangadi, Jona A.; O'Reilly, James T.; Recht, Abram

    2012-01-01

    Although radiation therapy is highly safe and effective in treating cancer, recent reports of dangerous radiation-related errors have focused a national spotlight on the field of radiation oncology and, more specifically, on the rapidly evolving and complex nature of radiation devices and how they are regulated. The purpose of this review is to explore the issues involved in medical device regulation in radiation oncology. We start with a general review of federal medical device regulation, including explanations of the legal and regulatory framework, and then discuss issues specific to radiation oncology with real-world examples. We also provide our thoughts on potential solutions and reforms to the current system, including better reporting of radiation-related errors in a centralized database, well-defined criteria for establishing substantial equivalence of a new device, and standard postmarket surveillance of radiation devices. Modern radiation therapy is a powerful tool that can help cure many patients' cancers and alleviate others' suffering with limited adverse effects. We must ensure that this promise is never compromised by avoidable mistakes. PMID:22548012

  14. Measurement and standardization of eye safety for optical radiation of LED products

    NASA Astrophysics Data System (ADS)

    Mou, Tongsheng; Peng, Zhenjian

    2013-06-01

    The blue light hazard (BLH) to human eye's retina is now a new issue emerging in applications of artificial light sources. Especially for solid state lighting sources based on the blue chip-LED(GaN), the photons with their energy more than 2.4 eV show photochemical effects on the retina significantly, raising damage both in photoreceptors and retinal pigment epithelium. The photobiological safety of artificial light sources emitting optical radiation has gained more and more attention worldwide and addressed by international standards IEC 62471-2006(CIE S009/E: 2002). Meanwhile, it is involved in IEC safety specifications of LED lighting products and covered by European Directive 2006/25/EC on the minimum health and safety requirements regarding the exposure of the workers to artificial optical radiation. In practical applications of the safety standards, the measuring methods of optical radiation from LED products to eyes are important in establishment of executable methods in the industry. In 2011, a new project to develop the international standard of IEC TR62471-4,that is "Measuring methods of optical radiation related to photobiological safety", was approved and are now under way. This paper presents the concerned methods for the assessment of optical radiation hazards in the standards. Furthermore, a retina radiance meter simulating eye's optical geometry is also described, which is a potential tool for blue light hazard assessment of retinal exposure to optical radiation. The spectroradiometric method integrated with charge-coupled device(CCD) imaging system is introduced to provide more reliable results.

  15. Radiation Safety Issues in High Altitude Commercial Aircraft

    NASA Technical Reports Server (NTRS)

    Wilson, John W.; Cucinotta, Francis A.; Shinn, Judy L.

    1995-01-01

    The development of a global economy makes the outlook for high speed commercial intercontinental flight feasible, and the development of various configurations operating from 20 to 30 km have been proposed. In addition to the still unresolved issues relating to current commercial operations (12-16 km), the higher dose rates associated with the higher operating altitudes makes il imperative that the uncertainties in the atmospheric radiation environment and the associated health risks be re-examined. Atmospheric radiation associated with the galactic cosmic rays forms a background level which may, under some circumstances, exceed newly recommended allowable exposure limits proposed on the basis of recent evaluations of the A -bomb survivor data (due to increased risk coefficients). These larger risk coefficients, within the context of the methodology for estimating exposure limits, are resulting in exceedingly low estimated allowable exposure limits which may impact even present day flight operations and was the reason for the CEC workshop in Luxembourg (1990). At higher operating altitudes, solar particles events can produce exposures many orders of magnitude above background levels and pose significant health risks to the most sensitive individuals (such as during pregnancy). In this case the appropriate quality factors are undefined, and some evidence exists which indicates that the quality factor for stochastic effects is a substantial underestimate.

  16. 10 CFR 34.42 - Radiation Safety Officer for industrial radiography.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ..., and ALARA procedures as required by 10 CFR part 20 of this chapter, and reviewing them regularly to ensure that the procedures in use conform to current 10 CFR part 20 procedures, conform to other NRC... 10 Energy 1 2010-01-01 2010-01-01 false Radiation Safety Officer for industrial radiography....

  17. 10 CFR 34.42 - Radiation Safety Officer for industrial radiography.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ..., and ALARA procedures as required by 10 CFR part 20 of this chapter, and reviewing them regularly to ensure that the procedures in use conform to current 10 CFR part 20 procedures, conform to other NRC... 10 Energy 1 2014-01-01 2014-01-01 false Radiation Safety Officer for industrial radiography....

  18. 10 CFR 34.42 - Radiation Safety Officer for industrial radiography.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ..., and ALARA procedures as required by 10 CFR part 20 of this chapter, and reviewing them regularly to ensure that the procedures in use conform to current 10 CFR part 20 procedures, conform to other NRC... 10 Energy 1 2011-01-01 2011-01-01 false Radiation Safety Officer for industrial radiography....

  19. 10 CFR 34.42 - Radiation Safety Officer for industrial radiography.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ..., and ALARA procedures as required by 10 CFR part 20 of this chapter, and reviewing them regularly to ensure that the procedures in use conform to current 10 CFR part 20 procedures, conform to other NRC... 10 Energy 1 2012-01-01 2012-01-01 false Radiation Safety Officer for industrial radiography....

  20. 10 CFR 34.42 - Radiation Safety Officer for industrial radiography.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ..., and ALARA procedures as required by 10 CFR part 20 of this chapter, and reviewing them regularly to ensure that the procedures in use conform to current 10 CFR part 20 procedures, conform to other NRC... 10 Energy 1 2013-01-01 2013-01-01 false Radiation Safety Officer for industrial radiography....

  1. 10 CFR 35.57 - Training for experienced Radiation Safety Officer, teletherapy or medical physicist, authorized...

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 1 2012-01-01 2012-01-01 false Training for experienced Radiation Safety Officer, teletherapy or medical physicist, authorized medical physicist, authorized user, nuclear pharmacist, and authorized nuclear pharmacist. 35.57 Section 35.57 Energy NUCLEAR REGULATORY COMMISSION MEDICAL USE...

  2. 21 CFR 14.120 - Establishment of the Technical Electronic Product Radiation Safety Standards Committee (TEPRSSC).

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 21 Food and Drugs 1 2013-04-01 2013-04-01 false Establishment of the Technical Electronic Product Radiation Safety Standards Committee (TEPRSSC). 14.120 Section 14.120 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL PUBLIC HEARING BEFORE A PUBLIC ADVISORY COMMITTEE Technical Electronic...

  3. Radiation safety aspects of the operation of first three synchrotron beam lines of Indus-2.

    PubMed

    Nayak, M K; Nair, Haridas G; Bakshi, A K; Sahani, P K; Singh, Sunil; Khan, Saleem; Verma, Dimple; Dev, Vipin; Sahu, T K; Khare, Mukesh; Kumar, Vijay; Bandyopadhyay, Tapas; Tripathi, R M; Sharma, D N

    2015-04-01

    Five synchrotron radiation beam lines are commissioned and now under regular operation at the Synchrotron Radiation Source, Indus-2 at Raja Ramanna Centre For Advanced Technology (RRCAT), Indore, India. Nine beam lines are under trial operation, and six beam lines are in the installation stage. In the early phase of installation of beam lines on Indus-2, three bending magnet beam lines, Extended X-ray Absorption Fine Structure (EXAFS, BL-8), Energy Dispersive X-ray Diffraction (EDXRD, BL-11) and Angle Dispersive X-ray Diffraction (ADXRD, BL-12), were installed and commissioned, after approval from Atomic Energy Regulatory Board (AERB), India. These beam lines are pink (BL-8), white (BL-11) and monochromatic (BL-12), which are housed in specially designed shielded hutches. In order to ensure safety of users and other working personnel from ionizing radiations present in these beam lines, several safety systems are incorporated and safety procedures are followed. The paper describes the radiological safety aspects of the three beam lines during its initial commissioning trials and also the measurements on radiation levels carried out in and around the beam line hutches. PMID:25209995

  4. Strategies for Navigating Common Ethical Dilemmas Encountered by Operational Radiation Safety Professionals.

    PubMed

    Emery, Robert J; Rios, Janelle

    2016-02-01

    Because operational radiation safety professionals can encounter ethical dilemmas in the course of their work, codes of ethics and professional standards of conduct are maintained by the Health Physics Society (HPS) and the American Academy of Health Physics (AAHP). While these works provide valuable guidance, they do not operationalize the types of ethical dilemmas radiation safety practitioners might encounter. For example, consider the ethical conundrum of “dual loyalty,” defined as the situation in which an individual holds simultaneous obligations to two or more parties. In the case of radiation safety, practicing professionals hold obligations to the workers being protected and to the leaders of the organization. If these obligations are in conflict, serious difficulties can arise. The conundrum of dual loyalty is described and a strategy for reducing its effect is discussed. Two other common ethical issues; “confidentiality” and “organizational dissent” are similarly presented. A foundation from which to launch an ongoing dialogue about ethical issues within the radiation safety profession is also proposed. PMID:26710164

  5. Occupational Exposure to Diagnostic Radiology in Workers without Training in Radiation Safety

    NASA Astrophysics Data System (ADS)

    Gaona, Enrique; Enríquez, Jesús G. Franco

    2004-09-01

    The physicians, technicians, nurses, and others involved in radiation areas constitute the largest group of workers occupationally exposed to man-made sources of radiation. Personnel radiation exposure must be monitored for safety and regulatory considerations, this assessment may need to be made over a period of one month or several months. The purpose of this study was to carry out an exploratory survey of occupational exposures associated with diagnostic radiology. The personnel dosimeters used in this study were thermoluminiscent dosimeters (TLDs). The reported number of monitored workers was 110 of different departments of radiology of the Mexican Republic without education in radiation safety, included general fluoscopic/radiographic imaging, computed tomography and mammography procedures. Physicians and X-ray technologist in diagnostic radiology receive an average annual effective dose of 2.9 mSv with range from 0.18 to 5.64 mSv. The average level of occupational exposures is generally similar to the global average level of natural radiation exposure. The annual global per capita effective dose due to natural radiation sources is 2.4 mSv (UNSCEAR 2000 Report). There is not significant difference between average occupational exposures and natural radiation exposure for p < 0.05.

  6. Integrating an academic radiation safety program into an environmental management system.

    PubMed

    Zurosky, Daniel M

    2003-08-01

    The Environmental Health and Safety (EH&S) Program at the University of South Carolina recently developed an environmental management system (EMS) based on the ISO 14001 International Standard. Since our radiation safety program must already meet strict state licensing requirements, the process of conforming to this standard was relatively easy to accomplish. The EH&S program achieved certification to the ISO 14001 standard in August of 2002. The benefits of the EMS include: better interaction between radiation safety and other EH&S program entities, holds all employees accountable by closely tracking program activities, presents a clear picture of program accomplishments to the university administration, allows for better use of limited resources and provides for continuous program improvement. PMID:12865748

  7. Current global and Korean issues in radiation safety of nuclear medicine procedures.

    PubMed

    Song, H C

    2016-06-01

    In recent years, the management of patient doses in medical imaging has evolved as concern about radiation exposure has increased. Efforts and techniques to reduce radiation doses are focussed not only on the basis of patient safety, but also on the fundamentals of justification and optimisation in cooperation with international organisations such as the International Commission on Radiological Protection, the International Atomic Energy Agency, and the World Health Organization. The Image Gently campaign in children and Image Wisely campaign in adults to lower radiation doses have been initiated in the USA. The European Association of Nuclear Medicine paediatric dosage card, North American consensus guidelines, and Nuclear Medicine Global Initiative have recommended the activities of radiopharmaceuticals that should be administered in children. Diagnostic reference levels (DRLs), developed predominantly in Europe, may be an important tool to manage patient doses. In Korea, overexposure to radiation, even from the use of medical imaging, has become a public issue, particularly since the accident at the Fukushima nuclear power plant. As a result, the Korean Nuclear Safety and Security Commission revised the technical standards for radiation safety management in medical fields. In parallel, DRLs for nuclear medicine procedures have been collected on a nationwide scale. Notice of total effective dose from positron emission tomography-computed tomography for cancer screening has been mandatory since mid-November 2014. PMID:26960820

  8. Probabilistic Modeling Approach for Evaluating the Compliance of Ready-To-Eat Foods with New European Union Safety Criteria for Listeria monocytogenes▿

    PubMed Central

    Koutsoumanis, Konstantinos; Angelidis, Apostolos S.

    2007-01-01

    Among the new microbiological criteria that have been incorporated in EU Regulation 2073/2005, of particular interest are those concerning Listeria monocytogenes in ready-to eat (RTE) foods, because for certain food categories, they no longer require zero tolerance but rather specify a maximum allowable concentration of 100 CFU/g or ml. This study presents a probabilistic modeling approach for evaluating the compliance of RTE sliced meat products with the new safety criteria for L. monocytogenes. The approach was based on the combined use of (i) growth/no growth boundary models, (ii) kinetic growth models, (iii) product characteristics data (pH, aw, shelf life) collected from 160 meat products from the Hellenic retail market, and (iv) storage temperature data recorded from 50 retail stores in Greece. This study shows that probabilistic analysis of the above components using Monte Carlo simulation, which takes into account the variability of factors affecting microbial growth, can lead to a realistic estimation of the behavior of L. monocytogenes throughout the food supply chain, and the quantitative output generated can be further used by food managers as a decision-making tool regarding the design or modification of a product's formulation or its “use-by” date in order to ensure its compliance with the new safety criteria. The study also argues that compliance of RTE foods with the new safety criteria should not be considered a parameter with a discrete and binary outcome because it depends on factors such as product characteristics, storage temperature, and initial contamination level, which display considerable variability even among different packages of the same RTE product. Rather, compliance should be expressed and therefore regulated in a more probabilistic fashion. PMID:17557858

  9. Probabilistic modeling approach for evaluating the compliance of ready-to-eat foods with new European Union safety criteria for Listeria monocytogenes.

    PubMed

    Koutsoumanis, Konstantinos; Angelidis, Apostolos S

    2007-08-01

    Among the new microbiological criteria that have been incorporated in EU Regulation 2073/2005, of particular interest are those concerning Listeria monocytogenes in ready-to eat (RTE) foods, because for certain food categories, they no longer require zero tolerance but rather specify a maximum allowable concentration of 100 CFU/g or ml. This study presents a probabilistic modeling approach for evaluating the compliance of RTE sliced meat products with the new safety criteria for L. monocytogenes. The approach was based on the combined use of (i) growth/no growth boundary models, (ii) kinetic growth models, (iii) product characteristics data (pH, a(w), shelf life) collected from 160 meat products from the Hellenic retail market, and (iv) storage temperature data recorded from 50 retail stores in Greece. This study shows that probabilistic analysis of the above components using Monte Carlo simulation, which takes into account the variability of factors affecting microbial growth, can lead to a realistic estimation of the behavior of L. monocytogenes throughout the food supply chain, and the quantitative output generated can be further used by food managers as a decision-making tool regarding the design or modification of a product's formulation or its "use-by" date in order to ensure its compliance with the new safety criteria. The study also argues that compliance of RTE foods with the new safety criteria should not be considered a parameter with a discrete and binary outcome because it depends on factors such as product characteristics, storage temperature, and initial contamination level, which display considerable variability even among different packages of the same RTE product. Rather, compliance should be expressed and therefore regulated in a more probabilistic fashion. PMID:17557858

  10. Radiological protection, safety and security issues in the industrial and medical applications of radiation sources

    NASA Astrophysics Data System (ADS)

    Vaz, Pedro

    2015-11-01

    The use of radiation sources, namely radioactive sealed or unsealed sources and particle accelerators and beams is ubiquitous in the industrial and medical applications of ionizing radiation. Besides radiological protection of the workers, members of the public and patients in routine situations, the use of radiation sources involves several aspects associated to the mitigation of radiological or nuclear accidents and associated emergency situations. On the other hand, during the last decade security issues became burning issues due to the potential malevolent uses of radioactive sources for the perpetration of terrorist acts using RDD (Radiological Dispersal Devices), RED (Radiation Exposure Devices) or IND (Improvised Nuclear Devices). A stringent set of international legally and non-legally binding instruments, regulations, conventions and treaties regulate nowadays the use of radioactive sources. In this paper, a review of the radiological protection issues associated to the use of radiation sources in the industrial and medical applications of ionizing radiation is performed. The associated radiation safety issues and the prevention and mitigation of incidents and accidents are discussed. A comprehensive discussion of the security issues associated to the global use of radiation sources for the aforementioned applications and the inherent radiation detection requirements will be presented. Scientific, technical, legal, ethical, socio-economic issues are put forward and discussed.

  11. Intensive Care Nurses’ Knowledge of Radiation Safety and Their Behaviors Towards Portable Radiological Examinations

    PubMed Central

    Dianati, Mansoor; Zaheri, Azita; Talari, Hamid Reza; Deris, Fateme; Rezaei, Sara

    2014-01-01

    Background: Radiological examinations for patients who are hospitalized at intensive care units are usually performed using portable radiography devices. However they may require knowledge and safety precautions of nurses. Objectives: The aim of the study was to investigate ICU nurses’ knowledge of radiation safety and their behaviors towards portable radiological examinations. Materials and Methods: In total, 44 intensive care nurses were recruited for this cross-sectional descriptive study using census sampling during April and May 2014. The study setting was at intensive care units of Shahid Beheshti Hospital of Kashan, Iran. An eleven-item questionnaire and a five-item checklist were used for evaluating nurses’ radiation protection knowledge and behaviors, respectively. An expert panel consisting of ten nursing and radiology faculty members confirmed the content validity of the questionnaire and the checklist. Moreover, a Geiger-Müller counter was used for measuring ionizing radiation during portable radiological examinations. Study data were analyzed using the SPSS software version 13.0. Mean, standard deviation, frequency and one-sample t test were used for description of the data. The level of significance was set at below 0.05. Results: The mean of participants’ radiation protection knowledge was 4.77 ± 1.38. The most prevalent radiation protection behavior of nurses was leaving the intensive care unit during portable radiological examinations. Only 6.8% of nurses stayed at the nursing station during radiological examinations. The highest dose of radiation was 0.11 micro Sievert per hour (μSv/h), which was much lower than the highest permitted level of radiation exposure i.e. 0.25 μSv/h. Conclusions: Portable radiological examinations did not expose healthcare providers to high doses of ionizing radiation. Nurses’ radiation protection knowledge was limited and hence, they require in-service education programs. PMID:25741515

  12. Implementation of ANSI 13.36 - Radiation Safety Training for Workers

    SciTech Connect

    Trinosky, P.A.; Wells, L.

    2000-11-18

    ''Radiation Safety Training for Workers'' (ANSI 13.36) specifies a process for developing and implementing radiation safety training using performance-based concepts. In general, radiation safety training includes radiological safety policies, fundamental radiological controls, and the technical functions of specific facilities. Actual training, however, can vary significantly from one site to another, depending on the requirements and potential risks associated with the specific work involved. Performance-based training focuses on the instruction and practices required to develop job-related knowledge, skills, and abilities, rather than on simply prescribing training content and objectives. The Health Physics Society Standards Committee (HPSSC) working group recommended performance-based training, as opposed to a broad training program with prescribed performance objectives, for two main reasons: (1) the wide range of radiological workers to be trained and (2) the concern that a prescriptive program (i.e., 40 hours of training) could be misapplied. In addition, the working group preferred that the scope and depth of training be based on specific hazards and the magnitude of risk posed by those hazards. The group also proposed that passing scores be based on specified goals and the characteristics of test questions used. For instance, where passing scores are established (e.g., multiple-choice exams), they should be based on an analysis of the test questions rather than simply an arbitrary passing score. This standard is not intended to replace regulatory or contractual training requirements that establish minimum objectives, topics, class duration, or passing scores. Nor does it address radiation safety training received as part of an academic program of study. Such individuals would still require site-specific and on-the-job training for certain tasks.

  13. Key Performance Indicators in the Evaluation of the Quality of Radiation Safety Programs.

    PubMed

    Schultz, Cheryl Culver; Shaffer, Sheila; Fink-Bennett, Darlene; Winokur, Kay

    2016-08-01

    Beaumont is a multiple hospital health care system with a centralized radiation safety department. The health system operates under a broad scope Nuclear Regulatory Commission license but also maintains several other limited use NRC licenses in off-site facilities and clinics. The hospital-based program is expansive including diagnostic radiology and nuclear medicine (molecular imaging), interventional radiology, a comprehensive cardiovascular program, multiple forms of radiation therapy (low dose rate brachytherapy, high dose rate brachytherapy, external beam radiotherapy, and gamma knife), and the Research Institute (including basic bench top, human and animal). Each year, in the annual report, data is analyzed and then tracked and trended. While any summary report will, by nature, include items such as the number of pieces of equipment, inspections performed, staff monitored and educated and other similar parameters, not all include an objective review of the quality and effectiveness of the program. Through objective numerical data Beaumont adopted seven key performance indicators. The assertion made is that key performance indicators can be used to establish benchmarks for evaluation and comparison of the effectiveness and quality of radiation safety programs. Based on over a decade of data collection, and adoption of key performance indicators, this paper demonstrates one way to establish objective benchmarking for radiation safety programs in the health care environment. PMID:27356165

  14. [Systemic approach to ecologic safety at objects with radiation jeopardy, involved into localization of low and medium radioactive waste].

    PubMed

    Veselov, E I

    2011-01-01

    The article deals with specifying systemic approach to ecologic safety of objects with radiation jeopardy. The authors presented stages of work and algorithm of decisions on preserving reliability of storage for radiation jeopardy waste. Findings are that providing ecologic safety can cover 3 approaches: complete exemption of radiation jeopardy waste, removal of more dangerous waste from present buildings and increasing reliability of prolonged localization of radiation jeopardy waste at the initial place. The systemic approach presented could be realized at various radiation jeopardy objects. PMID:21774123

  15. [SUBSTANTIATION OF DOSE LIMITS FOR A NEW NORMATIVE DOCUMENT ON RADIATION SAFETY OF LONG-DURATION SPACE MISSIONS AT ORBIT ALTITUDES OF UP TO 500 KM].

    PubMed

    Ushakov, I B; Grigoriev, Yu G; Shafirkin, A V; Shurshakov, V A

    2016-01-01

    Review of the data of experimental radiobiology and epidemiological follow-up of large groups of people subjected to radiation exposures on Earth has been undertaken to substantiate dose limits for critical organs of cosmonauts in order to ensure good performance and vitality while on long-duration orbital missions. The career dose limits for cosmonauts and astronauts established earlier in the USSR and USA amounted to nothing more but banning the risk of cancer death increase to 3%. To apply more rigorous criteria of delayed radiation risks, the Russian limits for cosmonauts were revised to substantiate a 4-fold reduction of the average tissue equivalent dose maximum to 1 Sv. The total of cancer and non-cancer radiation risks over lifetime and probable reduction of mean life expectancy (MLE) were calculated using the model of radiation-induced mortality for mammals and taken as the main damage to health. The established dose limit is equal to the career dose for nuclear industry personnel set forth by Russian standard document NRB 99/2009. For better agreement of admissible threshold doses to critical human organs (bone marrow, lens and skin) in the revised radiation limits for long-duration space missions and radiation safety limits on Earth, reduction of dose limits for the critical organs were substantiated additionally; these limits comply with those for planned over-exposure on Earth in document NRB 99/2009. PMID:27347592

  16. Radiation safety review for 511-keV emitters in nuclear medicine.

    PubMed

    Dell, M A

    1997-03-01

    With the advent of high-energy collimators and dual-head coincidence cameras, standard nuclear medicine facilities will soon begin imaging with PET isotopes. The use of 511-keV emitters raises new radiation safety concerns for technologists traditionally limited to handling 99mTc and other low-energy isotopes. This article is a basic review of positron emitters, measurement concerns, exposure rates, shielding requirements and external radiation exposure mitigation. Newly developed PET shielding products are presented and regulatory status is discussed briefly. PMID:9239598

  17. Feasibility and safety of outpatient brachytherapy in 37 patients with brain tumors using the GliaSite Radiation Therapy System.

    PubMed

    Chino, Kazumi; Silvain, Daniel; Grace, Ana; Stubbs, James; Stea, Baldassarre

    2008-07-01

    Temporary, low dose rate brachytherapy to the margins of resected brain tumors, using a balloon catheter system (GliaSite Radiation Therapy System) and liquid I-125 radiation source (Iotrex), began in 2002 at the University of Arizona Medical Center. Initially, all patients were treated on an inpatient basis. For patient convenience, we converted to outpatient therapy. In this article we review the exposure data and safety history for the 37 patients treated as outpatients. Proper patient selection and instruction is crucial to having a successful outpatient brachytherapy program. A set of evaluation criteria and patient instructions were developed in compliance with the U.S. Nuclear Regulatory Commission's document NUREG-1556 Volume 9 (Appendix U) and Arizona State Nuclear regulatory guidelines, which specify acceptable exposure rates for outpatient release in this setting. Of the 37 patients monitored, 26 patients were treated for recurrent glioblastoma multiforme (GBM), six for primary GBM, and five for metastatic brain tumors. All 37 patients and their primary caregivers gave signed agreement to follow a specific set of instructions and were released for the duration of brachytherapy (3-7 days). The typical prescription dose was 60 Gy delivered at 0.5 cm from the balloon surface. Afterloaded activities in these patients ranged from 90.9 to 750.0 mCi and measured exposure rates at 1 m from the head were less than 14 mR/h. The mean exposure to the caretaker measured by personal radiation Landauer Luxel + whole body dosimeters for 25 caretakers was found to be 9.6 mR, which was significantly less than the mean calculated exposure of 136.8 mR. For properly selected patients, outpatient brachytherapy is simple and can be performed within established regulatory guidelines. PMID:18697562

  18. Feasibility and safety of outpatient brachytherapy in 37 patients with brain tumors using the GliaSite Radiation Therapy System

    SciTech Connect

    Chino, Kazumi; Silvain, Daniel; Grace, Ana; Stubbs, James; Stea, Baldassarre

    2008-07-15

    Temporary, low dose rate brachytherapy to the margins of resected brain tumors, using a balloon catheter system (GliaSite Radiation Therapy System) and liquid I-125 radiation source (Iotrex), began in 2002 at the University of Arizona Medical Center. Initially, all patients were treated on an inpatient basis. For patient convenience, we converted to outpatient therapy. In this article we review the exposure data and safety history for the 37 patients treated as outpatients. Proper patient selection and instruction is crucial to having a successful outpatient brachytherapy program. A set of evaluation criteria and patient instructions were developed in compliance with the U.S. Nuclear Regulatory Commission's document NUREG-1556 Volume 9 (Appendix U) and Arizona State Nuclear regulatory guidelines, which specify acceptable exposure rates for outpatient release in this setting. Of the 37 patients monitored, 26 patients were treated for recurrent glioblastoma multiforme (GBM), six for primary GBM, and five for metastatic brain tumors. All 37 patients and their primary caregivers gave signed agreement to follow a specific set of instructions and were released for the duration of brachytherapy (3-7 days). The typical prescription dose was 60 Gy delivered at 0.5 cm from the balloon surface. Afterloaded activities in these patients ranged from 90.9 to 750.0 mCi and measured exposure rates at 1 m from the head were less than 14 mR/h. The mean exposure to the caretaker measured by personal radiation Landauer Luxel+ whole body dosimeters for 25 caretakers was found to be 9.6 mR, which was significantly less than the mean calculated exposure of 136.8 mR. For properly selected patients, outpatient brachytherapy is simple and can be performed within established regulatory guidelines.

  19. Retinal safety of near infrared radiation in photovoltaic restoration of sight.

    PubMed

    Lorach, H; Wang, J; Lee, D Y; Dalal, R; Huie, P; Palanker, D

    2016-01-01

    Photovoltaic restoration of sight requires intense near-infrared light to effectively stimulate retinal neurons. We assess the retinal safety of such radiation with and without the retinal implant. Retinal damage threshold was determined in pigmented rabbits exposed to 880nm laser radiation. The 50% probability (ED50) of retinal damage during 100s exposures with 1.2mm diameter beam occurred at 175mW, corresponding to a modeled temperature rise of 12.5°C. With the implant, the same temperature was reached at 78mW, close to the experimental ED50 of 71mW. In typical use conditions, the retinal temperature rise is not expected to exceed 0.43°C, well within the safety limits for chronic use. PMID:26819813

  20. Radiation safety assessment of a system of small reactors for distributed energy.

    PubMed

    Odano, N; Ishida, T

    2005-01-01

    A passively safe small reactor for a distributed energy system, PSRD, is an integral type of light-water reactor with a thermal output of 100 or 300 MW aimed to be used for supplying district heat, electricity to small grids, and so on. Candidate locations for the PSRD as a distributed energy source are on-ground, deep underground, and in a seaside pit in the vicinity of the energy consumption area. Assessments of the radiation safety of a PSRD were carried out for three cases corresponding to normal operation, shutdown and a hypothetical postulated accident for several siting candidates. Results of the radiation safety assessment indicate that the PSRD design has sufficient shielding performance and capability and that the exposure to the general public is very low in the case of a hypothetical accident. PMID:16381690

  1. Retinal safety of near infrared radiation in photovoltaic restoration of sight

    PubMed Central

    Lorach, H.; Wang, J.; Lee, D. Y.; Dalal, R.; Huie, P.; Palanker, D.

    2015-01-01

    Photovoltaic restoration of sight requires intense near-infrared light to effectively stimulate retinal neurons. We assess the retinal safety of such radiation with and without the retinal implant. Retinal damage threshold was determined in pigmented rabbits exposed to 880nm laser radiation. The 50% probability (ED50) of retinal damage during 100s exposures with 1.2mm diameter beam occurred at 175mW, corresponding to a modeled temperature rise of 12.5°C. With the implant, the same temperature was reached at 78mW, close to the experimental ED50 of 71mW. In typical use conditions, the retinal temperature rise is not expected to exceed 0.43°C, well within the safety limits for chronic use. PMID:26819813

  2. Advances in Atmospheric Radiation Measurements and Modeling Needed to Improve Air Safety

    NASA Astrophysics Data System (ADS)

    Tobiska, W. Kent; Atwell, William; Beck, Peter; Benton, Eric; Copeland, Kyle; Dyer, Clive; Gersey, Brad; Getley, Ian; Hands, Alex; Holland, Michael; Hong, Sunhak; Hwang, Junga; Jones, Bryn; Malone, Kathleen; Meier, Matthias M.; Mertens, Chris; Phillips, Tony; Ryden, Keith; Schwadron, Nathan; Wender, Stephen A.; Wilkins, Richard; Xapsos, Michael A.

    2015-04-01

    Air safety is tied to the phenomenon of ionizing radiation from space weather, primarily from galactic cosmic rays but also from solar energetic particles. A global framework for addressing radiation issues in this environment has been constructed, but more must be done at international and national levels. Health consequences from atmospheric radiation exposure are likely to exist. In addition, severe solar radiation events may cause economic consequences in the international aviation community due to exposure limits being reached by some crew members. Impacts from a radiation environment upon avionics from high-energy particles and low-energy, thermalized neutrons are now recognized as an area of active interest. A broad community recognizes that there are a number of mitigation paths that can be taken relative to the human tissue and avionics exposure risks. These include developing active monitoring and measurement programs as well as improving scientific modeling capabilities that can eventually be turned into operations. A number of roadblocks to risk mitigation still exist, such as effective pilot training programs as well as monitoring, measuring, and regulatory measures. An active international effort toward observing the weather of atmospheric radiation must occur to make progress in mitigating radiation exposure risks. Stakeholders in this process include standard-making bodies, scientific organizations, regulatory organizations, air traffic management systems, aircraft owners and operators, pilots and crew, and even the public.

  3. Radiation safety education reduces the incidence of adult fingers on neonatal chest radiographs.

    PubMed

    Sahota, N; Burbridge, B E; Duncan, M D

    2014-06-01

    A previous audit revealed a high frequency of adult fingers visualised on neonatal intensive care unit (NICU) chest radiographs-representing an example of inappropriate occupational radiation exposure. Radiation safety education was provided to staff and we hypothesised that the education would reduce the frequency of adult fingers visualised on NICU chest radiographs. Two cross-sectional samples taken before and after the administration of the education were compared. We examined fingers visualised directly in the beam, fingers in the direct beam but eliminated by technologists editing the image, and fingers under the cones of the portable x-ray machine. There was a 46.2% reduction in fingers directly in the beam, 50.0% reduction in fingers directly in the beam but cropped out, and 68.4% reduction in fingers in the coned area. There was a 57.1% overall reduction in adult fingers visualised, which was statistically significant (Z value - 7.48, P < 0.0001). This study supports radiation safety education in minimising inappropriate occupational radiation exposure. PMID:24705198

  4. Comparison of radiation sources and filtering safety glasses for fluorescent nondestructive evaluation

    NASA Astrophysics Data System (ADS)

    Lopez, Richard Daniel

    This study was directed toward the question of whether recent advancements in radiation sources and test media offered significant improvements over the current state of the art. Included were experiments characterizing common penetrant and magnetic particle materials to determine their fluorescent excitation spectra, and a comparison between the fluorescent excitation spectra and the emission spectra of common excitation sources. The relationship between exciter and test medium directly controls the luminance of a defect indication. As indication luminance increases, the probability of it being detected by the inspector increases. Fluorescent penetrant and magnetic particle test media were originally designed around the widely available filtered medium pressure mercury vapor lamp, which remains the standard excitation radiation source. Test media properties, and the types of available excitation sources have changed with time, and it was unclear whether present-day media was still best excited by the historical standard ultraviolet radiation source. Predictions and experimental work was performed to determine the optimal excitation source for fluorescent nondestructive testing, and to determine which safety lens option would offer the highest probability of detection. Improvement in radiation sources was primarily judged by an increase in fluorophore luminance versus background, which led to an increase in signal-to-noise ratio facilitating better indication detectability. Other factors considered were improved health and safety, and ease of use.

  5. Radiation safety requirements for radioactive waste management in the framework of a quality management system

    SciTech Connect

    Salgado, M.M.; Benitez, J.C.; Pernas, R.; Gonzalez, N.

    2007-07-01

    The Center for Radiation Protection and Hygiene (CPHR) is the institution responsible for the management of radioactive wastes generated from nuclear applications in medicine, industry and research in Cuba. Radioactive Waste Management Service is provided at a national level and it includes the collection and transportation of radioactive wastes to the Centralized Waste Management Facilities, where they are characterized, segregated, treated, conditioned and stored. A Quality Management System, according to the ISO 9001 Standard has been implemented for the RWM Service at CPHR. The Management System includes the radiation safety requirements established for RWM in national regulations and in the Licence's conditions. The role of the Regulatory Body and the Radiation Protection Officer in the Quality Management System, the authorization of practices, training and personal qualification, record keeping, inspections of the Regulatory Body and internal inspection of the Radiation Protection Officer, among other aspects, are described in this paper. The Quality Management System has shown to be an efficient tool to demonstrate that adequate measures are in place to ensure the safety in radioactive waste management activities and their continual improvement. (authors)

  6. Legitimating a nuclear critic: John Gofman, radiation safety, and cancer risks.

    PubMed

    Semendeferi, Ioanna

    2008-01-01

    Whether low-level ionizing radiation has an effect on humans has been a polarizing issue for the last fifty years. The epicenter of this controversy has been the validity of the linear non-threshold dose-response model, according to which any amount of radiation, however small, causes damage to human genes and health. In the late 1960s and early 1970s, the nuclear scientist and medical researcher John Gofman (1918-2007) played a pivotal role in the debate. Historical accounts have treated Gofman as a radical antinuclear scientist whose unscientific arguments put enormous political pressure on the nuclear power industry and regulatory agencies. Gofman's bitter struggle with the Atomic Energy Commission, which funded his research at Lawrence Livermore National Laboratory, partly accounts for this view. However, my analysis of Gofman's involvement in the low-level radiation debate shows how he also helped shift the focus in radiation safety from the risks of genetic damage or leukemia to somatic or cancer risks. His arguments led to the introduction of the linear non-threshold radiation model as a means of numerically estimating cancer risks. This was a watershed event in radiation-safety science and politics. Gofman's case sheds light on the process by which a scientist could secure legitimation even when his technical arguments threatened the government's interests. I conclude that it also points to an open issue in the history of antinuclear scientists, or of other politically active scientists or technology critics: treating them as critics should not preclude historians from treating them as scientists. PMID:20073123

  7. Posttherapy radiation safety considerations in radiomicrosphere treatment with 90Y-microspheres.

    PubMed

    Gulec, Seza A; Siegel, Jeffry A

    2007-12-01

    Radiomicrosphere treatment involves the intrahepatic arterial administration of (90)Y-resin or (90)Y-glass microspheres. The microspheres are biocompatible, but not biodegradable, and little to no (90)Y leaches from the microspheres. Without any bioelimination, the beta-dose delivery is generally confined to the liver. Although U.S. Nuclear Regulatory Commission requirements permit patients treated with these microspheres to be released without the need for dose determination or patient instructions, there are important radiation safety issues that need scientific clarification. We carefully evaluated the radiation exposure mechanisms, including the bremsstrahlung radiation doses to others, for a variety of lifestyle behaviors. Dose estimates were also made for several practical and theoretic situations involving the patient's gonads, an embryo or fetus, and a nursing infant. For the infant, we evaluated the potential beta-dose that might be introduced via breast milk ingestion. The bremsstrahlung component of the decay scheme of the pure beta-emitter (90)Y has traditionally been ignored in internal and external dose calculations. Because the production of in vivo bremsstrahlung with the high-energy pure beta-particle-emitting radionuclides used for therapeutic purposes is sufficient to permit external detection and imaging, we believe that the contribution of such radiation should be considered with regard to patient release; we therefore chose to evaluate this potential external radiation hazard. In all cases, the estimated doses were very small, indicating that no patient restrictions are required for radiation safety purposes after the release of a patient who has been treated with (90)Y-microspheres. PMID:18006608

  8. Regulatory Safety Issues in the Structural Design Criteria of ASME Section III Subsection NH and for Very High Temperatures for VHTR & GEN IV

    SciTech Connect

    William J. O’Donnell; Donald S. Griffin

    2007-05-07

    The objective of this task is to identify issues relevant to ASME Section III, Subsection NH [1], and related Code Cases that must be resolved for licensing purposes for VHTGRs (Very High Temperature Gas Reactor concepts such as those of PBMR, Areva, and GA); and to identify the material models, design criteria, and analysis methods that need to be added to the ASME Code to cover the unresolved safety issues. Subsection NH was originally developed to provide structural design criteria and limits for elevated-temperature design of Liquid Metal Fast Breeder Reactor (LMFBR) systems and some gas-cooled systems. The U.S. Nuclear Regulatory Commission (NRC) and its Advisory Committee for Reactor Safeguards (ACRS) reviewed the design limits and procedures in the process of reviewing the Clinch River Breeder Reactor (CRBR) for a construction permit in the late 1970s and early 1980s, and identified issues that needed resolution. In the years since then, the NRC and various contractors have evaluated the applicability of the ASME Code and Code Cases to high-temperature reactor designs such as the VHTGRs, and identified issues that need to be resolved to provide a regulatory basis for licensing. This Report describes: (1) NRC and ACRS safety concerns raised during the licensing process of CRBR , (2) how some of these issues are addressed by the current Subsection NH of the ASME Code; and (3) the material models, design criteria, and analysis methods that need to be added to the ASME Code and Code Cases to cover unresolved regulatory issues for very high temperature service.

  9. New beam-charge interlock system for radiation safety at the KEKB injector linac

    NASA Astrophysics Data System (ADS)

    Suwada, T.; Kadokura, E.; Satoh, M.; Furukawa, K.

    2008-02-01

    A new beam-charge interlock system is under development for radiation safety and machine protection at the KEKB injector linac. A hardware-based interlock system is required instead of the present software-based interlock system in order to boost its reliability. This system restricts the integrated amount of beam charges delivered to four different storage rings. The beam charges are measured using wall-current monitors and detection electronics at six locations along the linac. The detection electronics independently transmits a beam-abort request through a twisted hardwire cable directly to the safety control system of the linac, when the integrated amount of beam charges exceeds a certain threshold level prescribed for each location. We describe the characteristics and performance of the new beam-charge interlock system along with the details of the experimental tests.

  10. Incident Learning and Failure-Mode-and-Effects-Analysis Guided Safety Initiatives in Radiation Medicine.

    PubMed

    Kapur, Ajay; Goode, Gina; Riehl, Catherine; Zuvic, Petrina; Joseph, Sherin; Adair, Nilda; Interrante, Michael; Bloom, Beatrice; Lee, Lucille; Sharma, Rajiv; Sharma, Anurag; Antone, Jeffrey; Riegel, Adam; Vijeh, Lili; Zhang, Honglai; Cao, Yijian; Morgenstern, Carol; Montchal, Elaine; Cox, Brett; Potters, Louis

    2013-01-01

    By combining incident learning and process failure-mode-and-effects-analysis (FMEA) in a structure-process-outcome framework we have created a risk profile for our radiation medicine practice and implemented evidence-based risk-mitigation initiatives focused on patient safety. Based on reactive reviews of incidents reported in our departmental incident-reporting system and proactive FMEA, high safety-risk procedures in our paperless radiation medicine process and latent risk factors were identified. Six initiatives aimed at the mitigation of associated severity, likelihood-of-occurrence, and detectability risks were implemented. These were the standardization of care pathways and toxicity grading, pre-treatment-planning peer review, a policy to thwart delay-rushed processes, an electronic whiteboard to enhance coordination, and the use of six sigma metrics to monitor operational efficiencies. The effectiveness of these initiatives over a 3-years period was assessed using process and outcome specific metrics within the framework of the department structure. There has been a 47% increase in incident-reporting, with no increase in adverse events. Care pathways have been used with greater than 97% clinical compliance rate. The implementation of peer review prior to treatment-planning and use of the whiteboard have provided opportunities for proactive detection and correction of errors. There has been a twofold drop in the occurrence of high-risk procedural delays. Patient treatment start delays are routinely enforced on cases that would have historically been rushed. Z-scores for high-risk procedures have steadily improved from 1.78 to 2.35. The initiatives resulted in sustained reductions of failure-mode risks as measured by a set of evidence-based metrics over a 3-years period. These augment or incorporate many of the published recommendations for patient safety in radiation medicine by translating them to clinical practice. PMID:24380074

  11. TH-E-19A-01: Quality and Safety in Radiation Therapy

    SciTech Connect

    Ford, E; Ezzell, G; Miller, B; Yorke, E

    2014-06-15

    Clinical radiotherapy data clearly demonstrate the link between the quality and safety of radiation treatments and the outcome for patients. The medical physicist plays an essential role in this process. To ensure the highest quality treatments, the medical physicist must understand and employ modern quality improvement techniques. This extends well beyond the duties traditionally associated with prescriptive QA measures. This session will review the current best practices for improving quality and safety in radiation therapy. General elements of quality management will be reviewed including: what makes a good quality management structure, the use of prospective risk analysis such as FMEA, and the use of incident learning. All of these practices are recommended in society-level documents and are incorporated into the new Practice Accreditation program developed by ASTRO. To be effective, however, these techniques must be practical in a resource-limited environment. This session will therefore focus on practical tools such as the newly-released radiation oncology incident learning system, RO-ILS, supported by AAPM and ASTRO. With these general constructs in mind, a case study will be presented of quality management in an SBRT service. An example FMEA risk assessment will be presented along with incident learning examples including root cause analysis. As the physicist's role as “quality officer” continues to evolve it will be essential to understand and employ the most effective techniques for quality improvement. This session will provide a concrete overview of the fundamentals in quality and safety. Learning Objectives: Recognize the essential elements of a good quality management system in radiotherapy. Understand the value of incident learning and the AAPM/ASTRO ROILS incident learning system. Appreciate failure mode and effects analysis as a risk assessment tool and its use in resource-limited environments. Understand the fundamental principles of good

  12. Incident Learning and Failure-Mode-and-Effects-Analysis Guided Safety Initiatives in Radiation Medicine

    PubMed Central

    Kapur, Ajay; Goode, Gina; Riehl, Catherine; Zuvic, Petrina; Joseph, Sherin; Adair, Nilda; Interrante, Michael; Bloom, Beatrice; Lee, Lucille; Sharma, Rajiv; Sharma, Anurag; Antone, Jeffrey; Riegel, Adam; Vijeh, Lili; Zhang, Honglai; Cao, Yijian; Morgenstern, Carol; Montchal, Elaine; Cox, Brett; Potters, Louis

    2013-01-01

    By combining incident learning and process failure-mode-and-effects-analysis (FMEA) in a structure-process-outcome framework we have created a risk profile for our radiation medicine practice and implemented evidence-based risk-mitigation initiatives focused on patient safety. Based on reactive reviews of incidents reported in our departmental incident-reporting system and proactive FMEA, high safety-risk procedures in our paperless radiation medicine process and latent risk factors were identified. Six initiatives aimed at the mitigation of associated severity, likelihood-of-occurrence, and detectability risks were implemented. These were the standardization of care pathways and toxicity grading, pre-treatment-planning peer review, a policy to thwart delay-rushed processes, an electronic whiteboard to enhance coordination, and the use of six sigma metrics to monitor operational efficiencies. The effectiveness of these initiatives over a 3-years period was assessed using process and outcome specific metrics within the framework of the department structure. There has been a 47% increase in incident-reporting, with no increase in adverse events. Care pathways have been used with greater than 97% clinical compliance rate. The implementation of peer review prior to treatment-planning and use of the whiteboard have provided opportunities for proactive detection and correction of errors. There has been a twofold drop in the occurrence of high-risk procedural delays. Patient treatment start delays are routinely enforced on cases that would have historically been rushed. Z-scores for high-risk procedures have steadily improved from 1.78 to 2.35. The initiatives resulted in sustained reductions of failure-mode risks as measured by a set of evidence-based metrics over a 3-years period. These augment or incorporate many of the published recommendations for patient safety in radiation medicine by translating them to clinical practice. PMID:24380074

  13. INSTRUMENTS AND METHODS OF INVESTIGATION: Radiation safety in the Russian atomic power industry

    NASA Astrophysics Data System (ADS)

    Gerasimov, Aleksandr S.; Kiselev, Gennadii V.

    2003-07-01

    Of all the radioactive wastes known in nuclear power industry and engineering, long-lived actinides and fission products from spent nuclear fuel are the most hazardous. One way to reduce their radiation hazard is to resort to nuclear transmutation, which can be performed either in reactors of various types or in accelerator-driven subcritical systems, whose nuclear safety is superior to that of conventional reactors. Fundamentally resolving the problem of the destruction of long-lived radioactive wastes is likely to stimulate progress in the development of the nuclear power industry.

  14. [Implementing new technology in radiation oncology: The French agency for nuclear safety (ASN) report].

    PubMed

    Lartigau, É-F; Lisbona, A; Isambert, A; Cadot, P; Derreumaux, S; Dupuis, O; Gérard, J-P; Ledu, D; Mahé, M-A; Marchesi, V; Mazurier, J; De Oliveira, A; Phare, O; Aubert, B

    2015-10-01

    In August 2013, the French nuclear safety agency (ASN) requested the permanent group of experts in radiation protection in medicine (GPMED) to propose recommendations on the implementation of new technology and techniques in radiation oncology. These recommendations were finalized in February 2015 by the GPMED. In April 2015, the ASN sent a letter to the French ministry of health (DGS/DGOS), and its national health agencies (ANSM, INCa, HAS). In these letters, ASN proposed that, from the 12 recommendations made by the GPMED, an action plan should be established, whose control could be assigned to the French national cancer institute (INCa), as a pilot of the national committee for radiotherapy and that this proposal has to be considered at the next meeting of the national committee of radiotherapy. PMID:26278991

  15. CT Radiation Dose Management: A Comprehensive Optimization Process for Improving Patient Safety.

    PubMed

    Parakh, Anushri; Kortesniemi, Mika; Schindera, Sebastian T

    2016-09-01

    Rising concerns of radiation exposure from computed tomography have caused various advances in dose reduction technologies. While proper justification and optimization of scans has been the main focus to address increasing doses, the value of dose management has been largely overlooked. The purpose of this article is to explain the importance of dose management, provide an overview of the available options for dose tracking, and discuss the importance of a dedicated dose team. The authors also describe how a digital radiation tracking software can be used for analyzing the big data on doses for auditing patient safety, scanner utilization, and productivity, all of which have enormous personal and institutional implications. (©) RSNA, 2016. PMID:27533027

  16. Biomedical radiography: radiation protection and safety. January 1970-December 1987 (citations from the NTIS data base). Report for January 1970-December 1987

    SciTech Connect

    Not Available

    1987-12-01

    This bibliography contains citations concerning the safety of biomedical radiography. Radiation-protection methods and techniques are described, and safety techniques for specific radiology procedures are detailed. Radiation exposure of health workers and patients is discussed. Safety limits are defined. (Contains 166 citations fully indexed and including a title list.)

  17. Key Performance Criteria Affecting the Most the Safety of a Nuclear Waste Long Term Storage : A Case Study Commissioned by CEA

    SciTech Connect

    Marvy, A.; Lioure, A; Heriard-Dubreuil, G.; Gadbois, S.; Schneider, T.; Schieber, C.

    2003-02-24

    As part of the work scope set in the French law on high level long lived waste R&D passed in 1991, CEA is conducting a research program to establish the scientific basis and assess the feasibility of long term storage as an option for the safe management of nuclear waste for periods as long as centuries. This goal is a significant departure from the current industrial practice where storage facilities are usually built to last only a few decades. From a technical viewpoint such an extension in time seems feasible provided care and maintenance is exercised. Considering such long periods of time, the risk for Society of loosing oversight and control of such a facility is real, which triggers the question of whether and how long term storage safety can be actually achieved. Therefore CEA commissioned a study (1) in which MUTADIS Consultants (2) and CEPN (3) were both involved. The case study looks into several past and actual human enterprises conducted over significant periods o f time, one of them dating back to the end of the 18th century, and all identified out of the nuclear field. Then-prevailing societal behavior and organizational structures are screened out to show how they were or are still able to cope with similar oversight and control goals. As a result, the study group formulated a set of performance criteria relating to issues like responsibility, securing funds, legal and legislative implications, economic sustainable development, all being areas which are not traditionally considered as far as technical studies are concerned. These criteria can be most useful from the design stage onward, first in an attempt to define the facility construction and operating guiding principles, and thereafter to substantiate the safety case for long term storage and get geared to the public dialogue on that undertaking should it become a reality.

  18. Engineered and Administrative Safety Systems for the Control of Prompt Radiation Hazards at Accelerator Facilities

    SciTech Connect

    Liu, James C.; Vylet, Vashek; Walker, Lawrence S.; /SLAC

    2007-12-17

    The ANSI N43.1 Standard, currently in revision (ANSI 2007), sets forth the requirements for accelerator facilities to provide adequate protection for the workers, the public and the environment from the hazards of ionizing radiation produced during and from accelerator operations. The Standard also recommends good practices that, when followed, provide a level of radiation protection consistent with those established for the accelerator communities. The N43.1 Standard is suitable for all accelerator facilities (using electron, positron, proton, or ion particle beams) capable of producing radiation, subject to federal or state regulations. The requirements (see word 'shall') and recommended practices (see word 'should') are prescribed in a graded approach that are commensurate with the complexity and hazard levels of the accelerator facility. Chapters 4, 5 and 6 of the N43.1 Standard address specially the Radiation Safety System (RSS), both engineered and administrative systems, to mitigate and control the prompt radiation hazards from accelerator operations. The RSS includes the Access Control System (ACS) and Radiation Control System (RCS). The main requirements and recommendations of the N43.1 Standard regarding the management, technical and operational aspects of the RSS are described and condensed in this report. Clearly some aspects of the RSS policies and practices at different facilities may differ in order to meet the practical needs for field implementation. A previous report (Liu et al. 2001a), which reviews and summarizes the RSS at five North American high-energy accelerator facilities, as well as the RSS references for the 5 labs (Drozdoff 2001; Gallegos 1996; Ipe and Liu 1992; Liu 1999; Liu 2001b; Rokni 1996; TJNAF 1994; Yotam et al. 1991), can be consulted for the actual RSS implementation at various laboratories. A comprehensive report describing the RSS at the Stanford Linear Accelerator Center (SLAC 2006) can also serve as a reference.

  19. Application of the MERIT survey in the multi-criteria quality assessment of occupational health and safety management

    PubMed Central

    Korban, Zygmunt

    2015-01-01

    Occupational health and safety management systems apply audit examinations as an integral element of these systems. The examinations are used to verify whether the undertaken actions are in compliance with the accepted regulations, whether they are implemented in a suitable way and whether they are effective. One of the earliest solutions of that type applied in the mining industry in Poland involved the application of audit research based on the MERIT survey (Management Evaluation Regarding Itemized Tendencies). A mathematical model applied in the survey facilitates the determination of assessment indexes WOPi for each of the assessed problem areas, which, among other things, can be used to set up problem area rankings and to determine an aggregate (synthetic) assessment. In the paper presented here, the assessment indexes WOPi were used to calculate a development measure, and the calculation process itself was supplemented with sensitivity analysis. PMID:26414772

  20. Application of the MERIT survey in the multi-criteria quality assessment of occupational health and safety management.

    PubMed

    Korban, Zygmunt

    2015-01-01

    Occupational health and safety management systems apply audit examinations as an integral element of these systems. The examinations are used to verify whether the undertaken actions are in compliance with the accepted regulations, whether they are implemented in a suitable way and whether they are effective. One of the earliest solutions of that type applied in the mining industry in Poland involved the application of audit research based on the MERIT survey (Management Evaluation Regarding Itemized Tendencies). A mathematical model applied in the survey facilitates the determination of assessment indexes WOPi for each of the assessed problem areas, which, among other things, can be used to set up problem area rankings and to determine an aggregate (synthetic) assessment. In the paper presented here, the assessment indexes WOPi were used to calculate a development measure, and the calculation process itself was supplemented with sensitivity analysis. PMID:26414772

  1. Analytical criteria for performance characteristics of IgE binding methods for evaluating safety of biotech food products.

    PubMed

    Holzhauser, Thomas; Ree, Ronald van; Poulsen, Lars K; Bannon, Gary A

    2008-10-01

    There is detailed guidance on how to perform bioinformatic analyses and enzymatic degradation studies for genetically modified crops under consideration for approval by regulatory agencies; however, there is no consensus in the scientific community on the details of how to perform IgE serum studies. IgE serum studies are an important safety component to acceptance of genetically modified crops when the introduced protein is novel, the introduced protein is similar to known allergens, or the crop is allergenic. In this manuscript, we describe the characteristics of the reagents, validation of assay performance, and data analysis necessary to optimize the information obtained from serum testing of novel proteins and genetically modified (GM) crops and to make results more accurate and comparable between different investigations. PMID:18727951

  2. Recommendations from the workshop on Comparative Approaches to Safety Assessment of GM Plant Materials: A road toward harmonized criteria?

    PubMed

    Bartholomaeus, Andrew; Batista, Juan Carlos; Burachik, Moisés; Parrott, Wayne

    2015-01-01

    An international meeting of genetically modified (GM) food safety assessors from the main importing and exporting countries from Asia and the Americas was held in Buenos Aires, Argentina, between June 26(th) and 28(th), 2013. Participants shared their evaluation approaches, identified similarities and challenges, and used their experience to propose areas for future work. Recommendations for improving risk assessment procedures and avenues for future collaboration were also discussed. The deliberations of the meeting were also supported by a survey of participants which canvassed risk assessment approaches across the regions from which participants came. This project was initiated by Argentine Agri-Food Health and Quality National Service (SENASA, Ministry of Agriculture, Argentina), with the support of the International Life Sciences Institute (ILSI) and other partner institutions. The importance of making all possible efforts toward more integrated and harmonized regulatory oversight for GM organisms (GMOs) was strongly emphasized. This exercise showed that such harmonization is a feasible goal that would contribute to sustain a fluid trade of commodities and ultimately enhance food security. Before this can be achieved, key issues identified in this meeting will have to be addressed in the near future to enable regulatory collaboration or joint work. The authors propose that the recommendations coming out of the meeting should be used as a basis for continuing work, follow up discussions and concrete actions. PMID:25706477

  3. Safety Strategies in an Academic Radiation Oncology Department and Recommendations for Action

    PubMed Central

    Terezakis, Stephanie A.; Pronovost, Peter; Harris, Kendra; DeWeese, Theodore; Ford, Eric

    2013-01-01

    Background Safety initiatives in the United States continue to work on providing guidance as to how the average practitioner might make patients safer in the face of the complex process by which radiation therapy (RT), an essential treatment used in the management of many patients with cancer, is prepared and delivered. Quality control measures can uncover certain specific errors such as machine dose mis-calibration or misalignments of the patient in the radiation treatment beam. However, they are less effective at uncovering less common errors that can occur anywhere along the treatment planning and delivery process, and even when the process is functioning as intended, errors still occur. Prioritizing Risks and Implementing Risk-Reduction Strategies Activities undertaken at the radiation oncology department at the Johns Hopkins Hospital (Baltimore) include Failure Mode and Effects Analysis (FMEA), risk-reduction interventions, and voluntary error and near-miss reporting systems. A visual process map portrayed 269 RT steps occurring among four subprocesses—including consult, simulation, treatment planning, and treatment delivery. Two FMEAs revealed 127 and 159 possible failure modes, respectively. Risk-reduction interventions for 15 “top-ranked” failure modes were implemented. Since the error and near-miss reporting system’s implementation in the department in 2007, 253 events have been logged. However, the system may be insufficient for radiation oncology, for which a greater level of practice-specific information is required to fully understand each event. Conclusions The “basic science” of radiation treatment has received considerable support and attention in developing novel therapies to benefit patients. The time has come to apply the same focus and resources to ensuring that patients safely receive the maximal benefits possible. PMID:21819027

  4. Radiation protection during space flight

    SciTech Connect

    Kovalev, E.E.

    1983-12-01

    The problem of ensuring space flight safety arises from conditions inherent to space flights and outer space and from the existing weight limitations of spacecraft. In estimating radiation hazard during space flights, three natural sources are considered: the Earth's radiation belt, solar radiation, and galactic radiation. This survey first describes the major sources of radiation hazard in outer space with emphasis on those source parameters directly related to shielding manned spacecraft. Then, the current status of the safety criteria used in the shielding calculations is discussed. The rest of the survey is devoted to the rationale for spacecraft radiation shielding calculations. The recently completed long-term space flights indicate the reliability of the radiation safety measures used for the near-Earth space exploration. While planning long-term interplanetary flights, it is necessary to solve a number of complicated technological problems related to the radiation protection of the crew.

  5. SU-E-J-04: A Data-Driven, Response-Based, Multi-Criteria Decision Support System for Personalized Lung Radiation Treatment Planning

    SciTech Connect

    Luo, Y; McShan, D; Schipper, M; Matuszak, M; Ten Haken, R; Kong, F

    2014-06-01

    Purpose: To develop a decision support tool to predict a patient's potential overall survival (OS) and radiation induced toxicity (RIT) based on clinical factors and responses during the course of radiotherapy, and suggest appropriate radiation dose adjustments to improve therapeutic effect. Methods: Important relationships between a patient's basic information and their clinical features before and during the radiation treatment are identified from historical clinical data by using statistical learning and data mining approaches. During each treatment period, a data analysis (DA) module predicts radiotherapy features such as time to local progression (TTLP), time to distant metastases (TTDM), radiation toxicity to different organs, etc., under possible future treatment plans based on patient specifics or responses. An information fusion (IF) module estimates intervals for a patient's OS and the probabilities of RIT from a treatment plan by integrating the outcomes of module DA. A decision making (DM) module calculates “satisfaction” with the predicted radiation outcome based on trade-offs between OS and RIT, and finds the best treatment plan for the next time period via multi-criteria optimization. Results: Using physical and biological data from 130 lung cancer patients as our test bed, we were able to train and implement the 3 modules of our decision support tool. Examples demonstrate how it can help predict a new patient's potential OS and RIT with different radiation dose plans along with how these combinations change with dose, thus presenting a range of satisfaction/utility for use in individualized decision support. Conclusion: Although the decision support tool is currently developed from a small patient sample size, it shows the potential for the improvement of each patient's satisfaction in personalized radiation therapy. The radiation treatment outcome prediction and decision making model needs to be evaluated with more patients and demonstrated for

  6. Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

    SciTech Connect

    Neupauer, R.M.; Thurmond, S.M.

    1992-09-01

    This report describes health and safety concerns associated with the Mixed and Low-level Waste Treatment Facility at the Idaho National Engineering Laboratory. Various hazards are described such as fire, electrical, explosions, reactivity, temperature, and radiation hazards, as well as the potential for accidental spills, exposure to toxic materials, and other general safety concerns.

  7. Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory. Part 1, Waste streams and treatment technologies

    SciTech Connect

    Neupauer, R.M.; Thurmond, S.M.

    1992-09-01

    This report describes health and safety concerns associated with the Mixed and Low-level Waste Treatment Facility at the Idaho National Engineering Laboratory. Various hazards are described such as fire, electrical, explosions, reactivity, temperature, and radiation hazards, as well as the potential for accidental spills, exposure to toxic materials, and other general safety concerns.

  8. Safety.

    ERIC Educational Resources Information Center

    Education in Science, 1996

    1996-01-01

    Discusses safety issues in science, including: allergic reactions to peanuts used in experiments; explosions in lead/acid batteries; and inspection of pressure vessels, such as pressure cookers or model steam engines. (MKR)

  9. Prophylactic UV Radiation and CIE Standard on Photobiological Safety of Lamps and Lamp Systems

    NASA Astrophysics Data System (ADS)

    Sarychev, Genrih; Gavrilkina, Galina

    Two aspects of UV photobiology have come up almost simultaneously for discussion. On the one hand, the CIE has, for all practical purposes, completed discussions of a new standard “CIE S 009/E: 2002 Photobiological Safety of Lamps and Lamp Systems”1), and it was adopted without any amendments. On the other hand, some national standards (for example, in Russia) have for decades insisted on UVA+UVB radiation being used for prophylactic purposes at actinic erythemal doses (around 140 J m-2 per 8 hours of irradiation), which are significantly higher than prohibitive doses of actinic UV hazard (30 J m-2) suggested in the CIE standard. It seems that this arisen situation is to be thought about more carefully.

  10. The application of "Helios" supercomputer in radiation safety studies for the IFMIF

    NASA Astrophysics Data System (ADS)

    Kondo, Keitaro; Fischer, Ulrich; Gröschel, Friedrich; Heinzel, Volker; Leichtle, Dieter; Serikov, Arkady

    2014-06-01

    The HELIOS supercomputer system at International Fusion Energy Research Centre, Aomori, Japan has been extensively utilized in radiation safety studies for the International Fusion Materials Irradiation Facility (IFMIF). This paper is focusing on the neutronic analysis to support the layout of the high energy beam transport (HEBT) section of IFMIF. The McDeLicious-11 Monte Carlo code, which is an enhancement to MCNP5, was utilized in order to simulate the neutron generation in the IFMIF lithium target through d-Li(d,xn) reactions and the R2Smesh approach was utilized to evaluate the ambient dose distribution after shutdown. The necessary thickness of the biological shielding and additional local shielding for the HEBT section has been evaluated. The accessibility of HEBT rooms and a necessary cooling time is discussed based on the result of shutdown dose analysis.

  11. An initial radiation safety needs assessment of Costa Rica: the South Texas Chapter of the Health Physics Society's strategic planning appraisal for participation in the "Radiation Safety Without Borders" initiative.

    PubMed

    Emery, Robert J; Felknor, S A

    2002-05-01

    In response to the Health Physics Society's recent 'radiation safety without borders" initiative, the South Texas Chapter of the Health Physics Society selected Costa Rica as its partner country of choice. To develop an understanding of the radiation safety needs of this country, the fall 2001 University of Texas Health Science Center at Houston School of Public Health Environmental Radiation and Radioactivity class was tasked with the assignment of assessing the possible radiation safety needs and concerns for this country. The assignment culminated in a class presentation to the membership of the South Texas Chapter during its annual fall meeting. Using library and web based resources, tile students reviewed a number of public health and radiation-related topics. Life expectancies were found to be equivalent to the United States, even though significant differences in per capita health expenditures were noted. Costa Rica exhibited lower population mortality rates from major causes such as cardiovascular diseases, neoplasms, and external sources. Maternal and infant mortality rates were found to be much higher in Costa Rica than in the United States. Naturally occurring radiation sources such as uranium deposits were not identified as apparent major radiation issues of concern, although ultraviolet radiation exposures are consistently high. Several recent events in the country and the region involving patient overexposures suggest that concerns are likely focused on ensuring the proper use and maintenance of healing arts radiation equipment. The lack of available information on radioactive waste disposal suggests that waste handling also may be an issue warranting attention. The exercise proved to be very educational for the students, and the information gathered will serve to focus the Chapter's efforts when technical exchanges are initiated. The importance of linking this initiative to other existing programs within the country is also discussed. PMID:12003035

  12. Technical support for the Ukrainian State Committee for Nuclear Radiation Safety on specific waste issues

    SciTech Connect

    Little, C.A.

    1995-07-01

    The government of Ukraine, a now-independent former member of the Soviet Union, has asked the United States to assist its State Committee for Nuclear and Radiation Safety (SCNRS) in improving its regulatory control in technical fields for which it has responsibility. The US Nuclear Regulatory Commission (NRC) is providing this assistance in several areas, including management of radioactive waste and spent fuel. Radioactive wastes resulting from nuclear power plant operation, maintenance, and decommissioning must be stored and ultimately disposed of appropriately. In addition, radioactive residue from radioisotopes used in various industrial and medical applications must be managed. The objective of this program is to provide the Ukrainian SCNRS with the information it needs to establish regulatory control over uranium mining and milling activities in the Zheltye Vody (Yellow Waters) area and radioactive waste disposal in the Pripyat (Chernobyl) area among others. The author of this report, head of the Environmental Technology Section, Health Sciences Research Division of Oak Ridge National Laboratory, accompanied NRC staff to Ukraine to meet with SCNRS staff and visit sites in question. The report highlights problems at the sites visited and recommends license conditions that SCNRS can require to enhance safety of handling mining and milling wastes. The author`s responsibility was specifically for the visit to Zheltye Vody and the mining and milling waste sites associated with that facility. An itinerary for the Zheltye Vody portion of the trip is included as Appendix A.

  13. Application of an Informatics-Based Decision-Making Framework and Process to the Assessment of Radiation Safety in Nanotechnology

    DOE PAGESBeta

    Hoover, Mark D.; Myers, David S.; Cash, Leigh J.; Guilmette, Raymond A.; Kreyling, Wolfgang G.; Oberdörster, Günter; Smith, Rachel; Cassata, James R.; Boecker, Bruce B.; Grissom, Michael P.

    2015-01-01

    The National Council on Radiation Protection and Measurements (NCRP) has established NCRP Scientific Committee 2-6 to develop a report on the current state of knowledge and guidance for radiation safety programs involved with nanotechnology. Nanotechnology is the understanding and control of matter at the nanoscale, at dimensions between approximately 1 and 100 nanometers, where unique phenomena enable novel applications. While the full report is in preparation, this article presents and applies an informatics-based decision-making framework and process through which the radiation protection community can anticipate that nano-enabled applications, processes, nanomaterials, and nanoparticles are likely to become present or are alreadymore » present in radiation-related activities; recognize specific situations where environmental and worker safety, health, well-being, and productivity may be affected by nano-related activities; evaluate how radiation protection practices may need to be altered to improve protection; control information, interpretations, assumptions, and conclusions to implement scientifically sound decisions and actions; and confirm that desired protection outcomes have been achieved. This generally applicable framework and supporting process can be continuously applied to achieve health and safety at the convergence of nanotechnology and radiation-related activities.« less

  14. Application of an Informatics-Based Decision-Making Framework and Process to the Assessment of Radiation Safety in Nanotechnology

    SciTech Connect

    Hoover, Mark D.; Myers, David S.; Cash, Leigh J.; Guilmette, Raymond A.; Kreyling, Wolfgang G.; Oberdörster, Günter; Smith, Rachel; Cassata, James R.; Boecker, Bruce B.; Grissom, Michael P.

    2015-01-01

    The National Council on Radiation Protection and Measurements (NCRP) has established NCRP Scientific Committee 2-6 to develop a report on the current state of knowledge and guidance for radiation safety programs involved with nanotechnology. Nanotechnology is the understanding and control of matter at the nanoscale, at dimensions between approximately 1 and 100 nanometers, where unique phenomena enable novel applications. While the full report is in preparation, this article presents and applies an informatics-based decision-making framework and process through which the radiation protection community can anticipate that nano-enabled applications, processes, nanomaterials, and nanoparticles are likely to become present or are already present in radiation-related activities; recognize specific situations where environmental and worker safety, health, well-being, and productivity may be affected by nano-related activities; evaluate how radiation protection practices may need to be altered to improve protection; control information, interpretations, assumptions, and conclusions to implement scientifically sound decisions and actions; and confirm that desired protection outcomes have been achieved. This generally applicable framework and supporting process can be continuously applied to achieve health and safety at the convergence of nanotechnology and radiation-related activities.

  15. Evaluation of Safety in a Radiation Oncology Setting Using Failure Mode and Effects Analysis

    SciTech Connect

    Ford, Eric C. Gaudette, Ray; Myers, Lee; Vanderver, Bruce; Engineer, Lilly; Zellars, Richard; Song, Danny Y.; Wong, John; DeWeese, Theodore L.

    2009-07-01

    Purpose: Failure mode and effects analysis (FMEA) is a widely used tool for prospectively evaluating safety and reliability. We report our experiences in applying FMEA in the setting of radiation oncology. Methods and Materials: We performed an FMEA analysis for our external beam radiation therapy service, which consisted of the following tasks: (1) create a visual map of the process, (2) identify possible failure modes; assign risk probability numbers (RPN) to each failure mode based on tabulated scores for the severity, frequency of occurrence, and detectability, each on a scale of 1 to 10; and (3) identify improvements that are both feasible and effective. The RPN scores can span a range of 1 to 1000, with higher scores indicating the relative importance of a given failure mode. Results: Our process map consisted of 269 different nodes. We identified 127 possible failure modes with RPN scores ranging from 2 to 160. Fifteen of the top-ranked failure modes were considered for process improvements, representing RPN scores of 75 and more. These specific improvement suggestions were incorporated into our practice with a review and implementation by each department team responsible for the process. Conclusions: The FMEA technique provides a systematic method for finding vulnerabilities in a process before they result in an error. The FMEA framework can naturally incorporate further quantification and monitoring. A general-use system for incident and near miss reporting would be useful in this regard.

  16. Improvement of microbiological safety of sous-vide meals by gamma radiation

    NASA Astrophysics Data System (ADS)

    Farkas, J.; Polyák-Fehér, K.; Andrássy, É.; Mészáros, L.

    2002-03-01

    Experimental batches of smoked-cured pork in stewed beans sauce were inoculated with spores of psychrotrophic Bacillus cereus, more heat and radiation resistant than spores of non-proteolytic C. botulinum. After vacuum packaging, the meals were treated with combinations of pasteurizing heat treatments and gamma irradiation of 5 kGy. Prior and after treatments, and periodically during storage at 10°C, total aerobic and total anerobic viable cell counts, and selectively, the viable cell counts of B. cereus and sulphite-reducing clostridia have been determined. The effects of the treatment order as well as addition of nisin to enhance the preservative efficiency of the physical treatments were also studied. Heat-sensitization of bacterial spores surviving irradiation occurred. The quality-friendly sous-vide cooking in combination with this medium dose gamma irradiation and/or nisin addition increased considerably the microbiological safety and the keeping quality of the meals studied. However, approx. 40% loss of thiamin content occurred as an effect of combination treatments, and adverse sensorial effects may also limit the feasible radiation doses or the usable concentrations of nisin.

  17. The Cold War legacy of regulatory risk analysis: The Atomic Energy Commission and radiation safety

    NASA Astrophysics Data System (ADS)

    Boland, Joseph B.

    From its inception in 1946 the Atomic Energy Commission pioneered the use of risk analysis as a mode of regulatory rationality and political rhetoric, yet historical treatments of risk analysis nearly always overlook the important role it played in the administration of atomic energy during the early Cold War. How this absence from history has been achieved and why it characterizes most historical accounts are the subjects of Chapter II. From there, this study goes on to develop the thesis that the advent of the atomic bomb was a world-shattering event that forced the Truman administration to choose between two novel alternatives: (1) movement towards global governance based initially on cooperative control of atomic energy or (2) unsparing pursuit of nuclear superiority. I refer to these as nuclear internationalism and nuclear nationalism, respectively. Each defined a social risk hierarchy. With the triumph of nuclear nationalism, nuclear annihilation was designated the greatest risk and a strong nuclear defense the primary means of prevention. The AEC's mission in the 1950s consisted of the rapid development of a nuclear arsenal, continual improvements in weapons technologies, and the promotion of nuclear power. The agency developed a risk-based regulatory framework through its dominant position within the National Committee on Radiation Protection. It embraced a technocratic model of risk analysis whose articulation and application it controlled, largely in secret. It used this to undergird a public rhetoric of reassurance and risk minimization. In practice, safety officials adjusted exposure levels within often wide parameters and with considerable fluidity in order to prevent safety concerns from interfering with operations. Secrecy, the political climate of the time, and a lack of accountability enabled the agency to meld technical assessments with social value judgments in a manner reflective of nuclear nationalism's risk hierarchy. In the late fifties

  18. Applications of radiation processing in combination with conventional treatments to assure food safety: New development

    NASA Astrophysics Data System (ADS)

    Lacroix, M.; Turgis, M.; Borsa, J.; Millette, M.; Salmieri, S.; Caillet, S.; Han, J.

    2009-11-01

    Spice extracts under the form of essential oils (Eos) were tested for their efficiency to increase the relative bacterial radiosensitivity (RBR) of Listeria monocytogenes, Escherichia coli and Salmonellatyphi in culture media under different atmospheric conditions. The selected Eos were tested for their ability to reduce the dose necessary to eliminate E. coli and S.typhi in medium fat ground beef (23% fat) and Listeria in ready-to-eat carrots when packed under air or under atmosphere rich in oxygen (MAP). Results have demonstrated that depending of the compound added and the combined treatment used, the RBR increased from 2 to 4 times. In order to evaluate the industrial feasibility, EOs were added in ground beef at a concentration which does not affect the taste and treated at a dose of 1.5 kGy. The content of total mesophilic aerobic, E. coli, Salmonella, total coliform, lactic acid bacteria, and Pseudomonas was determined during 28 days. The results showed that the combined treatment (radiation and EOs) can eliminate Salmonella and E. coli when done under air. When done under MAP, Pseudomonas could be eliminated and a shelf life of more than 28 days was observed. An active edible coating containing EOs was also developed and sprayed on ready-to-eat carrots before radiation treatment and Listeria was evaluated. A complete inhibition of Listeria was obtained at a dose of 0.5 kGy when applied under MAP. Our results have shown that the combination of an edible coating, MAP, and radiation can be used to maintain the safety of meat and vegetables.

  19. Radiation Segmentectomy: A Novel Approach to Increase Safety and Efficacy of Radioembolization

    SciTech Connect

    Riaz, Ahsun; Gates, Vanessa L.; Atassi, Bassel; Lewandowski, Robert J.; Mulcahy, Mary F.; Ryu, Robert K.; Sato, Kent T.; Baker, Talia; Kulik, Laura; Gupta, Ramona; Abecassis, Michael; Benson, Al B.; Omary, Reed; Millender, Laura; Kennedy, Andrew; Salem, Riad

    2011-01-01

    Purpose: To describe a technique of segmental radioembolization for the treatment of patients with unresectable hepatocellular carcinoma (HCC). Radiation segmentectomy was defined as radioembolization of two or fewer hepatic segments. We sought to (1) calculate dose when activity is delivered segmentally assuming uniform and nonuniform distribution and, (2) determine safety and efficacy of this novel technique. Methods and Materials: A total of 84 patients with HCC who were treated with {sup 90}Y radioembolization using a segmental approach were included in this analysis. The dose delivered to the segment was calculated assuming uniform and nonuniform microsphere distribution within the treatment volume. To calculate dose assuming nonuniform distribution, a tumor hypervascularity ratio was assigned. Posttreatment response (using size and necrosis guidelines), toxicity, time to progression, and survival were determined. Results: The median treatment volume was 110 cm{sup 3}. The median radiation-naive liver volume was 1403 cm{sup 3}. The median dose delivered to the segment(s) assuming uniform distribution was 521 Gy. Taking into account tumor hypervascularity (nonuniform distribution), the median dose delivered to the tumor and normal infused hepatic volume was 1214 Gy and 210 Gy, respectively. Response by size and necrosis guidelines was seen in 59% and 81% of patients. Grade 3/4 biochemical toxicities were observed in 8 patients (9%). Median time to progression was 13.6 months (95% confidence interval, 9.3-18.7 months); median survival was 26.9 months (95% confidence interval, 20.5-30.2 months). Conclusions: Radiation segmentectomy is a safe and efficacious method of selectively delivering high dose to the tumor with minimal exposure of normal parenchyma.

  20. Criteria for personal dosimetry in mixed radiation fields in space. [analyzing trapped protons, tissue disintegration stars, and neutrons

    NASA Technical Reports Server (NTRS)

    Schaefer, H. J.

    1974-01-01

    The complexity of direct reading and passive dosimeters for monitoring radiation is studied to strike the right balance of compromise to simplify the monitoring procedure. Trapped protons, tissue disintegration stars, and neutrons are analyzed.

  1. 78 FR 51754 - Request To Modify License by Replacing Security Plan With New Radiation Safety Plan; U.S...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-21

    ...The U.S. Nuclear Regulatory Commission (NRC) has received, by letter dated June 21, 2013 (actual receipt by NRC was July 18, 2013), a license amendment application from the U.S. Department of the Army (the licensee) for its Jefferson Proving Ground (JPG) site located in Madison, Indiana, requesting to replace its security plan with a new radiation safety...

  2. Criteria for Developing Criteria Sets.

    ERIC Educational Resources Information Center

    Martin, James L.

    Criteria sets are a necessary step in the systematic development of evaluation in education. Evaluation results from the combination of criteria and evidence. There is a need to develop explicit tools for evaluating criteria, similar to those used in evaluating evidence. The formulation of such criteria depends on distinguishing between terms…

  3. Managing NIF safety equipment in a high neutron and gamma radiation environment.

    PubMed

    Datte, Philip; Eckart, Mark; Jackson, Mark; Khater, Hesham; Manuel, Stacie; Newton, Mark

    2013-06-01

    The National Ignition Facility (NIF) is a 192 laser beam facility that supports the Inertial Confinement Fusion program. During the ignition experimental campaign, the NIF is expected to perform shots with varying fusion yield producing 14 MeV neutrons up to 20 MJ or 7.1 × 10(18) neutrons per shot and a maximum annual yield of 1,200 MJ. Several infrastructure support systems will be exposed to varying high yield shots over the facility's 30-y life span. In response to this potential exposure, analysis and testing of several facility safety systems have been conducted. A detailed MCNP (Monte Carlo N-Particle Transport Code) model has been developed for the NIF facility, and it includes most of the major structures inside the Target Bay. The model has been used in the simulation of expected neutron and gamma fluences throughout the Target Bay. Radiation susceptible components were identified and tested to fluences greater than 10(13) (n cm(-2)) for 14 MeV neutrons and γ-ray equivalent. The testing includes component irradiation using a 60Co gamma source and accelerator-based irradiation using 4- and 14- MeV neutron sources. The subsystem implementation in the facility is based on the fluence estimates after shielding and survivability guidelines derived from the dose maps and component tests results. This paper reports on the evaluation and implementation of mitigations for several infrastructure safety support systems, including video, oxygen monitoring, pressure monitors, water sensing systems, and access control interfaces found at the NIF. PMID:23629064

  4. Fire protection design criteria

    SciTech Connect

    1997-03-01

    This Standard provides supplemental fire protection guidance applicable to the design and construction of DOE facilities and site features (such as water distribution systems) that are also provided for fire protection. It is intended to be used in conjunction with the applicable building code, national Fire Protection Association Codes and Standards, and any other applicable DOE construction criteria. This Standard, along with other delineated criteria, constitutes the basic criteria for satisfying DOE fire and life safety objectives for the design and construction or renovation of DOE facilities.

  5. Enhancing the role of case-oriented peer review to improve quality and safety in radiation oncology: Executive summary

    PubMed Central

    Marks, Lawrence B.; Adams, Robert D.; Pawlicki, Todd; Blumberg, Albert L.; Hoopes, David; Brundage, Michael D.; Fraass, Benedick A.

    2013-01-01

    This report is part of a series of white papers commissioned for the American Society for Radiation Oncology (ASTRO) Board of Directors as part of ASTRO's Target Safely Campaign, focusing on the role of peer review as an important component of a broad safety/quality assurance (QA) program. Peer review is one of the most effective means for assuring the quality of qualitative, and potentially controversial, patient-specific decisions in radiation oncology. This report summarizes many of the areas throughout radiation therapy that may benefit from the application of peer review. Each radiation oncology facility should evaluate the issues raised and develop improved ways to apply the concept of peer review to its individual process and workflow. This might consist of a daily multidisciplinary (eg, physicians, dosimetrists, physicists, therapists) meeting to review patients being considered for, or undergoing planning for, radiation therapy (eg, intention to treat and target delineation), as well as meetings to review patients already under treatment (eg, adequacy of image guidance). This report is intended to clarify and broaden the understanding of radiation oncology professionals regarding the meaning, roles, benefits, and targets for peer review as a routine quality assurance tool. It is hoped that this work will be a catalyst for further investigation, development, and study of the efficacy of peer review techniques and how these efforts can help improve the safety and quality of our treatments. PMID:24175002

  6. Plutonium storage criteria

    SciTech Connect

    Chung, D.; Ascanio, X.

    1996-05-01

    The Department of Energy has issued a technical standard for long-term (>50 years) storage and will soon issue a criteria document for interim (<20 years) storage of plutonium materials. The long-term technical standard, {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides,{close_quotes} addresses the requirements for storing metals and oxides with greater than 50 wt % plutonium. It calls for a standardized package that meets both off-site transportation requirements, as well as remote handling requirements from future storage facilities. The interim criteria document, {open_quotes}Criteria for Interim Safe Storage of Plutonium-Bearing Solid Materials{close_quotes}, addresses requirements for storing materials with less than 50 wt% plutonium. The interim criteria document assumes the materials will be stored on existing sites, and existing facilities and equipment will be used for repackaging to improve the margin of safety.

  7. Radiation safety during remediation of the SevRAO facilities: 10 years of regulatory experience.

    PubMed

    Sneve, M K; Shandala, N; Kiselev, S; Simakov, A; Titov, A; Seregin, V; Kryuchkov, V; Shcheblanov, V; Bogdanova, L; Grachev, M; Smith, G M

    2015-09-01

    In compliance with the fundamentals of the government's policy in the field of nuclear and radiation safety approved by the President of the Russian Federation, Russia has developed a national program for decommissioning of its nuclear legacy. Under this program, the State Atomic Energy Corporation 'Rosatom' is carrying out remediation of a Site for Temporary Storage of spent nuclear fuel (SNF) and radioactive waste (RW) at Andreeva Bay located in Northwest Russia. The short term plan includes implementation of the most critical stage of remediation, which involves the recovery of SNF from what have historically been poorly maintained storage facilities. SNF and RW are stored in non-standard conditions in tanks designed in some cases for other purposes. It is planned to transport recovered SNF to PA 'Mayak' in the southern Urals. This article analyses the current state of the radiation safety supervision of workers and the public in terms of the regulatory preparedness to implement effective supervision of radiation safety during radiation-hazardous operations. It presents the results of long-term radiation monitoring, which serve as informative indicators of the effectiveness of the site remediation and describes the evolving radiation situation. The state of radiation protection and health care service support for emergency preparedness is characterized by the need to further study the issues of the regulator-operator interactions to prevent and mitigate consequences of a radiological accident at the facility. Having in mind the continuing intensification of practical management activities related to SNF and RW in the whole of northwest Russia, it is reasonable to coordinate the activities of the supervision bodies within a strategic master plan. Arrangements for this master plan are discussed, including a proposed programme of actions to enhance the regulatory supervision in order to support accelerated mitigation of threats related to the nuclear legacy in the

  8. Making the invisible visible: a qualitative study of the values, attitudes and norms of radiologists relating to radiation safety.

    PubMed

    Fridell, Kent; Ekberg, Jessica

    2016-06-01

    Some shortcomings regarding safety have emerged in inspections by the Swedish Radiation Safety Authority of Swedish radiology departments which perform 5.4 million radiological examinations and 100 000 nuclear scans annually. To ensure safety in the healthcare system and to build a strong environment of radiation protection for patients (and for employees) there must be a strong culture of safety. To understand an organization's behaviour, decisions and actions it is important to study its cultural values. The aims of this study were to discuss how values, attitudes and norms affect radiologists' decisions as well as how they influence the implementation of various radiation protection measures. To investigate this, focus group interviews and in-depth individual interviews were performed in a sample from a number of radiology departments at hospitals in Sweden. The results show that the core value was derived from the patients' perspective with the focus on the knowledge that he or she has come to the healthcare system for a particular reason: to discover disease or, in the best case, to be declared healthy. The majority attitudes were based on experiences associated with aspects that the radiologist could not influence. This often concerns increased pressure on radiology investigations from clinics in the various operational units. Under the concept of norms, the radiologists in the study requested that the development of regulations and guidelines should be connected to issues of justification for various radiological queries. PMID:26947913

  9. Radiation safety considerations for the parasitic Final Focus Test Beam at SLAC

    SciTech Connect

    Rokni, S.H.; Iverson, R.H.; Keller, L.P.

    1996-11-01

    A low intensity electron beam parasitic to the operation of the Stanford Linear Collider (SLC) has been transported through the Final Focus Test Beam (FFTB) facility making secondary test beams available for users. Photons generated in collimation of the SLC electron and positron beams in the linac pass through a splitter magnet that deflects the primary beams away from the linac axis into the SLC beam lines. These photons are converted to electrons and positrons in a secondary production target located down beam on the linac axis. The secondary electrons are then transported through the FFTB beam line onto experimental detectors. The average power of the parasitic beam is very low, thus, it presents no hazards. However, various accident scenarios involving failure of the splitter magnet and the active protection devices could send much more powerful SLC beams (up to 90 kilo-watts) into this zero-degree secondary beam line. For the accident cases, the average power in the transmitted beam was calculated using the Monte Carlo programs EGS4 and TURTLE. Results from analysis of the radiation protection systems that assure safety during the parasitic operation are presented.

  10. Radiation prevulcanized natural rubber latex: Cytotoxicity and safety evaluation on animal

    NASA Astrophysics Data System (ADS)

    Keong, C. C.; Zin, W. M. Wan; Ibrahim, P.; Ibrahim, S.

    2010-05-01

    Radiation prevulcanized natural rubber latex (RVNRL) was claimed to be more user friendly than natural rubber latex prevulcanized by sulphur curing system. The absence of Type IV allergy inducing chemicals in RVNRL make it a suitable material for manufacturing of many kinds of latex products, especially those come into direct contact with users. This paper reveals and discusses the findings of cytotoxicity test and safety evaluation on animal for RVNRL. The test was done on RVNRL films prepared by coagulant dipping method and RVNRL dipped products produced by latex dipped product manufacturers. Cytotocixity test was carried out on mammalian cell culture American Type Culture Collection CCL 81, Vero. Results indicated that no cytotoxic effect from RVNRL films and products was found on the cell culture. Two animal studies, namely dermal sensitization study and primary skin irritation study, were done on gloves made from RVNRL. Albino white guinea pigs were used as test subjects in dermal sensitization study and results showed no sensitization induced by the application of test material in the guinea pigs. Primary skin irritation study was done on New Zealand white rabbits and results showed that the product tested was not corrosive and was not a primary irritant

  11. Enhancing VHTR Passive Safety and Economy with Thermal Radiation Based Direct Reactor Auxiliary Cooling System

    SciTech Connect

    Haihua Zhao; Hongbin Zhang; Ling Zou; Xiaodong Sun

    2012-06-01

    One of the most important requirements for Gen. IV Very High Temperature Reactor (VHTR) is passive safety. Currently all the gas cooled version of VHTR designs use Reactor Vessel Auxiliary Cooling System (RVACS) for passive decay heat removal. The decay heat first is transferred to the core barrel by conduction and radiation, and then to the reactor vessel by thermal radiation and convection; finally the decay heat is transferred to natural circulated air or water systems. RVACS can be characterized as a surface based decay heat removal system. The RVACS is especially suitable for smaller power reactors since small systems have relatively larger surface area to volume ratio. However, RVACS limits the maximum achievable power level for modular VHTRs due to the mismatch between the reactor power (proportional to volume) and decay heat removal capability (proportional to surface area). When the relative decay heat removal capability decreases, the peak fuel temperature increases, even close to the design limit. Annular core designs with inner graphite reflector can mitigate this effect; therefore can further increase the reactor power. Another way to increase the reactor power is to increase power density. However, the reactor power is also limited by the decay heat removal capability. Besides the safety considerations, VHTRs also need to be economical in order to compete with other reactor concepts and other types of energy sources. The limit of decay heat removal capability set by using RVACS has affected the economy of VHTRs. A potential alternative solution is to use a volume-based passive decay heat removal system, called Direct Reactor Auxiliary Cooling Systems (DRACS), to remove or mitigate the limitation on decay heat removal capability. DRACS composes of natural circulation loops with two sets of heat exchangers, one on the reactor side and another on the environment side. For the reactor side, cooling pipes will be inserted into holes made in the outer or

  12. A Systems Approach to Evaluating Ionizing Radiation: Six Focus Areas to Improve Quality, Efficiency, and Patient Safety

    PubMed Central

    Mower, Laura; Bushe, Chris

    2015-01-01

    Abstract: Ionizing radiation is an essential component of the care process. However, providers and patients may not be fully aware of the risks involved, the level of ionizing radiation delivered with various procedures, or the potential for harm through incidental overexposure or cumulative dose. Recent high-profile incidents demonstrating the devastating short-term consequences of radiation overexposure have drawn attention to these risks, but applicable solutions are lacking. Although various recommendations and guidelines have been proposed, organizational variability challenges providers to identify their own practical solutions. To identify potential failure modes and develop solutions to preserve patient safety within a large, national healthcare system, we assembled a multidisciplinary team to conduct a comprehensive analysis of practices surrounding the delivery of ionizing radiation. Workgroups were developed to analyze existing culture, processes, and technology to identify deficiencies and propose solutions. Six focus areas were identified: competency and certification; equipment; monitoring and auditing; education; clinical pathways; and communication and marketing. This manuscript summarizes this comprehensive, multidisciplinary, and systemic analysis of risk and provides examples to illustrate how these focus areas can be used to improve the use of ionizing radiation. The proposed solutions, once fully implemented, may advance patient safety and care. PMID:26042626

  13. A Systems Approach to Evaluating Ionizing Radiation: Six Focus Areas to Improve Quality, Efficiency, and Patient Safety.

    PubMed

    Perlin, Jonathan B; Mower, Laura; Bushe, Chris

    2013-09-19

    Ionizing radiation is an essential component of the care process. However, providers and patients may not be fully aware of the risks involved, the level of ionizing radiation delivered with various procedures, or the potential for harm through incidental overexposure or cumulative dose. Recent high-profile incidents demonstrating the devastating short-term consequences of radiation overexposure have drawn attention to these risks, but applicable solutions are lacking. Although various recommendations and guidelines have been proposed, organizational variability challenges providers to identify their own practical solutions. To identify potential failure modes and develop solutions to preserve patient safety within a large, national healthcare system, we assembled a multidisciplinary team to conduct a comprehensive analysis of practices surrounding the delivery of ionizing radiation. Workgroups were developed to analyze existing culture, processes, and technology to identify deficiencies and propose solutions. Six focus areas were identified: competency and certification; equipment; monitoring and auditing; education; clinical pathways; and communication and marketing. This manuscript summarizes this comprehensive, multidisciplinary, and systemic analysis of risk and provides examples to illustrate how these focus areas can be used to improve the use of ionizing radiation. The proposed solutions, once fully implemented, may advance patient safety and care. PMID:24102690

  14. A systems approach to evaluating ionizing radiation: six focus areas to improve quality, efficiency, and patient safety.

    PubMed

    Perlin, Jonathan B; Mower, Laura; Bushe, Chris

    2015-01-01

    Ionizing radiation is an essential component of the care process. However, providers and patients may not be fully aware of the risks involved, the level of ionizing radiation delivered with various procedures, or the potential for harm through incidental overexposure or cumulative dose. Recent high-profile incidents demonstrating the devastating short-term consequences of radiation overexposure have drawn attention to these risks, but applicable solutions are lacking. Although various recommendations and guidelines have been proposed, organizational variability challenges providers to identify their own practical solutions. To identify potential failure modes and develop solutions to preserve patient safety within a large, national healthcare system, we assembled a multidisciplinary team to conduct a comprehensive analysis of practices surrounding the delivery of ionizing radiation. Workgroups were developed to analyze existing culture, processes, and technology to identify deficiencies and propose solutions. Six focus areas were identified: competency and certification; equipment; monitoring and auditing; education; clinical pathways; and communication and marketing. This manuscript summarizes this comprehensive, multidisciplinary, and systemic analysis of risk and provides examples to illustrate how these focus areas can be used to improve the use of ionizing radiation. The proposed solutions, once fully implemented, may advance patient safety and care. PMID:26042626

  15. Evaluation of radiation safety in (177)Lu-PSMA therapy and development of outpatient treatment protocol.

    PubMed

    Demir, Mustafa; Abuqbeitah, Mohammad; Uslu-Beşli, Lebriz; Yıldırım, Özlem; Yeyin, Nami; Çavdar, İffet; Vatankulu, Betül; Gündüz, Hüseyin; Kabasakal, Levent

    2016-06-01

    The aim of this study is to investigate the outpatient treatment protocol and radiation safety of a new-emerging lutetium-177 ((177)Lu) prostate specific membrane antigen (PSMA) therapy. This work analyzed the dose rate of 23 patients treated with 7400 MBq (177)Lu-PSMA at different distances (0, 0.25, 0.50, 1.0 and 2.0 m) and variable time marks (0, 1, 2, 4, 18, 24, 48 and 120 h) after the termination of infusion. Blood samples were withdrawn from 17 patients within the same group at 3, 10, 20, 40, 60 and 90 min and 2, 3, 24 h after termination of infusion. Seven different patients were asked to collect urine for 24 h and a gamma well counter was used for counting samples. Family members were invited to wear an optically stimulated luminescence dosimeter whenever they were in the proximity of the patients up to 4-5 d. The total dose of the medical team including the radiopharmacist, physicist, physician, nurse, and nuclear medicine technologist was estimated by an electronic personnel dosimeter. The finger dose was determined using a ring thermoluminescent dosimeter for the radiopharmacist and nurse. The mean dose rate at 1 m after 4 h and 6 h was 23  ±  6 μSv h(-1) and 15  ±  4 μSv h(-1) respectively. The mean total dose to 23 caregivers was 202.3  ±  42.7 μSv (range: 120-265 μSv). The radiation dose of the nurse and radiopharmacist was 6 and 4 μSv per patient, respectively, whereas the dose of the physicist and physician was 2 μSv. The effective half life of blood distribution and early elimination was 0.4  ±  0.1 h and 5  ±  1 h, respectively. Seven patients excreted a mean of 45% (range: 32%-65%) from the initial activity in 6 h. Our findings demonstrate that (177)Lu-PSMA is a safe treatment modality to be applied as an outpatient protocol, since the dose rate decreases below the determined threshold of  <30 μSv h(-1) after approximately 5 h and degrades to 20 μSv h(-1) after 6

  16. Analysis of radiation environmental safety for China's Spallation Neutron Source (CSNS)

    NASA Astrophysics Data System (ADS)

    Wang, Qing-Bin; Wu, Qing-Biao; Ma, Zhong-Jian; Zhang, Qing-Jiang; Li, Nan; Wu, Jing-Min; Liu, Jian; Zhang, Gang

    2010-07-01

    The China Spallation Neutron Source (CSNS) is going to be located in Dalang Town, Dongguan City in the Guangdong Province. In this paper we report the results of the parameters related with environment safety based on experiential calculations and Monte Carlo simulations. The main project of the accelerator is an under ground construction. On top there is a 0.5 m concrete and 5.0 m soil covering for shielding, which can reduce the dose out of the tunnel's top down to 0.2 μSv/h. For the residents on the boundary of the CSNS, the dose produced by skyshine, which is caused by the penetrated radiation leaking from the top of the accelerator, is no more than 0.68 μSv/a. When CSNS is operating normally, the maximal annual effective dose due to the emission of gas from the tunnel is 2.40×10-3 mSv/a to the public adult, and 2.29×10-3 mSv/a to a child, both values are two orders of magnitude less than the limiting value for control and management. CSNS may give rise to an activation of the soil and groundwater in the nearest tunnels, where the main productions are 3H, 7Be, 22Na, 54Mn, etc. But the specific activity is less than the exempt specific activity in the national standard GB13376-92. So it is safe to say that the environmental impact caused by the activation of soil and groundwater is insignificant. To sum up, for CSNS, as a powerful neutron source device, driven by a high-energy high-current proton accelerator, a lot of potential factors affecting the environment exist. However, as long as effective shieldings for protection are adopted and strict rules are drafted, the environmental impact can be kept under control within the limits of the national standard.

  17. Workflow Enhancement (WE) Improves Safety in Radiation Oncology: Putting the WE and Team Together

    SciTech Connect

    Chao, Samuel T.; Meier, Tim; Hugebeck, Brian; Reddy, Chandana A.; Godley, Andrew; Kolar, Matt; Suh, John H.

    2014-07-15

    Purpose: To review the impact of a workflow enhancement (WE) team in reducing treatment errors that reach patients within radiation oncology. Methods and Materials: It was determined that flaws in our workflow and processes resulted in errors reaching the patient. The process improvement team (PIT) was developed in 2010 to reduce errors and was later modified in 2012 into the current WE team. Workflow issues and solutions were discussed in PIT and WE team meetings. Due to tensions within PIT that resulted in employee dissatisfaction, there was a 6-month hiatus between the end of PIT and initiation of the renamed/redesigned WE team. In addition to the PIT/WE team forms, the department had separate incident forms to document treatment errors reaching the patient. These incident forms are rapidly reviewed and monitored by our departmental and institutional quality and safety groups, reflecting how seriously these forms are treated. The number of these incident forms was compared before and after instituting the WE team. Results: When PIT was disbanded, a number of errors seemed to occur in succession, requiring reinstitution and redesign of this team, rebranded the WE team. Interestingly, the number of incident forms per patient visits did not change when comparing 6 months during the PIT, 6 months during the hiatus, and the first 6 months after instituting the WE team (P=.85). However, 6 to 12 months after instituting the WE team, the number of incident forms per patient visits decreased (P=.028). After the WE team, employee satisfaction and commitment to quality increased as demonstrated by Gallup surveys, suggesting a correlation to the WE team. Conclusions: A team focused on addressing workflow and improving processes can reduce the number of errors reaching the patient. Time is necessary before a reduction in errors reaching patients will be seen.

  18. [A questionnaire about radiation safety management of the draining-water system at nuclear medicine facilities].

    PubMed

    Shizukuishi, Kazuya; Watanabe, Hiroshi; Narita, Hiroto; Kanaya, Shinichi; Kobayashi, Kazumi; Yamamoto, Tetsuo; Tsukada, Masaru; Iwanaga, Tetsuo; Ikebuchi, Shuji; Kusama, Keiji; Tanaka, Mamoru; Namiki, Norio; Fuiimura, Youko; Horikoshi, Akiko; Inoue, Tomio; Kusakabe, Kiyoko

    2004-05-01

    We conducted a questionnaire survey about radiation-safety management condition in Japanese nuclear medicine facilities to make materials of proposition for more reasonable management of medical radioactive waste. We distributed a questionnaire to institutions equipped with Nuclear Medicine facilities. Of 1,125 institutions, 642 institutes (52.8%) returned effective answers. The questionnaire covered the following areas: 1) scale of an institution, 2) presence of enforcement of radiotherapy, 3) system of a tank, 4) size and number of each tank, 5) a form of draining-water system, 6) a displacement in a radioactive rays management area, 7) a measurement method of the concentration of medical radioactive waste in draining water system, 8) planned and used quantity of radioisotopes for medical examination and treatment, 9) an average displacement of hospital for one month. In most institutions, a ratio of dose limitation of radioisotope in draining-water system was less than 1.0, defined as an upper limitation in ordinance. In 499 hospitals without facilities of hospitalization for unsealed radioisotope therapy, 473 hospitals reported that sum of ratios of dose limits in a draining-water system was less than 1.0. It was calculated by used dose of radioisotope and monthly displacement from hospital, on the premise that all used radioisotope entered in the general draining-water system. When a drainage including radioactivity from a controlled area join with that from other area before it flows out of a institution, it may be diluted and its radioactive concentration should be less than its upper limitation defined in the rule. Especially, in all institutions with a monthly displacement of more than 25,000 m3, the sum of ratio of the concentration of each radionuclide to the concentration limit dose calculated by used dose of radioisotope, indicated less than 1.0. PMID:15354724

  19. Less restrictive patient-specific radiation-safety precautions can be safely prescribed after permanent seed implantation

    PubMed Central

    Dauer, Lawrence T.; Kollmeier, Marisa A.; Williamson, Matthew J.; St. Germain, Jean; Altamirano, Joaquin; Yamada, Yoshiya; Zelefsky, Michael J.

    2013-01-01

    PURPOSE To utilize radiation exposure-rate measurements to determine patient-specific radiation-safety instructions with the aim of reducing unnecessary precaution times and to evaluate potential doses to members of the public. Materials and Methods Radiation exposure-rate measurements were obtained from 1279 patients with stage T1-2 prostate cancer who underwent transperineal I-125 or Pd-103 seed implantation from January 1995 through July 2008. An algorithm was developed from these measurements to determine required precaution times needed to maintain public effective doses below 50% of the limits for specific exposure situations. Results The median air kerma rates at 30 cm from the anterior skin surface were 4.9 μGy/h (range: 0.1-31.5) for I-125 and 1.5 μGy/h (range: 0.02-14.9) for Pd-103. Derived algorithms depended primarily upon the half-life, Tp, the measured exposure rate at 30 cm, and specific exposure situation factors. For the typical Pd-103 patient, no radiation-safety precautions are required. For the typical I-125 patient, no precautions are required for co-workers, nonpregnant adults that do not sleep with the family member, or nonpregnant adults that sleep with the patient. Typical I-125 patients should only need to avoid sleeping in the “spoon” position (i.e., in contact) with pregnant adults and avoid holding a child for long periods of time in the lap for about 2 months. Conclusions The large number of cases available for this study permitted the development of an algorithm to simply determine patient-specific radiation-safety instructions. Resulting precaution times are significantly less restrictive than precaution times generally prescribed currently. PMID:19853532

  20. Safety and Efficacy of Stereotactic Body Radiation Therapy in the Treatment of Pulmonary Metastases from High Grade Sarcoma

    PubMed Central

    Mehta, Niraj; Selch, Michael; Lee, Jay M.; Eilber, Fritz C.; Chmielowski, Bartosz; Agazaryan, Nzhde; Steinberg, Michael

    2013-01-01

    Introduction. Patients with high-grade sarcoma (HGS) frequently develop metastatic disease thus limiting their long-term survival. Lung metastases (LM) have historically been treated with surgical resection (metastasectomy). A potential alternative for controlling LM could be stereotactic body radiation therapy (SBRT). We evaluated the outcomes from our institutional experience utilizing SBRT. Methods. Sixteen consecutive patients with LM from HGS were treated with SBRT between 2009 and 2011. Routine radiographic and clinical follow-up was performed. Local failure was defined as CT progression on 2 consecutive scans or growth after initial shrinkage. Radiation pneumonitis and radiation esophagitis were scored using Common Toxicity Criteria (CTC) version 3.0. Results. All 16 patients received chemotherapy, and a subset (38%) also underwent prior pulmonary metastasectomy. Median patient age was 56 (12–85), and median follow-up time was 20 months (range 3–43). A total of 25 lesions were treated and evaluable for this analysis. Most common histologies were leiomyosarcoma (28%), synovial sarcoma (20%), and osteosarcoma (16%). Median SBRT prescription dose was 54 Gy (36–54) in 3-4 fractions. At 43 months, local control was 94%. No patient experienced G2-4 radiation pneumonitis, and no patient experienced radiation esophagitis. Conclusions. Our retrospective experience suggests that SBRT for LM from HGS provides excellent local control and minimal toxicity. PMID:24198717

  1. 10 CFR 39.41 - Design and performance criteria for sources.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false Design and performance criteria for sources. 39.41 Section 39.41 Energy NUCLEAR REGULATORY COMMISSION LICENSES AND RADIATION SAFETY REQUIREMENTS FOR WELL... sealed source contains licensed material whose chemical and physical forms are as insoluble...

  2. 10 CFR 39.41 - Design and performance criteria for sources.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Design and performance criteria for sources. 39.41 Section 39.41 Energy NUCLEAR REGULATORY COMMISSION LICENSES AND RADIATION SAFETY REQUIREMENTS FOR WELL... sealed source contains licensed material whose chemical and physical forms are as insoluble...

  3. 10 CFR 39.41 - Design and performance criteria for sources.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 1 2014-01-01 2014-01-01 false Design and performance criteria for sources. 39.41 Section 39.41 Energy NUCLEAR REGULATORY COMMISSION LICENSES AND RADIATION SAFETY REQUIREMENTS FOR WELL... test source must be held at −40 °C for 20 minutes, 600 °C for 1 hour, and then be subject to a...

  4. Goal Structured Notation in a Radiation Hardening Safety Case for COTS-Based Spacecraft

    NASA Technical Reports Server (NTRS)

    Witulski, Arthur; Austin, Rebekah; Reed, Robert; Karsai, Gabor; Mahadevan, Nag; Sierawski, Brian; Evans, John; LaBel, Ken

    2016-01-01

    A systematic approach is presented to constructing a radiation assurance case using Goal Structured Notation (GSN) for spacecraft containing COTS parts. The GSN paradigm is applied to an SRAM single-event upset experiment board designed to fly on a CubeSat November 2016. Construction of a radiation assurance case without use of hardened parts or extensive radiation testing is discussed.

  5. Lessons learned from Fukushima Daiichi nuclear power plant accident: efficient education items of radiation safety for general public.

    PubMed

    Ohno, K; Endo, K

    2015-07-01

    The Fukushima Daiichi nuclear power plant (FNP-1) accident, while as tragic as the tsunami, was a man-made disaster created by the ignorance of the effects of radiation and radioactive materials. Therefore, it is important that all specialists in radiation protection in medicine sympathize with the anxiety of the general public regarding the harmful effects of radiation and advise people accordingly. All questions and answers were collected related to inquiries from the general public that were posted to reliable websites, including those of the government and radiation-related organizations, from March 2011 to November 2012. The questions were summarized and classified by similarity of content. (1) The total number of questions is 372. The content was broadly classified into three categories: inquiries for radiation-related knowledge and about health effects and foods. The questions asked to obtain radiation-related knowledge were the most common, accounting for 38 %. Thirty-six percentage of the questions were related to health effects, and 26 % involved foods, whereas 18 % of the questions were related to children and pregnancy. (2) The change over time was investigated in 290 questions for which the time of inquiry was known. Directly after the earthquake, the questions were primarily from people seeking radiation-related knowledge. Later, questions related to health effects increased. The anxiety experienced by residents following the nuclear accident was caused primarily by insufficient knowledge related to radiation, concerns about health effects and uncertainties about food and water safety. The development of educational materials focusing on such content will be important for risk communication with the general public in countries with nuclear power plants. Physicians and medical physicist should possess the ability to respond to questions such as these and should continue with medical examinations and treatments in a safe and appropriate manner. PMID

  6. Progress and Status on the Development of NASA's Nowcast of Atmospheric Ionizing Radiation for Aviation Safety (NAIRAS) model

    NASA Astrophysics Data System (ADS)

    Mertens, C. J.; Tobiska, W. K.; Blattnig, S. R.; Kress, B. T.; Wiltberger, M. J.; Solomon, S. C.; Kunches, J.; Murray, J. J.

    2008-12-01

    The NASA Applied Sciences Program recently selected a project for funding through the Research Opportunities in Space and Earth Sciences (ROSES) solicitation. The project objective is to develop a nowcast prediction of air-crew radiation exposure from both background galactic cosmic rays (GCR) and solar energetic particle events (SEP) that may accompany solar storms. The new air-crew radiation exposure model is called the Nowcast of Atmospheric Ionizing Radiation for Aviation Safety (NAIRAS) model. NAIRAS will provide global, data-driven, real-time radiation dose predictions of biologically harmful radiation at commercial airline altitudes. Observations are utilized from the ground (neutron monitors), from the atmosphere (the NCEP reanalysis), and from space (NASA/ACE and NOAA/GOES). Atmospheric observations provide the overhead shielding information and the ground- and space-based observations provide boundary conditions on the incident GCR and SEP particle flux distributions for transport and dosimetry simulations. Dose rates are calculated using the parametric AIR (Atmospheric Ionizing Radiation) model and the physics-based HZETRN (High Charge and Energy Transport) code. In this paper we discuss the concept and design of the NAIRAS model, and present recent progress in the implementation and give examples of the model results. Specifically, we show predictions of representative annual background exposure levels and radiation exposure levels for selected SEP events during solar cycle 23, with emphasis on the high-latitude and polar region. We also characterize the suppression of the geomagnetic cutoff rigidity during these storm periods and their subsequent influence on atmospheric radiation exposure. We discuss the key uncertainties and areas that need improvement in both model and data, the timeline for project completion, and access to model results.

  7. GNS-12 Packaging design criteria

    SciTech Connect

    Clements, E.P., Westinghouse Hanford

    1996-07-24

    The purpose of this Packaging Design Criteria (PDC) is to provide criteria for the Safety Analysis Report for Packaging (SARP)(Onsite). The SARP provides the evaluation to demonstrate that the onsite transportation safety criteria are met for the transport and storage of the 324 Building vitrified encapsulated material in the GNS-12 cask. In this application, the approved PDC provides a formal set of standards for the payload requirements, and guidance for the current cask transport configuration and a revised storage seal and primary lid modification design.

  8. Historical Patterns in the Types of Procedures Performed and Radiation Safety Practices Used in Nuclear Medicine From 1945-2009.

    PubMed

    Van Dyke, Miriam E; Drozdovitch, Vladimir; Doody, Michele M; Lim, Hyeyeun; Bolus, Norman E; Simon, Steven L; Alexander, Bruce H; Kitahara, Cari M

    2016-07-01

    The authors evaluated historical patterns in the types of procedures performed in diagnostic and therapeutic nuclear medicine and the associated radiation safety practices used from 1945-2009 in a sample of U.S. radiologic technologists. In 2013-2014, 4,406 participants from the U.S. Radiologic Technologists (USRT) Study who previously reported working with medical radionuclides completed a detailed survey inquiring about the performance of 23 diagnostic and therapeutic radionuclide procedures and the use of radiation safety practices when performing radionuclide procedure-related tasks during five time periods: 1945-1964, 1965-1979, 1980-1989, 1990-1999, and 2000-2009. An overall increase in the proportion of technologists who performed specific diagnostic or therapeutic procedures was observed across the five time periods. Between 1945-1964 and 2000-2009, the median frequency of diagnostic procedures performed substantially increased (from 5 wk to 30 wk), attributable mainly to an increasing frequency of cardiac and non-brain PET scans, while the median frequency of therapeutic procedures performed modestly decreased (from 4 mo to 3 mo). Also a notable increase was observed in the use of most radiation safety practices from 1945-1964 to 2000-2009 (e.g., use of lead-shielded vials during diagnostic radiopharmaceutical preparation increased from 56 to 96%), although lead apron use dramatically decreased (e.g., during diagnostic imaging procedures, from 81 to 7%). These data describe historical practices in nuclear medicine and can be used to support studies of health risks for nuclear medicine technologists. PMID:27218293

  9. Gas-Cooled Fast Breeder Reactor Preliminary Safety Information Document, Amendment 10. GCFR residual heat removal system criteria, design, and performance

    SciTech Connect

    Not Available

    1980-09-01

    This report presents a comprehensive set of safety design bases to support the conceptual design of the gas-cooled fast breeder reactor (GCFR) residual heat removal (RHR) systems. The report is structured to enable the Nuclear Regulatory Commission (NRC) to review and comment in the licensability of these design bases. This report also presents information concerning a specific plant design and its performance as an auxiliary part to assist the NRC in evaluating the safety design bases.

  10. A proposed new handbook for the Federal Emergency Management Agency: Radiation safety in shelters

    NASA Astrophysics Data System (ADS)

    Haaland, C. M.

    1981-09-01

    A proposed replacement for the portion of the current Handbook for Radiological Monitoring that deals with protection of people in shelters from radiation from fallout resulting from nuclear war is presented. Basic information at a high school level is given on how to detect nuclear radiation, how to find and improve the safest places in a shelter, the necessity for and how to keep records on individual radiation exposures, and how to minimize exposures. Several procedures are introduced, some of which are based more on theoretical considerations than on actual experiments. These procedures include: (1) the method of time averaging radiation readings taken with one instrument in different locations of a large shelter while fallout is coming down and radiation levels ar climbing too rapidly for direct comparison of readings to determine the safest location; (2) the method of using one's own body to obtain directionality in radiation readings taken with a standard Civil Defense survey meter; (3) the method of using mutual shielding to reduce the average radiation exposure to shelter occupants; and (4) the ratio method for estimating radiation levels in hazardous areas.

  11. 49 CFR Appendix to Subpart H of... - Explanation of Pre-Authorization Safety Audit Evaluation Criteria for Non-North America-Domiciled...

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... experienced during the past 12 months. Recordable accident, as defined in 49 CFR 390.5, means an accident... Evaluation Criteria for Non-North America-Domiciled Motor Carriers Appendix to Subpart H of Part 385... Special Rules for New Entrant Non-North America-Domiciled Carriers Pt. 385, Subpt. H, App. Appendix...

  12. 49 CFR Appendix to Subpart H of... - Explanation of Pre-Authorization Safety Audit Evaluation Criteria for Non-North America-Domiciled...

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... experienced during the past 12 months. Recordable accident, as defined in 49 CFR 390.5, means an accident... Evaluation Criteria for Non-North America-Domiciled Motor Carriers Appendix to Subpart H of Part 385... Special Rules for New Entrant Non-North America-Domiciled Carriers Pt. 385, Subpt. H, App. Appendix...

  13. 49 CFR Appendix A to Subpart E of... - Explanation of Pre-Authorization Safety Audit Evaluation Criteria for Mexico-Domiciled Motor...

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... months. Recordable accident, as defined in 49 CFR 390.5, means an accident involving a commercial motor... Evaluation Criteria for Mexico-Domiciled Motor Carriers A Appendix A to Subpart E of Part 365 Transportation... OPERATING AUTHORITY Special Rules for Certain Mexico-domiciled Carriers Pt. 365, Subpt. E, App. A Appendix...

  14. On the radiation safety studies of space nuclear sources at the Scientific-Research Institute of Thermal Processes

    SciTech Connect

    Koroteev, A.S.; Gafarov, A.A.; Bakhtin, B.I.; Kosov, A.V. )

    1991-01-01

    The main directions and some results of the theoretical and experimental studies, carried out at the Scientific-Research Institute of Thermal Processes on the radiation safety (RS) problem of the space nuclear power sources (SNPS), are stated. The experimental base for SNPS aerodynamic heating and breakup research is described. Some results of studies on the development of RS system for SNPS of Cosmos-954''-type satellites and SNPS Topaz'' are represented. The main directions and results of research on the RS problem of radioisotope SNPS is showen. Some aspects of SNPS possible collisions with space debris in near-earth orbits is examined.

  15. [The control of radiation protection in the field of radiotherapy by the French Nuclear Safety Authority (ASN)].

    PubMed

    Godet, J-L

    2007-11-01

    During the last months, several incidents at radiotherapy services occurred in France; one of these accidents led to the death of several patients or required further heavy surgical acts. In this context, ASN (Autorité de sûreté nucléaire) issued an experimental guide for the notification of radiation protection events and achieved, in dialogue with professional organisations, a new scale intended to facilitate public information on radiotherapy incidents. ASN is also fully involved in the preparation of the action plan managed by the Health ministry in order to improve the safety of treatment in radiotherapy. PMID:17962062

  16. The Australian radiation protection and nuclear safety agency megavoltage photon thermoluminescence dosimetry postal audit service 2007-2010.

    PubMed

    Oliver, C P; Butler, D J; Webb, D V

    2012-03-01

    The Australian radiation protection and nuclear safety agency (ARPANSA) has continuously provided a level 1 mailed thermoluminescence dosimetry audit service for megavoltage photons since 2007. The purpose of the audit is to provide an independent verification of the reference dose output of a radiotherapy linear accelerator in a clinical environment. Photon beam quality measurements can also be made as part of the audit in addition to the output measurements. The results of all audits performed between 2007 and 2010 are presented. The average of all reference beam output measurements calculated as a clinically stated dose divided by an ARPANSA measured dose is 0.9993. The results of all beam quality measurements calculated as a clinically stated quality divided by an ARPANSA measured quality is 1.0087. Since 2011 the provision of all auditing services has been transferred from the Ionizing Radiation Standards section to the Australian Clinical Dosimetry Service (ACDS) which is currently housed within ARPANSA. PMID:22302465

  17. FHR Generic Design Criteria

    SciTech Connect

    Flanagan, G.F.; Holcomb, D.E.; Cetiner, S.M.

    2012-06-15

    The purpose of this document is to provide an initial, focused reference to the safety characteristics of and a licensing approach for Fluoride-Salt-Cooled High-Temperature Reactors (FHRs). The document does not contain details of particular reactor designs nor does it attempt to identify or classify either design basis or beyond design basis accidents. Further, this document is an initial attempt by a small set of subject matter experts to document the safety and licensing characteristics of FHRs for a larger audience. The document is intended to help in setting the safety and licensing research, development, and demonstration path forward. Input from a wider audience, further technical developments, and additional study will be required to develop a consensus position on the safety and licensing characteristics of FHRs. This document begins with a brief overview of the attributes of FHRs and then a general description of their anticipated safety performance. Following this, an overview of the US nuclear power plant approval process is provided that includes both test and power reactors, as well as the role of safety standards in the approval process. The document next describes a General Design Criteria (GDC)–based approach to licensing an FHR and provides an initial draft set of FHR GDCs. The document concludes with a description of a path forward toward developing an FHR safety standard that can support both a test and power reactor licensing process.

  18. FHR Generic Design Criteria

    SciTech Connect

    Flanagan, George F; Holcomb, David Eugene; Cetiner, Sacit M

    2012-06-01

    The purpose of this document is to provide an initial, focused reference to the safety characteristics of and a licensing approach for Fluoride-Salt-Cooled High-Temperature Reactors (FHRs). The document does not contain details of particular reactor designs nor does it attempt to identify or classify either design basis or beyond design basis accidents. Further, this document is an initial attempt by a small set of subject matter experts to document the safety and licensing characteristics of FHRs for a larger audience. The document is intended to help in setting the safety and licensing research, development, and demonstration path forward. Input from a wider audience, further technical developments, and additional study will be required to develop a consensus position on the safety and licensing characteristics of FHRs. This document begins with a brief overview of the attributes of FHRs and then a general description of their anticipated safety performance. Following this, an overview of the US nuclear power plant approval process is provided that includes both test and power reactors, as well as the role of safety standards in the approval process. The document next describes a General Design Criteria (GDC) - based approach to licensing an FHR and provides an initial draft set of FHR GDCs. The document concludes with a description of a path forward toward developing an FHR safety standard that can support both a test and power reactor licensing process.

  19. Initial experience with an 11 MeV self-shielded medical cyclotron on operation and radiation safety

    PubMed Central

    Pant, G. S.; Senthamizhchelvan, S.

    2007-01-01

    A self-shielded medical cyclotron (11 MeV) was commissioned at our center, to produce positron emitters, namely, 18F, 15O, 13N and 11C for positron emission tomography (PET) imaging. Presently the cyclotron has been exclusively used for the production of 18F- for 18F-FDG imaging. The operational parameters which influence the yield of 18F- production were monitored. The radiation levels in the cyclotron and radiochemistry laboratory were also monitored to assess the radiation safety status in the facility. The target material, 18O water, is bombarded with proton beam from the cyclotron to produce 18F- ion that is used for the synthesis of 18F-FDG. The operational parameters which influence the yield of 18F- were observed during 292 production runs out of a total of more than 400 runs. The radiation dose levels were also measured in the facility at various locations during cyclotron production runs and in the radiochemistry laboratory during 18F-FDG syntheses. It was observed that rinsing the target after delivery increased the number of production runs in a given target, as well as resulted in a better correlation between the duration of bombardment and the end of bombardment 18F- activity with absolutely clean target after being rebuilt. The radiation levels in the cyclotron and radiochemistry laboratory were observed to be well within prescribed limits with safe work practice. PMID:21157531

  20. Low Interrater Reliability in Grading of Rectal Bleeding Using National Cancer Institute Common Toxicity Criteria and Radiation Therapy Oncology Group Toxicity Scales: A Survey of Radiation Oncologists

    SciTech Connect

    Huynh-Le, Minh-Phuong; Zhang, Zhe; Tran, Phuoc T.; DeWeese, Theodore L.; Song, Daniel Y.

    2014-12-01

    Purpose: To measure concordance among genitourinary radiation oncologists in using the National Cancer Institute Common Toxicity Criteria (NCI CTC) and Radiation Therapy Oncology Group (RTOG) grading scales to grade rectal bleeding. Methods and Materials: From June 2013 to January 2014, a Web-based survey was sent to 250 American and Canadian academic radiation oncologists who treat prostate cancer. Participants were provided 4 case vignettes in which patients received radiation therapy and developed rectal bleeding and were asked for management plans and to rate the bleeding according to NCI CTC v.4 and RTOG late toxicity grading (scales provided). In 2 cases, participants were also asked whether they would send the patient for colonoscopy. A multilevel, random intercept modeling approach was used to assess sources of variation (case, respondent) in toxicity grading to calculate the intraclass correlation coefficient (ICC). Agreement on a dichotomous grading scale (low grades 1-2 vs high grades 3-4) was also assessed, using the κ statistic for multiple respondents. Results: Seventy-two radiation oncologists (28%) completed the survey. Forty-seven (65%) reported having either written or been principal investigator on a study using these scales. Agreement between respondents was moderate (ICC 0.52, 95% confidence interval [CI] 0.47-0.58) when using NCI CTC and fair using the RTOG scale (ICC 0.28, 95% CI 0.20-0.40). Respondents who chose an invasive management were more likely to select a higher toxicity grade (P<.0001). Using the dichotomous scale, we observed moderate agreement (κ = 0.42, 95% CI 0.40-0.44) with the NCI CTC scale, but only slight agreement with the RTOG scale (κ = 0.19, 95% CI 0.17-0.21). Conclusion: Low interrater reliability was observed among radiation oncologists grading rectal bleeding using 2 common scales. Clearer definitions of late rectal bleeding toxicity should be constructed to reduce this variability and avoid ambiguity in both

  1. Radiation Safety Aspects for Pulsed Photonuclear Assessment Techniques in Outdoor Operations

    SciTech Connect

    Daren R. Norman; James L. Jones; Brandon W. Blackburn; Allen Fisher; Scott M. Watson; Kevin J. Haskell; Alan W. Hunt; Mark Balzer

    2007-08-01

    As many pulsed photonuclear assessment (PPA) technologies are being developed for contraband detection within cargo container configurations, the radiation safe operation of source linacs for outdoor operations needs to be addressed. Idaho National Laboratory along with Idaho Accelerator Center are conducting field operations with high energy linacs in open outdoor configurations. The relevant information pertaining to the radiation regulations and dosimetry studies for these configurations will be presented for a prototypical 10 MeV PPA nuclear material detection system.

  2. 29 CFR 1904.4 - Recording criteria.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 29 Labor 5 2013-07-01 2013-07-01 false Recording criteria. 1904.4 Section 1904.4 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR RECORDING AND REPORTING OCCUPATIONAL INJURIES AND ILLNESSES Recordkeeping Forms and Recording Criteria § 1904.4 Recording criteria. (a)...

  3. The use of individual and societal risk criteria within the Dutch flood safety policy--nationwide estimates of societal risk and policy applications.

    PubMed

    Jonkman, Sebastiaan N; Jongejan, Ruben; Maaskant, Bob

    2011-02-01

    The Dutch government is in the process of revising its flood safety policy. The current safety standards for flood defenses in the Netherlands are largely based on the outcomes of cost-benefit analyses. Loss of life has not been considered separately in the choice for current standards. This article presents the results of a research project that evaluated the potential roles of two risk metrics, individual and societal risk, to support decision making about new flood safety standards. These risk metrics are already used in the Dutch major hazards policy for the evaluation of risks to the public. Individual risk concerns the annual probability of death of a person. Societal risk concerns the probability of an event with many fatalities. Technical aspects of the use of individual and societal risk metrics in flood risk assessments as well as policy implications are discussed. Preliminary estimates of nationwide levels of societal risk are presented. Societal risk levels appear relatively high in the southwestern part of the country where densely populated dike rings are threatened by a combination of river and coastal floods. It was found that cumulation, the simultaneous flooding of multiple dike rings during a single flood event, has significant impact on the national level of societal risk. Options for the application of the individual and societal risk in the new flood safety policy are presented and discussed. PMID:20883529

  4. Eye safety related to near infrared radiation exposure to biometric devices.

    PubMed

    Kourkoumelis, Nikolaos; Tzaphlidou, Margaret

    2011-01-01

    Biometrics has become an emerging field of technology due to its intrinsic security features concerning the identification of individuals by means of measurable biological characteristics. Two of the most promising biometric modalities are iris and retina recognition, which primarily use nonionizing radiation in the infrared region. Illumination of the eye is achieved by infrared light emitting diodes (LEDs). Even if few LED sources are capable of causing direct eye damage as they emit incoherent light, there is a growing concern about the possible use of LED arrays that might pose a potential threat. Exposure to intense coherent infrared radiation has been proven to have significant effects on living tissues. The purpose of this study is to explore the biological effects arising from exposing the eye to near infrared radiation with reference to international legislation. PMID:21380486

  5. External Beam Radiation Therapy and Abiraterone in Men With Localized Prostate Cancer: Safety and Effect on Tissue Androgens

    SciTech Connect

    Cho, Eunpi; Mostaghel, Elahe A.; Russell, Kenneth J.; Liao, Jay J.; Konodi, Mark A.; Kurland, Brenda F.; Marck, Brett T.; Matsumoto, Alvin M.; Dalkin, Bruce L.; Montgomery, R. Bruce

    2015-06-01

    Purpose: Optimizing androgen suppression may provide better control of localized prostate cancer (PCa). Numerous trials have supported the benefit of combining androgen deprivation therapy with definitive radiation therapy in men with locally advanced or high-grade disease. Addition of abiraterone to luteinizing hormone-releasing hormone agonist (LHRHa) with radiation has not been reported. We examined the safety of this combination as well as its impact on androgen suppression. Methods and Materials: A prospective, phase 2 study was conducted in men with localized PCa treated with 6 months of neoadjuvant and concurrent abiraterone with LHRHa and radiation. Duration of adjuvant LHRHa was at the discretion of the treating clinician. Prostate biopsy assays were obtained prior to the start of therapy and prior to radiation. Sera and tissue androgen levels were measured by liquid chromatography-tandem mass spectrometry. Results: A total of 22 men with intermediate- (n=3) and high-risk PCa (n=19) received study therapy. Sixteen men completed the intended course of abiraterone, and 19 men completed planned radiation to 77.4 to 81 Gy. Radiation to pelvic nodes was administered in 20 men. The following grade 3 toxicities were reported: lymphopenia (14 patients), fatigue (1 patient), transaminitis (2 patients), hypertension (2 patients), and hypokalemia (1 patient). There were no grade 4 toxicities. All 21 men who complied with at least 3 months of abiraterone therapy had a preradiation prostate-specific antigen (PSA) concentration nadir of <0.3 ng/mL. Median levels of tissue androgen downstream of CYP17A were significantly suppressed after treatment with abiraterone, and upstream steroids were increased. At median follow-up of 21 months (range: 3-37 months), only 1 patient (who had discontinued abiraterone at 3 months) had biochemical relapse. Conclusions: Addition of abiraterone to LHRHa with radiation is safe and achieves effective prostatic androgen suppression

  6. Advanced photon source proposal for upgrading the radiation safety of x-ray labs

    SciTech Connect

    Friedman, N.

    1991-07-01

    There are two adjacent x-ray labs in building 360, each having two entrance doors. Lab A240 has two x-ray machines and lab A248 has one. All machines are equipped with sliding safety windows and microswitches to monitor the state of the windows - open or closed. Two modes of operation are possible. (1) Secure Mode in which all safety windows are closed as indicated by the microswitches. This satisfies the interlock system, allowing the high voltage power supply to be turned on. (2) Bypass Mode in which the interlock system is overridden by a key-controlled selector switch and high voltage can be turned on with machine hutch window(s) open. The bypass mode is potentially unsafe because it is possible for an operator to leave a running instrument unattended while the windows are open. Thus, it is possible for someone entering the lab to expose themselves to x-rays.

  7. Radiation safety in commercial air traffic - A need for further study

    NASA Technical Reports Server (NTRS)

    Wilson, John W.; Townsend, Lawrence W.

    1988-01-01

    The problem of radiation exposure of crewmembers in high altitude supersonic commercial aircraft is addressed. As a result of recent changes in the quality factors for radiological protection, it is found that worst case estimates of radiation exposure are now well above the exposure limits of the general population, and a reassessment of radiation impact on commercial aviation is needed, if the proposed quality factors are adopted. Calculations are presented from a study on neutron dosage equivalent rates. It is shown that a crew flying at altitudes near 13 km (43,000 ft) for 40 hr/mo would receive exposure levels of 47-75 Sv/yr, and it is suggested that such crewmembers be considered as radiation workers, rather than general population members. However, since present exposure estimates need to be improved, and the maximum permissible dose limits are currently under revision, the final exposure limits are, as yet, unclear, suggesting the need for further study to clarify the work status of commercial aircrews.

  8. What You Should Know About Pediatric Nuclear Medicine and Radiation Safety

    MedlinePlus

    ... the Pediatric Imaging Council of the Society of Nuclear Medicine, as well as over 50 other societies, are members of this group. We are a group of over 700,000 health care professionals in radiology, pediatrics, medical physics and radiation protection. More information can be found ...

  9. Space Station crew safety alternatives study. Volume 2: Threat development

    NASA Technical Reports Server (NTRS)

    Raasch, R. F.; Peercy, R. L., Jr.; Rockoff, L. A.

    1985-01-01

    The first 15 years of accumulated space station concepts for initial operational capability (IOC) during the early 1990's were considered. Twenty-five threats to the space station are identified and selected threats addressed as impacting safety criteria, escape and rescue, and human factors safety concerns. Of the 25 threats identified, eight are discussed including strategy options for threat control: fire, biological or toxic contamination, injury/illness, explosion, loss of pressurization, radiation, meteoroid penetration, and debris.

  10. Space station crew safety alternatives study, volume 1

    NASA Technical Reports Server (NTRS)

    Peercy, R. L., Jr.; Raasch, R. F.; Rockoff, L. A.

    1985-01-01

    The first 15 years of accumulated space station concepts for initial operational capability (IOC) during the early 1990's were considered. Twenty-five threats to the space station are identified and selected threats addressed as impacting safety criteria, escape and rescue, and human factors safety concerns. Of the 25 threats identified, eight are discussed including strategy options for threat control: fire, biological or toxic contamination, injury/illness, explosion, loss of pressurization, radiation, meteoroid penetration and debris.

  11. Space Station crew safety alternatives study. Volume 4: Appendices

    NASA Technical Reports Server (NTRS)

    Peercy, R. L., Jr.; Raasch, R. F.; Rockoff, L. A.

    1985-01-01

    The scope of this study considered the first 15 years of accumulated space station concepts for Initial Operational Capability (10C) during the early 1990's. Twenty-five threats to the space station are identified and selected threats addressed as impacting safety criteria, escape and rescue, and human factors safety concerns. Of the 25 threats identified, eight are discussed including strategy options for threat control: fire, biological or toxic contamination, injury/illness, explosion, loss of pressurization, radiation, meteoroid penetration and debris.

  12. Space station crew safety alternatives study. Volume 3: Safety impact of human factors

    NASA Technical Reports Server (NTRS)

    Rockoff, L. A.; Raasch, R. F.; Peercy, R. L., Jr.

    1985-01-01

    The first 15 years of accumulated space station concepts for Initial Operational Capability (IOC) during the early 1990's was considered. Twenty-five threats to the space station are identified and selected threats addressed as impacting safety criteria, escape and rescue, and human factors safety concerns. Of the 25 threats identified, eight are discussed including strategy options for threat control: fire, biological or toxic contamination, injury/illness, explosion, loss of pressurization, radiation, meteoroid penetration and debris. Of particular interest here is volume three (of five volumes) pertaining to the safety impact of human factors.

  13. Radiation Emergencies

    MedlinePlus

    ... day from sources such as sunlight. A radiation emergency would involve larger amounts of radiation and could ... are no guarantees of safety during a radiation emergency, you can take actions to protect yourself. You ...

  14. [Place of the radiation safety officer in the implementation of the ALARA principle through European directive 97-43 items].

    PubMed

    Mozziconacci, J G; Ayivi, J; Loat, A; Ifergan, J; Mourbrun, M; Drevet, B

    2005-05-01

    The purpose of this article is to define the role of the radiation safety officer in raising the awareness of the radiology staff to the ALARA (As low as reasonable achievable) principle specified in European directive 97-43. The actions taken and the techniques used in our hospital, as well as the potential improvements that could be achieved with extra funding, will be presented. The didactic value of flow charts recording technical factors and fluoroscopy times for quality improvement will be demonstrated. In the future, a dosimeter incorporated on the new equipment could allow direct recording of the dose. The different items presented in this paper should allow routine implementation of the required elements described in the law 2003-270, i.e the French translation of European Directive 97-43. PMID:16114200

  15. Medical accelerator safety considerations: report of AAPM Radiation Therapy Committee Task Group No. 35.

    PubMed

    Purdy, J A; Biggs, P J; Bowers, C; Dally, E; Downs, W; Fraass, B A; Karzmark, C J; Khan, F; Morgan, P; Morton, R

    1993-01-01

    Ensuring safe operation for a medical accelerator is a difficult task. Users must assume more responsibility in using contemporary equipment. Additionally, users must work closely with manufacturers in promoting the safe and effective use of such complex equipment. Complex treatment techniques and treatment modality changeover procedures merit detailed, unambiguous written procedural instruction at the control console. A thorough "hands on" training period after receiving instructions, and before assuming treatment responsibilities, is essential for all technologists. Unambiguous written instructions must also be provided to guide technologists in safe response when equipment malfunctions or exhibits unexpected behavior or after any component has been changed or readjusted. Technologists should be given a written list of the appropriate individuals to consult when unexpected machine behavior occurs. They should be assisted in identifying aberrant behavior of equipment. Many centers already provide this instruction, but others may not. Practiced response and discussion with technologists should be a part of an ongoing quality assurance program. An important aspect of a safety program is the need for continuous vigilance. Table III gives a summary of a comprehensive safety program for medical accelerators. Table IV gives a list of summary recommendations as an example of how one might mitigate the consequences of an equipment failure and improve procedures and operator response in the context of the environment described. Most of these recommendations can be implemented almost immediately at any individual treatment center. PMID:8413039

  16. Value of public health and safety actions and radiation dose avoided

    SciTech Connect

    Baum, J.W.

    1994-05-01

    The values judged best to reflect the willingness of society to pay for the avoidance or reduction of risk were deduced from studies of costs of health care, transportation safety, consumer product safety, government agency actions, wage-risk compensation, consumer behavior (market) studies, and willingness-to-pay surveys. The results ranged from $1,400,000 to $2,700,000 per life saved. Applying the mean of these values ($2,100,000) and the latest risk per unit dose coefficients used by the ICRP (1991), which take into account risks to the general public, including genetic effects and nonfatal cancers, yields a value of dose avoided of $750 to $1,500 per person-cSv for public exposures. The lower value applies if adjustments are made for years of life lost per fatality. A nominal value of $1,000 per person-cSv seems appropriate in light of the many uncertainties involved in deducing these values. These values are consistent with values recommended by several European countries for individual doses in the region of 1 mSv/y (100 mrem/y). Below this dose rate, most countries have values a factor of 7 to 10 lower, based on the assumption that society is less concerned with fatality risks below about 10{sup {minus}4}/y.

  17. 30 CFR 104.3 - Pattern criteria.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... recurrence of violations of mandatory safety standards or health standards which significantly and substantially contribute to the cause and effect of mine safety or health hazards. These criteria are— (1) A... Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR PATTERN OF VIOLATIONS PATTERN...

  18. Enhancing VHTR passive safety and economy with thermal radiation based direct reactor auxiliary cooling system

    SciTech Connect

    Zhao, H.; Zhang, H.; Zou, L.; Sun, X.

    2012-07-01

    One of the most important requirements for Gen. IV Very High Temperature Reactor (VHTR) is passive safety. Currently all the gas cooled version of VHTR designs use Reactor Vessel Auxiliary Cooling System (RVACS) for passive decay heat removal. The RVACS can be characterized as a surface-based decay heat removal system. It is especially suitable for smaller power reactors since small systems have relatively larger surface area to volume ratio. However, RVACS limits the maximum achievable power level for modular VHTRs due to the mismatch between the reactor power (proportional to the core volume) and decay heat removal capability (proportional to the vessel surface area). Besides the safety considerations, VHTRs also need to be economical in order to compete with other reactor concepts and other types of energy sources. The limit of decay heat removal capability set by using RVACS has affected the economy of VHTRs. A potential alternative solution is to use a volume-based passive decay heat removal system, called Direct Reactor Auxiliary Cooling Systems (DRACS), to remove or mitigate the limitation on decay heat removal capability. DRACS composes of natural circulation loops with two sets of heat exchangers, one on the reactor side and another on the environmental side. For the reactor side, cooling pipes will be inserted into holes made in the outer or inner graphite reflector blocks. There will be gaps or annular regions formed between these cooling pipes and their corresponding surrounding graphite surfaces. Graphite has an excellent heat conduction property. By taking advantage of this feature, we can have a volume-based method to remove decay heat. The scalability can be achieved, if needed, by employing more rows of cooling pipes to accommodate higher decay heat rates. Since heat can easily conduct through the graphite regions among the holes made for the cooling pipes, those cooling pipes located further away from the active core region can still be very

  19. Monitoring human factor risk characteristics at nuclear legacy sites in northwest Russia in support of radiation safety regulation.

    PubMed

    Scheblanov, V Y; Sneve, M K; Bobrov, A F

    2012-12-01

    This paper describes research aimed at improving regulatory supervision of radiation safety during work associated with the management of spent nuclear fuel and radioactive waste at legacy sites in northwest Russia through timely identification of employees presenting unfavourable human factor risk characteristics. The legacy sites of interest include sites of temporary storage now operated by SevRAO on behalf of Rosatom. The sites were previously operational bases for servicing nuclear powered submarines and are now subject to major remediation activities. These activities include hazardous operations for recovery of spent nuclear fuel and radioactive waste from sub-optimal storage conditions. The paper describes the results of analysis of methods, procedures, techniques and informational issues leading to the development of an expert-diagnostic information system for monitoring of workers involved in carrying out the most hazardous operations. The system serves as a tool for human factor and professional reliability risk monitoring and has been tested in practical working environments and implemented as part of regulatory supervision. The work has been carried out by the Burnasyan Federal Medical Biophysical Center, within the framework of the regulatory cooperation programme between the Federal Medical-Biological Agency of Russia and the Norwegian Radiation Protection Authority. PMID:23186692

  20. [Radiation safety during work on the ANET-V therapeutic apparatus with 252Cf sources].

    PubMed

    Chekhonadskiĭ, V N; Drygin, V N; Vaĭnberg, M Sh; Komar, V Ia; Elisiutin, G P

    1985-03-01

    The Soviet ANET-W intracavitary neutron therapy apparatus is charged with 252Cf sources, the total mass of the radionuclide being 2100 micrograms. The radiation exposure of the staff has been studied and the results presented. Possible emergency situations have been analysed, methods of their prevention and liquidation worked out. Induced radioactivity in the patient's body has been estimated. Radiation dose levels for the medical staff are 10-15 times lower for the ANET-W apparatus than those for 252Cf sources administered by the manual series system but 10 times higher than those for the AGAT-W gamma-apparatus. The design, blocking system and emergency reset of the sources provide for safe work on the ANET-W apparatus. During liquidation of an emergency situation irradiation of the staff does not exceed 0.3 of the annual maximum tolerance dose. The level of induced activity in the patient's body is insignificant as in 10.5 min it does not exceed background values. PMID:3982256

  1. High radon levels in subterranean environments: monitoring and technical criteria to ensure human safety (case of Castañar cave, Spain).

    PubMed

    Alvarez-Gallego, Miriam; Garcia-Anton, Elena; Fernandez-Cortes, Angel; Cuezva, Soledad; Sanchez-Moral, Sergio

    2015-07-01

    Castañar cave contains the highest radon gas ((222)Rn) concentration in Spain with an annual average of 31.9 kBq m(-)(3). Seasonal variations with summer minimums and maximum values in fall were recorded. The reduction of air-filled porosity of soil and rock by condensation or rainfalls hides the radon exchange by gas diffusion, determining this seasonal stair-step pattern of the radon activity concentration in underground air. The effective total dose and the maximum hours permitted have been evaluated for the guides and public safety with a highly detailed radon measurement along 2011 and 2012. A network of 12 passive detectors (kodalphas) has been installed, as well as, two radon continuous monitoring in the most interesting geological sites of the subterranean environment. A follow up of the recommended time (max. 50 min) inside the underground environment has been analysed since the reopen to public visitors for not surpassing the legal maximum effective dose for tourists and guides. Results shown that public visitors would receive in fall a 12.1% of the total effective dose permitted per visit, whereas in summer it is reduced to 8.6%, while the cave guide received a total effective dose of 6.41 mSv in four months. The spatial radon maps allow defining the most suitable touristic paths according to the radon concentration distribution and therefore, appropriate fall and summer touristic paths are recommended. PMID:25863322

  2. Guide for preparing annual reports on radiation-safety testing of electronic products (general)

    SciTech Connect

    Not Available

    1987-10-01

    For manufacturers of electronic products other than those for which a specific guide has been issued, the guide replaces the Guide for the Filing of Annual Reports (21 CFR Subchapter J, Section 1002.11), HHS Publication FDA 82-8127. The electronic product (general) annual reporting guide is applicable to the following products: products intended to produce x radiation (accelerators, analytical devices, therapy x-ray machines); microwave diathermy machines; cold-cathode discharge tubes; and vacuum switches and tubes operating at or above 15,000 volts. To carry out its responsibilities under Public Law 90-602, the Food and Drug Administration's Center for Devices and Radiological Health (CDRH) has issued a series of regulations contained in Title 21 of the Code of Federal Regulations (CFR). Part 1002 of 21 CFR deals with records and reports. Section 1002.61 categorizes electronic products into Groups A through C. Section 1002.30 requires manufacturers of products in Groups B and C to establish and maintain certain records, while Section 1002.11 requires such manufacturers to submit an Annual Report summarizing the contents of the required records. Section 1002.7 requires that reports conform to reporting guides issued by CDRH unless an acceptable justification for an alternate format is provided.

  3. 10 CFR 830.122 - Quality assurance criteria.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... DEPARTMENT OF ENERGY NUCLEAR SAFETY MANAGEMENT Quality Assurance Requirements § 830.122 Quality assurance criteria. The QAP must address the following management, performance, and assessment criteria: (a) Criterion 1—Management/Program. (1) Establish an organizational structure, functional...

  4. 10 CFR 830.122 - Quality assurance criteria.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... DEPARTMENT OF ENERGY NUCLEAR SAFETY MANAGEMENT Quality Assurance Requirements § 830.122 Quality assurance criteria. The QAP must address the following management, performance, and assessment criteria: (a) Criterion 1—Management/Program. (1) Establish an organizational structure, functional...

  5. Crew Transportation Technical Standards and Design Evaluation Criteria

    NASA Technical Reports Server (NTRS)

    Lueders, Kathryn L.; Thomas, Rayelle E. (Compiler)

    2015-01-01

    Crew Transportation Technical Standards and Design Evaluation Criteria contains descriptions of technical, safety, and crew health medical processes and specifications, and the criteria which will be used to evaluate the acceptability of the Commercial Providers' proposed processes and specifications.

  6. Launch Commit Criteria Monitoring Agent

    NASA Technical Reports Server (NTRS)

    Semmel, Glenn S.; Davis, Steven R.; Leucht, Kurt W.; Rowe, Dan A.; Kelly, Andrew O.; Boeloeni, Ladislau

    2005-01-01

    The Spaceport Processing Systems Branch at NASA Kennedy Space Center has developed and deployed a software agent to monitor the Space Shuttle's ground processing telemetry stream. The application, the Launch Commit Criteria Monitoring Agent, increases situational awareness for system and hardware engineers during Shuttle launch countdown. The agent provides autonomous monitoring of the telemetry stream, automatically alerts system engineers when predefined criteria have been met, identifies limit warnings and violations of launch commit criteria, aids Shuttle engineers through troubleshooting procedures, and provides additional insight to verify appropriate troubleshooting of problems by contractors. The agent has successfully detected launch commit criteria warnings and violations on a simulated playback data stream. Efficiency and safety are improved through increased automation.

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

    SciTech Connect

    Chizhov, K.; Simakov, A.; Seregin, V.; Kudrin, I.; Shandala, N.; Tsovyanov, A.; Kryuchkov, V.; Krasnoschekov, A.; Kosnikov, A.; Kemsky, I.

    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 tool 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

  8. ACR Appropriateness Criteria on Induction and Adjuvant Therapy for Stage N2 Non-Small-Cell Lung Cancer: Expert Panel on Radiation Oncology-Lung

    SciTech Connect

    Gopal, Ramesh S.; Dubey, Sarita; Rosenzweig, Kenneth E.; Chang, Joe Yujiao; Decker, Roy; Gewanter, Richard M.; Kong Fengming; Lally, Brian E.; Langer, Corey J.; Lee, Hoon Ku; Movsas, Benjamin M.D.

    2010-11-15

    'The American College of Radiology seeks and encourages collaboration with other organizations on the development of the ACR Appropriateness Criteria through society representation on expert panels. Participation by representatives from collaborating societies on the expert panel does not necessarily imply society endorsement of the final document.'

  9. Implications of Graphite Radiation Damage on the Neutronic, Operational, and Safety Aspects of Very High Temperature Reactors

    SciTech Connect

    Hawari, Ayman I

    2011-08-30

    In both the prismatic and pebble bed designs of Very High Temperature Reactors (VHTR), the graphite moderator is expected to reach exposure levels of 1021 to 1022 n/cm2 over the lifetime of the reactor. This exposure results in damage to the graphite structure. In this work, molecular dynamic and ab initio molecular static calculations will be used to: 1) simulate radiation damage in graphite under various irradiation and temperature conditions, 2) generate the thermal neutron scattering cross sections for damaged graphite, and 3) examine the resulting microstructure to identify damage formations that may produce the high-temperature Wigner effect. The impact of damage on the neutronic, operational and safety behavior of the reactor will be assessed using reactor physics calculations. In addition, tests will be performed on irradiated graphite samples to search for the high-temperature Wigner effect, and phonon density of states measurements will be conducted to quantify the effect on thermal neutron scattering cross sections using these samples.

  10. 47 CFR 90.713 - Entry criteria.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Entry criteria. 90.713 Section 90.713 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES PRIVATE LAND MOBILE RADIO SERVICES Regulations Governing Licensing and Use of Frequencies in the 220-222 MHz Band § 90.713 Entry criteria. (a) As set forth in...

  11. Design criteria for SW-205 capillary system

    SciTech Connect

    Lyons, W.J.

    1989-04-01

    This design criteria covers the converting of the SW-250 Capillary System from fumehood manual operation to sealed glovebox automated operation. The design criteria contains general guidelines and includes drawings reflecting a similar installation at another site. Topics include purpose and physical description, architectural-engineering requirements, reference document, electrical, fire protection, occupational safety and health, quality assurance, and security.

  12. 46 CFR 154.471 - Design criteria.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 46 Shipping 5 2012-10-01 2012-10-01 false Design criteria. 154.471 Section 154.471 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) CERTAIN BULK DANGEROUS CARGOES SAFETY STANDARDS FOR SELF-PROPELLED VESSELS CARRYING BULK LIQUEFIED GASES Design, Construction and Equipment Support System § 154.471 Design criteria. (a) The...

  13. 78 FR 4830 - National Advisory Committee on Microbiological Criteria for Foods; Reestablishment

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-23

    ... Food Safety and Inspection Service National Advisory Committee on Microbiological Criteria for Foods; Reestablishment AGENCY: Food Safety and Inspection Service, USDA. ACTION: Notice of reestablishment of Committee... reestablishment of the National Advisory Committee on Microbiological Criteria for Foods (NACMCF). The...

  14. The Efficacy and Safety of Jaungo, a Traditional Medicinal Ointment, in Preventing Radiation Dermatitis in Patients with Breast Cancer: A Prospective, Single-Blinded, Randomized Pilot Study

    PubMed Central

    Kong, Moonkyoo; Hwang, Deok-Sang; Lee, Jee Young; Yoon, Seong Woo

    2016-01-01

    Purpose. This study was performed to evaluate the efficacy and safety of Jaungo in preventing radiation dermatitis in patients with breast cancer. Methods. Thirty patients were prospectively enrolled and randomly assigned to receive Jaungo or general supportive skin care. Radiation dermatitis and pain were examined at daily intervals from the start of radiotherapy until 4 weeks after its completion. The primary endpoint of this study was the incidence of radiation dermatitis. The secondary endpoints were time to onset of radiation dermatitis, duration of radiation dermatitis, and maximum pain score. Results. Jaungo reduced the incidence of grade ≥2 (46.7% versus 78.6%) and grade 3 radiation dermatitis (20.0% versus 50.0%) in comparison with general supportive skin care. Jaungo also delayed the onset of grade 2 dermatitis (35 days versus 30 days). In terms of time to onset of grade 3 dermatitis, duration of dermatitis, and maximum pain score, Jaungo showed results comparable to those achieved with general supportive skin care. No patients experienced adverse effects caused by Jaungo administration. Conclusions. Jaungo minimized radiation dermatitis in patients with breast cancer without causing adverse effects. Further randomized studies with a larger sample size are required to assess clinical use of Jaungo. PMID:27066103

  15. 16 CFR 1301.5 - Banning criteria.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Banning criteria. 1301.5 Section 1301.5 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS BAN OF... being distributed in commerce on or after the effective date of this ban and which has an...

  16. Endoscopic ultrasound-guided fiducial marker placement for image-guided radiation therapy without fluoroscopy: safety and technical feasibility

    PubMed Central

    Dhadham, Gautamy Chitiki; Hoffe, Sarah; Harris, Cynthia L.; Klapman, Jason B.

    2016-01-01

    Background and study aims: Endoscopic ultrasound (EUS)-guided fiducial marker placement for image-guided radiation treatment (IGRT) is becoming more widespread. Most case series report the procedure performed using fluoroscopy for spatial geometry although the benefits of this are unclear. The aim of our study is to report the technical feasibility, safety, and migration rate of fiducial marker placement in a large cohort of patients with gastrointestinal malignancies who underwent EUS-guided fiducial marker placement for IGRT without fluoroscopy. Patients and methods: A retrospective chart review was performed on all patients referred for EUS-guided fiducial marker placement from 08/1/07 to 7/31/14 at Moffitt Cancer Center. Results: During the study period, 514 patients underwent placement of 1093 gold fiducial markers under EUS-guidance. Two hundred and forty patients with esophageal/gastro-esophageal junction cancer had 405 fiducials placed. In 188 patients with pancreatic ancer, 510 fiducials were placed. In 54 patients with rectal cancer, 103 fiducials were placed and 32 patients had 75 fiducials placed into other gastrointestinal tract lesions. Minor bleeding, which resolved spontaneously, occurred in two patients. Technical difficulty in placing fiducials was noted in 18 patients. Intraprocedural fiducial migration was noted in two patients and only 2/1093 fiducials (.002%) in two esophageal patients migrated as noted on simulation computed tomography scan. Conclusions: EUS-guided fiducial marker placement without fluoroscopy is technically feasible and safe. There were minimal intraprocedure/post-procedure complications. Imaging at the time of simulation also revealed the migration rate to be extremely low. These results may allow for more widespread adoption of EUS-guided fiducial marker placement. PMID:27004258

  17. Packaging design criteria for the K east basin sludge transportation system

    SciTech Connect

    Tomaszewski, T.A., Westinghouse Hanford

    1996-07-11

    This packaging design criteria (PDC) establishes the onsite transportation safety criteria for a reusable packaging and transport system to transport K East Basin sludge and water.This PDC provides the basis for the development of a safety analysis report for packaging; establishes the packaging contents and safety class of the package; and provides design criteria for the package, packaging, and transport systems.

  18. Radiation

    NASA Video Gallery

    Outside the protective cocoon of Earth's atmosphere, the universe is full of harmful radiation. Astronauts who live and work in space are exposed not only to ultraviolet rays but also to space radi...

  19. Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

    SciTech Connect

    Neupauer, R.M.; Thurmond, S.M.

    1992-09-01

    This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical.

  20. Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory. Part 2, Chemical constituents

    SciTech Connect

    Neupauer, R.M.; Thurmond, S.M.

    1992-09-01

    This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical.

  1. Packaging design criteria for the Hanford Ecorok Packaging

    SciTech Connect

    Mercado, M.S.

    1996-01-19

    The Hanford Ecorok Packaging (HEP) will be used to ship contaminated water purification filters from K Basins to the Central Waste Complex. This packaging design criteria documents the design of the HEP, its intended use, and the transportation safety criteria it is required to meet. This information will serve as a basis for the safety analysis report for packaging.

  2. Space Radiation Cancer Risks

    NASA Technical Reports Server (NTRS)

    Cucinotta, Francis A.

    2007-01-01

    Space radiation presents major challenges to astronauts on the International Space Station and for future missions to the Earth s moon or Mars. Methods used to project risks on Earth need to be modified because of the large uncertainties in projecting cancer risks from space radiation, and thus impact safety factors. We describe NASA s unique approach to radiation safety that applies uncertainty based criteria within the occupational health program for astronauts: The two terrestrial criteria of a point estimate of maximum acceptable level of risk and application of the principle of As Low As Reasonably Achievable (ALARA) are supplemented by a third requirement that protects against risk projection uncertainties using the upper 95% confidence level (CL) in the radiation cancer projection model. NASA s acceptable level of risk for ISS and their new lunar program have been set at the point-estimate of a 3-percent risk of exposure induced death (REID). Tissue-averaged organ dose-equivalents are combined with age at exposure and gender-dependent risk coefficients to project the cumulative occupational radiation risks incurred by astronauts. The 95% CL criteria in practice is a stronger criterion than ALARA, but not an absolute cut-off as is applied to a point projection of a 3% REID. We describe the most recent astronaut dose limits, and present a historical review of astronaut organ doses estimates from the Mercury through the current ISS program, and future projections for lunar and Mars missions. NASA s 95% CL criteria is linked to a vibrant ground based radiobiology program investigating the radiobiology of high-energy protons and heavy ions. The near-term goal of research is new knowledge leading to the reduction of uncertainties in projection models. Risk projections involve a product of many biological and physical factors, each of which has a differential range of uncertainty due to lack of data and knowledge. The current model for projecting space radiation

  3. 29 CFR 1904.7 - General recording criteria.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 29 Labor 5 2010-07-01 2010-07-01 false General recording criteria. 1904.7 Section 1904.7 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR RECORDING AND REPORTING OCCUPATIONAL INJURIES AND ILLNESSES Recordkeeping Forms and Recording Criteria § 1904.7 General recording criteria....

  4. 29 CFR 1904.7 - General recording criteria.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 29 Labor 5 2012-07-01 2012-07-01 false General recording criteria. 1904.7 Section 1904.7 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR RECORDING AND REPORTING OCCUPATIONAL INJURIES AND ILLNESSES Recordkeeping Forms and Recording Criteria § 1904.7 General recording criteria....

  5. 29 CFR 1904.7 - General recording criteria.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 29 Labor 5 2011-07-01 2011-07-01 false General recording criteria. 1904.7 Section 1904.7 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR RECORDING AND REPORTING OCCUPATIONAL INJURIES AND ILLNESSES Recordkeeping Forms and Recording Criteria § 1904.7 General recording criteria....

  6. New facility shield design criteria

    SciTech Connect

    Howell, W.P.

    1981-07-01

    The purpose of the criteria presented here is to provide standard guidance for the design of nuclear radiation shields thoughout new facilities. These criteria are required to assure a consistent and integrated design that can be operated safely and economically within the DOE standards. The scope of this report is confined to the consideration of radiation shielding for contained sources. The whole body dose limit established by the DOE applies to all doses which are generally distributed throughout the trunk of the body. Therefore, where the whole body is the critical organ for an internally deposited radionuclide, the whole body dose limit applies to the sum of doses received must assure control of the concentration of radionuclides in the building atmosphere and thereby limit the dose from internal sources.

  7. Administration of the Radiation Control for Health Safety Act of 1968, public law 90-602, April 1, 1984 (1983 annual report)

    SciTech Connect

    Not Available

    1984-04-01

    The Food and Drug Administration through its National Center for Devices and Radiological Health, is responsible for the day-to-day administration of the Radiation Control for Health and Safety Act. This report covers the detailed operation of the Agency in carrying out that responsibility for calendar year 1983. There are nine equipment performance or regulatory standards (television receivers, cold-cathode gas discharge tubes, microwave ovens, diagnostic x-ray systems, cabinet x-ray systems, laser products, ultrasonic therapy products, mercury vapor lamps, and sunlamp products) now in effect.

  8. Radiation Exposure in X-Ray and CT Examinations

    MedlinePlus

    ... procedures. See the X-ray, Interventional Radiology and Nuclear Medicine Radiation Safety page for more information. top of page ... and Radiation Safety X-ray, Interventional Radiology and Nuclear Medicine Radiation Safety Videos related to Radiation Dose in X- ...

  9. Hanford Site Solid Waste Acceptance Criteria

    SciTech Connect

    MCDOWELL, A.K.; TRINER, G.C.

    2002-03-28

    DOE Order 435.1 requires that each treatment, storage, and/or disposal facility (referred to in this document as TSD unit) that manages low-level or transuranic (TRU) waste (including mixed waste and TSCA PCB waste) maintain waste acceptance criteria. These criteria must address the various requirements to operate the TSD unit in compliance with applicable safety and environmental requirements. This document sets forth the baseline criteria for acceptance of waste at TSD units operated by WMP. The criteria for each TSD unit have been established to ensure that waste accepted can be managed in a manner that is within the operating requirements of the unit, including environmental regulations, DOE Orders, permits, technical safety requirements, waste analysis plans, performance assessments, and other applicable requirements. Revisions to the acceptance criteria document require an Unreviewed Safety Question review to document that the changes are consistent with current applicable safety analysis. Acceptance criteria apply to the following TSD units: the Low-Level Burial Grounds (LLBG) including both the nonregulated portions of the LLBG and trenches 31 and 34 of the 218-W-5 Burial Ground for mixed waste disposal; Central Waste Complex (CWC); Waste Receiving and Processing (WRAP) Facility; and T-Plant facility. Waste from all generators, both from the Hanford Site and from offsite facilities, must comply with these criteria. Exceptions can be granted as provided in Section 1.6. Specific waste streams could have additional requirements based on the identified TSD pathway. These requirements are communicated in the waste specification records (WSRds) and/or waste stream profile sheet approvals. The Hanford Site manages nonradioactive waste through direct shipments to offsite contractors. The waste acceptance requirements of the offsite TSD facility must be met for these nonradioactive wastes. This document does not address the acceptance requirements of these offsite

  10. Administration of the Radiation Control for Health and Safety Act of 1968, Public Law 90-602, (1987 annual report). Report for January-December 1987

    SciTech Connect

    Not Available

    1988-04-01

    This document is an annual report submitted to the President for transmittal to the Congress. The Food and Drug Administration, through its Center for Devices and Radiological Health, is responsible for the day-to-day administration of the Radiation Control for Health and Safety Act of 1968. The report provides a summary of the operations of the Center in carrying out that responsibility for calendar year 1987. In reviewing the operations of the CDRH as reported in the document, it should be kept in mind that the day-to-day administration of the Act is only part of the Center's function. Other responsibilities include the administration and enforcement of the 1976 Medical Device Amendments to the Federal Food, Drug, and Cosmetic Act (not covered in the report). Manufacturers of electronic products are required by 21 CFR 1002.20 to report accidental radiation occurrences to the CDRH. The Center no longer maintains a Radiation Incidents Registry, since accidental radiation occurrences are reported through the Device Experience Network (DEN) and through the requirements of the Medical Device Reporting (MDR) regulations.

  11. Regulations for the administration and enforcement of the Radiation Control for Health and Safety Act of 1968

    SciTech Connect

    Not Available

    1988-04-01

    The purpose of the Act is to protect the public from unnecessary exposure to radiation from electronic products, including ionizing, nonionizing, electromagnetic, or particulate radiation, or any sonic, infrasonic, or ultrasonic wave. The regulations in the publication cover general provisions, statements of policy and interpretation, radiation protection recommendations, recordkeeping and reporting requirements for manufacturers, dealers, and distributors; notification requirements for defects or failure to comply; repurchase, repairs, or replacement of electronic products; importation of products; and performance standards for television receivers, cathode ray tubes, diagnostic x-ray equipment, radiographic equipment, fluoroscopic equipment, computer aided tomography equipment, microwave ovens, laser products, sunlamps, ultraviolet lamps, mercury lamps, and ultrasonic therapy products.

  12. Strength criteria for composite materials (a literature survey)

    NASA Technical Reports Server (NTRS)

    Roode, F.

    1982-01-01

    Literature concerning strength (failure) criteria for composite materials is reviewed with emphasis on phenomenological failure criteria. These criteria are primarily intended to give a good estimation of the safety margin with respect to failure for arbitrary multiaxial stress states. The failure criteria do not indicate the types of fracture that will occur in the material. The collection of failure criteria is evaluated for applicability for the glass reinforced plastics used in mine detectors. Material tests necessary to determine the parameters in the failure criteria are discussed.

  13. 10 CFR 20.1404 - Alternate criteria for license termination.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 1 2014-01-01 2014-01-01 false Alternate criteria for license termination. 20.1404 Section 20.1404 Energy NUCLEAR REGULATORY COMMISSION STANDARDS FOR PROTECTION AGAINST RADIATION Radiological Criteria for License Termination § 20.1404 Alternate criteria for license termination. (a)...

  14. 10 CFR 20.1404 - Alternate criteria for license termination.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false Alternate criteria for license termination. 20.1404 Section 20.1404 Energy NUCLEAR REGULATORY COMMISSION STANDARDS FOR PROTECTION AGAINST RADIATION Radiological Criteria for License Termination § 20.1404 Alternate criteria for license termination. (a)...

  15. 10 CFR 20.1404 - Alternate criteria for license termination.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 1 2012-01-01 2012-01-01 false Alternate criteria for license termination. 20.1404 Section 20.1404 Energy NUCLEAR REGULATORY COMMISSION STANDARDS FOR PROTECTION AGAINST RADIATION Radiological Criteria for License Termination § 20.1404 Alternate criteria for license termination. Link to...

  16. 10 CFR 20.1404 - Alternate criteria for license termination.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 1 2013-01-01 2013-01-01 false Alternate criteria for license termination. 20.1404 Section 20.1404 Energy NUCLEAR REGULATORY COMMISSION STANDARDS FOR PROTECTION AGAINST RADIATION Radiological Criteria for License Termination § 20.1404 Alternate criteria for license termination. (a)...

  17. 10 CFR 72.126 - Criteria for radiological protection.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Criteria for radiological protection. 72.126 Section 72... WASTE General Design Criteria § 72.126 Criteria for radiological protection. (a) Exposure control... radiation exposure. (b) Radiological alarm systems. Radiological alarm systems must be provided...

  18. 10 CFR 20.1404 - Alternate criteria for license termination.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Alternate criteria for license termination. 20.1404 Section 20.1404 Energy NUCLEAR REGULATORY COMMISSION STANDARDS FOR PROTECTION AGAINST RADIATION Radiological Criteria for License Termination § 20.1404 Alternate criteria for license termination. (a) The Commission may terminate a license using...

  19. Hand Safety

    MedlinePlus

    ... en gatillo See More... Hand Anatomy Hand Safety Fireworks Safety Lawnmower Safety Snowblower safety Pumpkin Carving Gardening ... en gatillo See More... Hand Anatomy Hand Safety Fireworks Safety Lawnmower Safety Snowblower safety Pumpkin Carving Gardening ...

  20. Hand Safety

    MedlinePlus

    ... Fireworks Safety Lawnmower Safety Snowblower safety Pumpkin Carving Gardening Safety Turkey Carving Removing a Ring Español Artritis ... Fireworks Safety Lawnmower Safety Snowblower safety Pumpkin Carving Gardening Safety Turkey Carving Removing a Ring Español Artritis ...

  1. SAFETY ENGINEERING FOR THE RELATIVISTIC HEAVY ION COLLIDER AT THE BROOKHAVEN NATIONAL LABORATORY.

    SciTech Connect

    MUSOLINO,S.V.

    1999-11-14

    THERE ARE ONLY A FEW OTHER HIGH ENERGY PARTICLE ACCELERATORS LIKE RHIC IN THE WORLD. THEREFORE, THE DESIGNERS OF THE MACHINE DO NOT ALWAYS HAVE CONSENSUS DESIGN STANDARDS AND REGULATORY GUIDANCE AVAILABLE TO ESTABLISH THE ENGINEERING PARAMETERS FOR SAFETY. SOME OF THE AREAS WHERE STANDARDS ARE NOT AVAILABLE RELATE TO THE CRYOGENIC SYSTEM, CONTAINMENT OF LARGE VOLUMES OF FLAMMABLE GAS IN FRAGILE VESSELS IN THE EXPERIMENTAL APPARATUS AND MITIGATION OF A DESIGN BASIS ACCIDENT WITH A STORED PARTICLE BEAM. UNIQUE BUT EQUIVALENT SAFETY ENGINEERING MUST BE DETERMINED. SPECIAL DESIGN CRITERIA FOR PROMPT RADIATION WERE DEVELOPED TO PROVIDE GUIDANCE FOR THE DESIGN OF RADIATION SHIELDING.

  2. Annual report on the administration of the Radiation Control for Health and Safety Act of 1968, Public Law 90-602, (1988), April 1, 1989. Annual report

    SciTech Connect

    Not Available

    1989-04-01

    The Secretary of Health and Human Services is required by Subpart 3, Part F of Title III of the Public Health Service Act; 42 USC 263b et seq. (Public Law 90-602) to submit an annual report to the President for transmittal to the Congress on or before April 1 on the administration of the Radiation Control for Health and Safety Act. The detailed information required in the report is outlined in Section 360D of the Public Health Service Act. The Food and Drug Administration, through its Center for Devices and Radiological Health, is responsible for the day-to-day administration of the Radiation Control for Health and Safety Act of 1968. The report provides a summary of the operations of the Center in carrying out that responsibility for calendar year 1988. In reviewing the operations of the Center for Devices and Radiological Health as reported in the document, it should be kept in mind that the day-to-day administration of the Act is only part of the Center's function. Other responsibilities include the administration and enforcement of the 1976 Medical Device Amendments to the Federal Food, Drug, and Cosmetic Act (not covered in the report).

  3. 30 CFR 75.1403-7 - Criteria-Mantrips.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 1 2013-07-01 2013-07-01 false Criteria-Mantrips. 75.1403-7 Section 75.1403-7 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Hoisting and Mantrips § 75.1403-7 Criteria—Mantrips. (a) Mantrips should be...

  4. 30 CFR 75.1403-4 - Criteria-Automatic elevators.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 1 2012-07-01 2012-07-01 false Criteria-Automatic elevators. 75.1403-4 Section 75.1403-4 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Hoisting and Mantrips § 75.1403-4 Criteria—Automatic elevators. (a) The doors...

  5. 30 CFR 75.1403-9 - Criteria-Shelter holes.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 1 2013-07-01 2013-07-01 false Criteria-Shelter holes. 75.1403-9 Section 75.1403-9 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Hoisting and Mantrips § 75.1403-9 Criteria—Shelter holes. (a) Shelter holes should...

  6. 30 CFR 75.1403-9 - Criteria-Shelter holes.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 1 2014-07-01 2014-07-01 false Criteria-Shelter holes. 75.1403-9 Section 75.1403-9 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Hoisting and Mantrips § 75.1403-9 Criteria—Shelter holes. (a) Shelter holes should...

  7. 30 CFR 75.1403-9 - Criteria-Shelter holes.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 1 2012-07-01 2012-07-01 false Criteria-Shelter holes. 75.1403-9 Section 75.1403-9 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Hoisting and Mantrips § 75.1403-9 Criteria—Shelter holes. (a) Shelter holes should...

  8. Radionuclides for radioimmunotherapy: criteria for selection.

    PubMed

    Geerlings, M W

    1993-01-01

    In developing and designing radioimmunotherapy, the selection of the isotope is a major factor. This selection depends on a number of criteria and parameters, affecting usefulness and feasibility. Usefulness is directly related to the radiological performance of the ionising radiation in relation to tissue and its morphology, with a major distinction between the effects of alpha and beta-particles (or rays). Usefulness is also directly related to the pharmacodynamic performance of the isotope-carrier (e.g. antibody) complex, where the proper choice of isotope radiodecay halflife is of major importance. Feasibility depends on availability of the components in the isotope-ligand-carrier complex, and also on convenience and safety aspects in the preparation and the handling of the materials as well as in their application in patients. A comparison is made between the various properties of alpha-emitting isotopes that have been proposed over a number of years, concluding that the combination 225Ac- 213Bi deserves serious further attention. PMID:8277210

  9. Nutrient Criteria Research

    EPA Science Inventory

    EPA has developed methodologies for deriving nutrient criteria, default criteria for the variety of waters and eco-regions found in the U.S., and a strategy for implementing the criteria including guidance on the use and development of biocriteria. Whereas preliminary research ha...

  10. Technical Basis For Radiological Acceptance Criteria For Uranium At The Y-12 National Security Complex

    SciTech Connect

    Veinot, K. G.

    2009-07-22

    The purpose of this report is to establish radiological acceptance criteria for uranium. Other factors for acceptance not considered include criticality safety concerns, contaminants to the process stream, and impacts to the Safety Basis for the affected facilities. Three types of criteria were developed in this report. They include limits on external penetrating and non-penetrating radiation and on the internal hazard associated with inhalation of the material. These criteria are intended to alleviate the need for any special controls beyond what are normally utilized for worker protection from uranium hazards. Any proposed exceptions would require case-by-case evaluations to determine cost impacts and feasibility. Since Y-12 has set rigorous ALARA goals for worker doses, the external limits are based on assumptions of work time involved in the movement of accepted material plus the desire that external doses normally received are not exceeded, and set so that no special personnel monitoring would be required. Internal hazard controls were established so that dose contributions from non-uranium nuclides would not exceed 10% of that expected from the uranium component. This was performed using a Hazard Index (HI) previously established for work in areas contaminated with non-uranium nuclides. The radiological acceptance criteria for uranium are summarized in Table 1. Note that these limits are based on the assumption that radioactive daughter products have reached equilibrium.

  11. Space Radiation

    NASA Technical Reports Server (NTRS)

    Wu, Honglu

    2006-01-01

    Astronauts receive the highest occupational radiation exposure. Effective protections are needed to ensure the safety of astronauts on long duration space missions. Increased cancer morbidity or mortality risk in astronauts may be caused by occupational radiation exposure. Acute and late radiation damage to the central nervous system (CNS) may lead to changes in motor function and behavior, or neurological disorders. Radiation exposure may result in degenerative tissue diseases (non-cancer or non-CNS) such as cardiac, circulatory, or digestive diseases, as well as cataracts. Acute radiation syndromes may occur due to occupational radiation exposure.

  12. A Monte Carlo-based radiation safety assessment for astronauts in an environment with confined magnetic field shielding.

    PubMed

    Geng, Changran; Tang, Xiaobin; Gong, Chunhui; Guan, Fada; Johns, Jesse; Shu, Diyun; Chen, Da

    2015-12-01

    The active shielding technique has great potential for radiation protection in space exploration because it has the advantage of a significant mass saving compared with the passive shielding technique. This paper demonstrates a Monte Carlo-based approach to evaluating the shielding effectiveness of the active shielding technique using confined magnetic fields (CMFs). The International Commission on Radiological Protection reference anthropomorphic phantom, as well as the toroidal CMF, was modeled using the Monte Carlo toolkit Geant4. The penetrating primary particle fluence, organ-specific dose equivalent, and male effective dose were calculated for particles in galactic cosmic radiation (GCR) and solar particle events (SPEs). Results show that the SPE protons can be easily shielded against, even almost completely deflected, by the toroidal magnetic field. GCR particles can also be more effectively shielded against by increasing the magnetic field strength. Our results also show that the introduction of a structural Al wall in the CMF did not provide additional shielding for GCR; in fact it can weaken the total shielding effect of the CMF. This study demonstrated the feasibility of accurately determining the radiation field inside the environment and evaluating the organ dose equivalents for astronauts under active shielding using the CMF. PMID:26484984

  13. Phase I trial to evaluate the tumor and normal tissue uptake, radiation dosimetry and safety of 111In-DTPA-human epidermal growth factor in patients with metastatic EGFR-positive breast cancer

    PubMed Central

    Vallis, Katherine A; Reilly, Raymond M; Scollard, Deborah; Merante, Pat; Brade, Anthony; Velauthapillai, Sobi; Caldwell, Curtis; Chan, Ida; Freeman, Marc; Lockwood, Gina; Miller, Naomi A; Cornelissen, Bart; Petronis, Jennifer; Sabate, Kathryn

    2014-01-01

    The safety, pharmacokinetics, biodistribution and radiation dosimetry of 111In-DTPA-hEGF, an Auger electron-emitting radiopharmaceutical, were evaluated in a first-in-human trial. Dose escalation was performed in patients with EGFR-positive metastatic breast cancer who had received ≥2 prior courses of systemic treatment. 111In-DTPA-hEGF (0.25 mg) was administered once intravenously (i.v.). Blood was collected for biochemistry/hematology testing and pharmacokinetic and immunogenicity analyses at selected times post injection (p.i.). Whole body planar images were acquired at 1, 4-6, 24 and 72 h p.i. and SPECT images at 24 and/or 72 h p.i. Macrodosimetry (MIRD) for the whole body and organs was estimated using OLINDA. Correlative radiological imaging was obtained at baseline, 1 and 3 months and then 6 monthly. Toxicity was scored using Common Terminology Criteria for Adverse Events (CTCAE)v2.0. Sixteen patients, median age 47 yr (range, 35-59), received 111In-DTPA-hEGF as follows: 357-434 MBq (7), 754-805 MBq (3), 1,241-1,527 MBq (3) and 2,030-2,290 MBq (3). Fifteen were evaluable for toxicity. The commonest adverse events (AE) were flushing, chills, nausea, and vomiting occurring during or immediately p.i. One patient experienced Grade 3 thrombocytopenia (attributed to bone marrow infiltration by cancer). There were no other Grade 3 or 4 AEs. Maximum tolerated dose was not reached. Clear accumulation of radiopharmaceutical in at least one known site of disease was observed in 47% of patients. 111In-DTPA-hEGF was cleared biexponentially from the blood with α-phase T½ of 0.16 ± 0.03 h and β-phase T½ of 9.41 ± 1.93 h. 111In-DTPA-hEGF was not immunogenic. The mean radiation dose estimates in mGy/MBq for whole body, liver, kidneys, spleen and thyroid were 0.08, 0.86, 0.74, 0.37 and 0.30, respectively. No objective antitumor responses were observed at the doses studied. In summary, administered amounts of up to 2,290 MBq (0.25 mg) of 111In-DTPA-hEGF were well

  14. SU-E-T-642: Safety Procedures for Error Elimination in Cyberknife Stereotactic Radiosurgery (SRS) and Stereotactic Body Radiation Therapy (SBRT)

    SciTech Connect

    Hussain, A; Alkafi, A; Al-Najjar, W; Moftah, B

    2014-06-15

    Purpose: Cyberknife system is used for providing stereotactic radiosurgery (SRS) and stereotactic body radiation therapy (SBRT) hypofractionation scheme. The whole treatment delivery is based on live imaging of the patient. The minor error made at any stage may bring severe radiation injury to the patient or damage to the system itself. Several safety measures were taken to make the system safer. Methods: The radiation treatment provided thru a 6MV linac attached to Kuka robot (Cyberknife G4, Accuray Inc. Sunnyvale, CA, USA). Several possible errors were identified related to patient alignment, treatment planning, dose delivery and physics quality assurance. During dose delivery, manual and visual checks were introduced to confirm pre and intra-treatment imaging to reduce possible errors. One additional step was introduced to confirm that software tracking-tools had worked correctly with highest possible confidence level. Robotic head move in different orientations over and around the patient body, the rigidity of linac-head cover and other accessories was checked periodically. The vender was alerted when a tiny or bigger piece of equipment needed additional interlocked support. Results: As of our experience treating 525 patients on Cyberknife during the last four years, we saw on and off technical issues. During image acquisition, it was made essential to follow the site-specific imaging protocols. Adequate anatomy was contoured to document the respective doses. Followed by auto-segmentation, manual tweaking was performed on every structure. The calculation box was enclosing the whole image during the final calculation. Every plan was evaluated on slice-by slice basis. To review the whole process, a check list was maintained during the physics 2nd-check. Conclusion: The implementation of manual and visual additional checks introduced along with automated checks for confirmation was found promising in terms of reduction in systematic errors and making the system

  15. WATER QUALITY CRITERIA DOCUMENTS

    EPA Science Inventory

    Background

    Water quality standards and criteria are the foundation for a wide range of programs under the Clean Water Act. Specifically, under section 304(a)(1) of the Clean Water Act it requires EPA to develop criteria for water quality that accurately re...

  16. Nuclear Reactor Safety: a current awareness bulletin

    SciTech Connect

    Cunningham, D.C.

    1985-01-15

    Nuclear Reactor Safety announces on a semimonthly basis the current worldwide information available on all safety-related aspects of fission reactors, including: accident analysis, safety systems, radiation protection, decommissioning and dismantling, and security measures.

  17. 49 CFR Appendix B to Part 236 - Risk Assessment Criteria

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 4 2011-10-01 2011-10-01 false Risk Assessment Criteria B Appendix B to Part 236... B to Part 236—Risk Assessment Criteria The safety-critical performance of each product for which risk assessment is required under this part must be assessed in accordance with the following...

  18. 16 CFR 1610.7 - Test sequence and classification criteria.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Test sequence and classification criteria. 1610.7 Section 1610.7 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION FLAMMABLE FABRICS ACT REGULATIONS STANDARD FOR THE FLAMMABILITY OF CLOTHING TEXTILES The Standard § 1610.7 Test sequence and classification criteria. (a) Preliminary...

  19. 16 CFR 1031.13 - Criteria for employee involvement.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Criteria for employee involvement. 1031.13 Section 1031.13 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION GENERAL COMMISSION PARTICIPATION AND COMMISSION EMPLOYEE INVOLVEMENT IN VOLUNTARY STANDARDS ACTIVITIES Employee Involvement § 1031.13 Criteria for employee involvement....

  20. 29 CFR 1926.95 - Criteria for personal protective equipment.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 29 Labor 8 2014-07-01 2014-07-01 false Criteria for personal protective equipment. 1926.95 Section..., DEPARTMENT OF LABOR (CONTINUED) SAFETY AND HEALTH REGULATIONS FOR CONSTRUCTION Personal Protective and Life Saving Equipment § 1926.95 Criteria for personal protective equipment. (a) Application....

  1. 29 CFR 1926.95 - Criteria for personal protective equipment.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 29 Labor 8 2010-07-01 2010-07-01 false Criteria for personal protective equipment. 1926.95 Section..., DEPARTMENT OF LABOR (CONTINUED) SAFETY AND HEALTH REGULATIONS FOR CONSTRUCTION Personal Protective and Life Saving Equipment § 1926.95 Criteria for personal protective equipment. (a) Application....

  2. Packaging Design Criteria for the Steel Waste Package

    SciTech Connect

    BOEHNKE, W.M.

    2000-10-19

    This packaging design criteria provides the criteria for the design, fabrication, safety evaluation, and use of the steel waste package (SWP) to transport remote-handled waste and special-case waste from the 324 facility to Central Waste Complex (CWC) for interim storage.

  3. Nuclear safety

    NASA Technical Reports Server (NTRS)

    Buden, D.

    1991-01-01

    Topics dealing with nuclear safety are addressed which include the following: general safety requirements; safety design requirements; terrestrial safety; SP-100 Flight System key safety requirements; potential mission accidents and hazards; key safety features; ground operations; launch operations; flight operations; disposal; safety concerns; licensing; the nuclear engine for rocket vehicle application (NERVA) design philosophy; the NERVA flight safety program; and the NERVA safety plan.

  4. Administration of the Radiation Control for Health and Safety Act of 1968, Public Law 90-602, April 1, 1986 (1985 annual report). Report for 1 January-31 December 1985

    SciTech Connect

    Not Available

    1986-04-01

    The Food and Drug Administration, through its Center for Devices and Radiological Health, is responsible for the day-to-day administration of the Radiation Control for Health and Safety Act of 1968. The report provides a summary of the operations of the Center in carrying out that responsibility for calendar year 1985.

  5. Radiation safety concerns for pregnant or breast feeding patients. The positions of the NCRP and the ICRP

    SciTech Connect

    Meinhold, C.B.

    1997-01-01

    For many years, protecting the fetus has been a concern of the National Council on Radiation Protection and Measurements (NCRP) and the International Commission on Radiological Protection (ICRP). Early recommendations focused on the possibility of a wide variety of detrimental developmental effects while later recommendations focused on the potential for severe mental retardation and/or reduction in the intelligence quotient (I.Q.). The latest recommendations also note that the risk of cancer for the fetus is probably two to three times greater per Sv than in the adult. For all these reasons, the NCRP and the ICRP have provided guidance to physicians on taking all reasonable steps to ascertain whether any woman requiring a radiological or nuclear medicine procedure is pregnant or nursing a child. The NCRP and the ICRP also advise the clinician to postpone such procedures until after delivery or cessation of nursing, if possible.

  6. Radiation Emergencies

    MedlinePlus

    ... over a short period can cause burns or radiation sickness. If the exposure is large enough, it can cause premature aging or even death. Although there are no guarantees of safety during a radiation emergency, you can take actions to protect yourself. ...

  7. The role of medium radiation dose on microbiological safety and shelf-life of some traditional soups

    NASA Astrophysics Data System (ADS)

    Irawati, Z.; Natalia, L.; Nurcahya, C. M.; Anas, F.

    2007-11-01

    Irradiation at medium doses in combination with cryogenic condition along the process to ensure the safety, quality and to extend the shelf-life of prepared meals have been investigated. Semi-concentrated black, ox-tail, chicken vegetable and chicken sweet corn soups were individually packed in a dry laminate pouch of PET 12 μ/LDPE adh.2 μ/Al-foil 7 μ/LDPE adh/LLDPE (C 4) 50 μ under vacuum followed by freezing for 24 h at -18 °C prior to irradiation with doses of 1, 3, 5 and 7 kGy at cryogenic condition (-79 °C), respectively. Both the non-irradiated and irradiated prepared meals were then stored in refrigerator at 5±2 °C. Non-irradiated and the irradiated samples at 1 kGy were mostly damaged after a week of storage. Gamma irradiation at doses of 5-7 kGy for the soups could reduce microbial load by about 2-3 log cycles, respectively, without affecting the physical-chemical parameters and palatability within 2-3 months while the unirradiated samples could only withstand for 1 month storage time.

  8. [Evaluation of the risk of delayed adverse effects of chronic combined exposure to radiation and chemical factors with the purpose to ensure safety in orbital and exploration space missions].

    PubMed

    Shafirkin, A V; Mukhamedieva, L N; Tatarkin, S V; Barantseva, M Iu

    2012-01-01

    The work had the aim to anatomize the existing issues with providing safety in extended orbital and exploration missions for ensuing estimation of actual values of the total radiation risk for the crew, and risks of other delayed effects of simultaneous exposure to ionizing radiation and chemical pollutants in cabin air, and a number of other stressful factors inevitable in space flight. The flow of chronic experiments for separate and combined studies with reproduction of air makeup and radiation doses in actual orbital and predicted exploration missions is outlined. To set safety limits, new approaches should be applied to the description of gradual norm degradation to pathologies in addition to several generalized quantitative indices of adaptation and straining of the regulatory systems, as well as of effectiveness of the compensatory body reserve against separate and combined exposure. PMID:22624477

  9. IEEE Committee on Man and Radiation--COMAR technical information statement radiofrequency safety and utility Smart Meters.

    PubMed

    Bushberg, Jerrold T; Foster, Kenneth R; Hatfield, James B; Thansandote, Arthur; Tell, Richard A

    2015-03-01

    This Technical Information Statement describes Smart Meter technology as used with modern electric power metering systems and focuses on the radio frequency (RF) emissions associated with their operation relative to human RF exposure limits. Smart Meters typically employ low power (-1 W or less) transmitters that wirelessly send electric energy usage data to the utility company several times per day in the form of brief, pulsed emissions in the unlicensed frequency bands of 902-928 MHz and 2.4-2.48 GHz or on other nearby frequencies. Most Smart Meters operate as wireless mesh networks where each Smart Meter can communicate with other neighboring meters to relay data to a data collection point in the region. This communication process includes RF emissions from Smart Meters representing energy usage as well as the relaying of data from other meters and emissions associated with maintaining the meter's hierarchy within the wireless network. As a consequence, most Smart Meters emit RF pulses throughout the day, more at certain times and less at others. However, the duty cycle associated with all of these emissions is very small, typically less than 1%, and most of the time far less than 1%, meaning that most Smart Meters actually transmit RF fields for only a few minutes per day at most. The low peak power of Smart Meters and the very low duty cycles lead to the fact that accessible RF fields near Smart Meters are far below both U.S. and international RF safety limits whether judged on the basis of instantaneous peak power densities or time-averaged exposures. This conclusion holds for Smart Meters alone or installed in large banks of meters. PMID:25627954

  10. Performance criteria for dosimeter angular response

    SciTech Connect

    Roberson, P.L.; Fox, R. A.; Cummings, F. M.; McDonald, J. C.; Jones, K.L.

    1988-06-01

    This report provides criteria for evaluating the response of personnel dosimeters to radiation at nonperpendicular incidence. The US Department of Energy Laboratory Accreditation Program (DOELAP) ensures that dosimetry systems at DOE facilities meet acceptable standards for precision and accuracy. In the past, these standards were limited to tests for system variability, energy dependence, and level of detection. The proposed criteria will broaden the scope of DOELAP to include the angular response of personnel dosimeters. Because occupational exposures in the workplace are rarely due to radiation from only one direction, dosimeters must accurately assign individual dose equivalent from irradiation at any forward angle of incidence. Including an angular response criterion in DOELAP would improve the quality of personnel monitoring provided that the criterion is developed from appropriate dose quantities. This report provides guidance for assigning individual dose equivalents for radiation fields at nonperpendicular incidence to the dosimeter. 21 refs., 10 figs., 10 tabs.

  11. TIBER II/ETR final design report: Volume 3, 5. 0 Radiation safety and environment; 6. 0 Physics and technology R and D needs

    SciTech Connect

    Lee, J.D.

    1987-09-01

    This paper discusses the design of the TIBER II Tokamak. This particular volume discusses: safety and environmental requirements and design targets; accident analyses; personnel safety and maintenance exposure; effluent control; waste management and decommissioning; safety considerations in building design; and safety and environmental conclusions and recommendations. (LSP)

  12. 29 CFR 1926.95 - Criteria for personal protective equipment.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 29 Labor 8 2011-07-01 2011-07-01 false Criteria for personal protective equipment. 1926.95 Section 1926.95 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR (CONTINUED) SAFETY AND HEALTH REGULATIONS FOR CONSTRUCTION Personal Protective and Life Saving Equipment § 1926.95...

  13. 78 FR 58567 - Criteria to Certify Coal Mine Rescue Teams

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-24

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF LABOR Mine Safety and Health Administration Criteria to Certify Coal Mine Rescue Teams AGENCY: Mine Safety and Health Administration, Labor. ACTION: Notice of availability; request for comments. SUMMARY: The...

  14. 78 FR 79010 - Criteria to Certify Coal Mine Rescue Teams

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-12-27

    ... training. MSHA published a notice in the Federal Register (78 FR 58567) announcing the availability of the... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF LABOR Mine Safety and Health Administration Criteria to Certify Coal Mine Rescue Teams AGENCY: Mine Safety...

  15. Radiological Safety Handbook.

    ERIC Educational Resources Information Center

    Army Ordnance Center and School, Aberdeen Proving Ground, MD.

    Written to be used concurrently with the U.S. Army's Radiological Safety Course, this publication discusses the causes, sources, and detection of nuclear radiation. In addition, the transportation and disposal of radioactive materials are covered. The report also deals with the safety precautions to be observed when working with lasers, microwave…

  16. Design Criteria for Microbiological Facilities at Fort Detrick. Volume II: Design Criteria

    ERIC Educational Resources Information Center

    Army Biological Labs., Fort Detrick, MD. Industrial Health and Safety Div.

    Volume II of a two-volume manual of design criteria, based primarily on biological safety considerations. It is prepared for the use of architect-engineers in designing new or modified microbiological facilities for Fort Detrick, Maryland. Volume II is divided into the following sections: (1) architectural, (2) heating, ventilating, and air…

  17. SU-E-T-248: Near Real-Time Analysis of Radiation Delivery and Imaging, Accuracy to Ensure Patient Safety

    SciTech Connect

    Wijesooriya, K; Seitter, K; Desai, V; Read, P; Larner, J

    2014-06-01

    Purpose: To develop and optimize an effective software method for comparing planned to delivered control point machine parameters for all VARIAN TrueBeam treatments so as to permit (1) assessment of a large patient pool throughout their treatment course to quantify treatment technique specific systematic and random uncertainty of observables, (2) quantify the site specific daily imaging shifts required for target alignment, and (3) define tolerance levels for mechanical parameters and imaging parameters based on statistical analysis data gathered, and the dosimetric impact of variations. Methods: Treatment and imaging log files were directly compared to plan parameters for Eclipse and Pinnacle planned treatments via 3D, IMRT, control point, RapidArc, and electrons. Each control point from all beams/arcs (7984) for all fractions (1940) of all patients treated over six months were analyzed. At each control point gantry angle, collimator angle, couch angle, jaw positions, MLC positions, MU were compared. Additionally per-treatment isocenter shifts were calculated. Results were analyzed as a whole in treatment type subsets: IMRT, 3D, RapidArc; and in treatment site subsets: brain, chest/mediastinum, esophagus, H and N, lung, pelvis, prostate. Results: Daily imaging isocenter shifts from initial external tattoo alignment were dependent on the treatment site with < 0.5 cm translational shifts for H and N, Brain, and lung SBRT, while pelvis, esophagus shifts were ∼1 cm. Mechanical delivery parameters were within tolerance levels for all sub-beams. The largest variations were for RapidArc plans: gantry angle 0.11±0.12,collimator angle 0.00±0.00, jaw positions 0.48±0.26, MLC leaf positions 0.66±0.08, MU 0.14±0.34. Conclusion: Per-control point validation reveals deviations between planned and delivered parameters. If used in a near real-time error checking system, patient safety can be improved by equipping the treatment delivery system with additional forcing

  18. NWTS program criteria for mined geologic disposal of nuclear waste: repository performance and development criteria. Public draft

    SciTech Connect

    1982-07-01

    This document, DOE/NWTS-33(3) is one of a series of documents to establish the National Waste Terminal Storage (NWTS) program criteria for mined geologic disposal of high-level radioactive waste. For both repository performance and repository development it delineates the criteria for design performance, radiological safety, mining safety, long-term containment and isolation, operations, and decommissioning. The US Department of Energy will use these criteria to guide the development of repositories to assist in achieving performance and will reevaluate their use when the US Nuclear Regulatory Commission issues radioactive waste repository rules.

  19. RADIATION SAFETY CONSIDERATIONS FOR THE USE OF 223RaCl2 DE IN MEN WITH CASTRATION-RESISTANT PROSTATE CANCER

    PubMed Central

    Dauer, Lawrence T.; Williamson, Matthew J.; Humm, John; O’Donoghue, Joseph; Ghani, Rashid; Awadallah, Robert; Carrasquillo, Jorge; Pandit-Taskar, Neeta; Aksnes, Anne-Kirsti; Biggin, Colin; Reinton, Vigdis; Morris, Michael; St Germain, Jean

    2016-01-01

    The majority of patients with late stage castration-resistant prostate cancer (CRPC) develop bone metastases that often result in significant bone pain. Therapeutic palliation strategies can delay or prevent skeletal complications and may prolong survival. An alpha-particle based therapy, radium-223 dichloride (223RaCl2), has been developed that delivers highly localized effects in target areas and likely reduces toxicity to adjacent healthy tissue, particularly bone marrow. Radiation safety aspects were evaluated for a single comprehensive cancer center clinical phase 1, open-label, single ascending-dose study for three cohorts at 50, 100, or 200 kBq kg−1 body weight. Ten patients received administrations, and six patients completed the study with 1 y follow-up. Dose rates from patients administered 223Ra dichloride were typically less than 2 μSv h−1 MBq−1 on contact and averaged 0.02 μSv h−1 MBq−1 at 1 m immediately following administration. Removal was primarily by fecal excretion, and whole body effective half-lives were highly dependent upon fecal compartment transfer, ranging from 2.5–11.4 d. Radium-223 is safe and straightforward to administer using conventional nuclear medicine equipment. For this clinical study, few radiation protection limitations were recommended post-therapy based on facility evaluations. Specific precautions are dependent on local regulatory authority guidance. Subsequent studies have demonstrated significantly improved overall survival and very low toxicity, suggesting that 223Ra may provide a new standard of care for patients with CRPC and bone metastases. PMID:24562070

  20. SU-E-I-10: Automatic Monitoring of Accumulated Dose Indices From DICOM RDSR to Improve Radiation Safety in X-Ray Angiography

    SciTech Connect

    Omar, A; Bujila, R; Nowik, P; Karambatsakidou, A

    2014-06-01

    Purpose: To investigate the potential benefits of automatic monitoring of accumulated patient and staff dose indicators, i.e., CAK and KAP, from DICOM Radiation Dose Structured Reports (RDSR) in x-ray angiography (XA). Methods: Recently RDSR has enabled the convenient aggregation of dose indices and technique parameters for XA procedures. The information contained in RDSR objects for three XA systems, dedicated to different types of clinical procedures, has been collected and aggregated in a database for over one year using a system developed with open-source software at the Karolinska University Hospital. Patient weight was complemented to the RDSR data via an interface with the Hospital Information System (HIS). Results: The linearly approximated trend in KAP over a time period of a year for cerebrovascular, pelvic/peripheral vascular, and cardiovascular procedures showed a decrease of 12%, 20%, and 14%, respectively. The decrease was mainly due to hardware/software upgrades and new low-dose imaging protocols, and partially due to ongoing systematic radiation safety education of the clinical staff. The CAK was in excess of 3 Gy for 15 procedures, and exceeded 5 Gy for 3 procedures. The dose indices have also shown a significant dependence on patient weight for cardiovascular and pelvic/peripheral vascular procedures; a 10 kg shift in mean patient weight can result in a dose index increase of 25%. Conclusion: Automatic monitoring of accumulated dose indices can be utilized to notify the clinical staff and medical physicists when the dose index has exceeded a predetermined action level. This allows for convenient and systematic follow-up of patients in risk of developing deterministic skin injuries. Furthermore, trend analyses of dose indices over time is a valuable resource for the identification of potential positive or negative effects (dose increase/decrease) from changes in hardware, software, and clinical work habits.

  1. Stereotactic Body Radiation Therapy for Non-Small Cell Lung Cancer Tumors Greater Than 5 cm: Safety and Efficacy

    SciTech Connect

    Woody, Neil M. Stephans, Kevin L.; Marwaha, Gaurav; Djemil, Toufik; Videtic, Gregory M.M.

    2015-06-01

    Purpose: The purpose of this study was to determine outcomes of patients with node-negative medically inoperable non-small cell lung cancer (NSCLC) whose primary tumors exceeded 5 cm and were treated with stereotactic body radiation therapy (SBRT). Methods and Materials: We surveyed our institutional prospective lung SBRT registry to identify treated patients with tumors >5 cm. Treatment outcomes for local control (LC), locoregional control (LRC), disease-free survival (DFS), and overall survival (OS) were assessed by Kaplan-Meier estimates. Toxicities were graded according to Common Terminology Criteria for Adverse Events version 4. Mean pretreatment pulmonary function test values were compared to mean posttreatment values. Results: From December 2003 to July 2014, 40 patients met study criteria. Median follow-up was 10.8 months (range: 0.4-70.3 months). Median age was 76 years (range: 56-90 years), median body mass index was 24.3 (range: 17.7-37.2), median Karnofsky performance score was 80 (range: 60-90), and median Charlson comorbidity index score was 2 (range: 0-5). Median forced expiratory volume in 1 second (FEV1) was 1.41 L (range: 0.47-3.67 L), and median diffusion capacity (DLCO) was 47% of predicted (range: 29%-80%). All patients were staged by fluorodeoxyglucose-positron emission tomography/computed tomography staging, and 47.5% underwent mediastinal staging by endobronchial ultrasonography. Median tumor size was 5.6 cm (range: 5.1-10 cm), median SBRT dose was 50 Gy (range: 30-60 Gy) in 5 fractions (range: 3-10 fractions). Eighteen-month LC, LRC, DFS, and OS rates were 91.2%, 64.4%, 34.6%, and 59.7%, respectively. Distant failure was the predominant pattern of failure (32.5%). Three patients (7.5%) experienced grade 3 or higher toxicity. Mean posttreatment FEV1 was not significantly reduced (P=.51), but a statistically significant absolute 6.5% (P=.03) reduction in DLCO was observed. Conclusions: Lung SBRT for medically inoperable node

  2. Radiological criteria for the remediation of sites for spent fuel and radioactive waste storage in the Russian Northwest.

    PubMed

    Shandala, N K; Sneve, M K; Titov, A V; Smith, G M; Novikova, N Ya; Romanov, V V; Seregin, V A

    2008-12-01

    In the 1960s, two technical bases of the Northern Fleet were created in Northwest Russia, at Andreeva Bay in the Kola Peninsula and Gremikha village on the coast of the Barents Sea. They maintained nuclear submarines, performing receipt and storage of radioactive waste and spent nuclear fuel, and are now designated sites of temporary storage (STSs). An analysis of the radiation situation at these sites demonstrates that substantial long-term remediation work will be required after the removal of the waste and spent nuclear fuel. Regulatory guidance is under development to support this work. Having in mind modern approaches to guaranteeing radiation safety, the primary regulatory focus is on a justification of dose constraints for determining acceptable residual contamination which might lead to exposure to workers and the public. For these sites, four principal options for remediation have been considered-renovation, conversion, conservation and liquidation. This paper describes a system of recommended dose constraints and derived control levels formulated for each option. The unconditional guarantee of long-term radioecological protection provides the basis for criteria development. Non-exceedance of these dose constraints and control levels implies compliance with radiological protection objectives related to the residual contamination. Dose reduction below proposed dose constraint values must also be carried out according to the optimisation principle. The developed criteria relate to the condition of the facilities and the STS areas after the termination of remediation activities. The proposed criteria for renovation, conversion, conservation and liquidation are entirely within the dose limits adopted in Russia for the management of man-made radiation sources, and are consistent with ICRP recommendations and national practice in other countries. The proposed criteria for STS remediation and new industrial (non-radiation-hazardous) facilities and buildings on

  3. SAB report: Radionuclides in drinking water. Review of the Office of Drinking Water`s criteria documents and related reports for uranium, radon, and man-made beta-gamma emitters by the radiation advisory committee

    SciTech Connect

    1991-12-01

    EPA`s Office of Drinking Water developed draft criteria documents and related reports that were the basis for new drinking water standards for uranium, radium, radon and man-made beta-gamma emitting radionuclides during the period November 1989-July 1990. The overall quality of the four draft criteria documents submitted to the Subcommittee for its review was not good. Taken as a set, the documents are inconsistent in approach and with Agency practice in the derivation of drinking water criteria for other contaminants.

  4. NASA Lewis Wind Tunnel Model Systems Criteria

    NASA Technical Reports Server (NTRS)

    Soeder, Ronald H.; Haller, Henry C.

    1994-01-01

    This report describes criteria for the design, analysis, quality assurance, and documentation of models or test articles that are to be tested in the aeropropulsion facilities at the NASA Lewis Research Center. The report presents three methods for computing model allowable stresses on the basis of the yield stress or ultimate stress, and it gives quality assurance criteria for models tested in Lewis' aeropropulsion facilities. Both customer-furnished model systems and in-house model systems are discussed. The functions of the facility manager, project engineer, operations engineer, research engineer, and facility electrical engineer are defined. The format for pretest meetings, prerun safety meetings, and the model criteria review are outlined Then, the format for the model systems report (a requirement for each model that is to be tested at NASA Lewis) is described, the engineers that are responsible for developing the model systems report are listed, and the time table for its delivery to the facility manager is given.

  5. A Silent Safety Program

    NASA Technical Reports Server (NTRS)

    Goodin, James Ronald

    2006-01-01

    NASA's Columbia Accident Investigation Board (CAIB) referred 8 times to the NASA "Silent Safety Program." This term, "Silent Safety Program" was not an original observation but first appeared in the Rogers Commission's Investigation of the Challenger Mishap. The CAIB on page 183 of its report in the paragraph titled 'Encouraging Minority Opinion,' stated "The Naval Reactor Program encourages minority opinions and "bad news." Leaders continually emphasize that when no minority opinions are present, the responsibility for a thorough and critical examination falls to management. . . Board interviews revealed that it is difficult for minority and dissenting opinions to percolate up through the agency's hierarchy. . ." The first question and perhaps the only question is - what is a silent safety program? Well, a silent safety program may be the same as the dog that didn't bark in Sherlock Holmes' "Adventure of the Silver Blaze" because system safety should behave as a devil's advocate for the program barking on every occasion to insure a critical review inclusion. This paper evaluates the NASA safety program and provides suggestions to prevent the recurrence of the silent safety program alluded to in the Challenger Mishap Investigation. Specifically targeted in the CAM report, "The checks and balances the safety system was meant to provide were not working." A silent system safety program is not unique to NASA but could emerge in any and every organization. Principles developed by Irving Janis in his book, Groupthink, listed criteria used to evaluate an organization's cultural attributes that allows a silent safety program to evolve. If evidence validates Jams's criteria, then Jams's recommendations for preventing groupthink can also be used to improve a critical evaluation and thus prevent the development of a silent safety program.

  6. Hanford Site solid waste acceptance criteria

    SciTech Connect

    Ellefson, M.D.

    1998-07-01

    Order 5820.2A requires that each treatment, storage, and/or disposal facility (referred to in this document as TSD unit) that manages low-level or transuranic waste (including mixed waste and TSCA PCB waste) maintain waste acceptance criteria. These criteria must address the various requirements to operate the TSD unit in compliance with applicable safety and environmental requirements. This document sets forth the baseline criteria for acceptance of radioactive waste at TSD units operated by WMH. The criteria for each TSD unit have been established to ensure that waste accepted can be managed in a manner that is within the operating requirements of the unit, including environmental regulations, DOE Orders, permits, technical safety requirements, waste analysis plans, performance assessments, and other applicable requirements. Acceptance criteria apply to the following TSD units: the Low-Level Burial Grounds (LLBG) including both the nonregulated portions of the LLBG and trenches 31 and 34 of the 218-W-5 Burial Ground for mixed waste disposal; Central Waste Complex (CWC); Waste Receiving and Processing Facility (WRAP); and T Plant Complex. Waste from all generators, both from the Hanford Site and from offsite facilities, must comply with these criteria. Exceptions can be granted as provided in Section 1.6. Specific waste streams could have additional requirements based on the 1901 identified TSD pathway. These requirements are communicated in the Waste Specification Records (WSRds). The Hanford Site manages nonradioactive waste through direct shipments to offsite contractors. The waste acceptance requirements of the offsite TSD facility must be met for these nonradioactive wastes. This document does not address the acceptance requirements of these offsite facilities.

  7. Fast Flux Test Facility final safety analysis report. Amendment 73

    SciTech Connect

    Gantt, D.A.

    1993-08-01

    This report provides Final Safety Analysis Report (FSAR) Amendment 73 for incorporation into the Fast Flux Test Facility (FFTR) FSAR set. This page change incorporates Engineering Change Notices (ECNs) issued subsequent to Amendment 72 and approved for incorparoration before May 6, 1993. These changes include: Chapter 3, design criteria structures, equipment, and systems; chapter 5B, reactor coolant system; chapter 7, instrumentation and control systems; chapter 9, auxiliary systems; chapter 11, reactor refueling system; chapter 12, radiation protection and waste management; chapter 13, conduct of operations; chapter 17, technical specifications; chapter 20, FFTF criticality specifications; appendix C, local fuel failure events; and appendix Fl, operation at 680{degrees}F inlet temperature.

  8. Lung donor selection criteria

    PubMed Central

    Chaney, John; Suzuki, Yoshikazu; Cantu, Edward

    2014-01-01

    The criteria that define acceptable physiologic and social parameters for lung donation have remained constant since their empiric determination in the 1980s. These criteria include a donor age between 25-40, a arterial partial pressure of oxygen (PaO2)/FiO2 ratio greater than 350, no smoking history, a clear chest X-ray, clean bronchoscopy, and a minimal ischemic time. Due to the paucity of organ donors, and the increasing number of patients requiring lung transplant, finding a donor that meets all of these criteria is quite rare. As such, many transplants have been performed where the donor does not meet these stringent criteria. Over the last decade, numerous reports have been published examining the effects of individual acceptance criteria on lung transplant survival and graft function. These studies suggest that there is little impact of the historical criteria on either short or long term outcomes. For age, donors should be within 18 to 64 years old. Gender may relay benefit to all female recipients especially in male to female transplants, although results are mixed in these studies. Race matched donor/recipients have improved outcomes and African American donors convey worse prognosis. Smoking donors may decrease recipient survival post transplant, but provide a life saving opportunity for recipients that may otherwise remain on the transplant waiting list. No specific gram stain or bronchoscopic findings are reflected in recipient outcomes. Chest radiographs are a poor indicator of lung donor function and should not adversely affect organ usage aside for concerns over malignancy. Ischemic time greater than six hours has no documented adverse effects on recipient mortality and should not limit donor retrieval distances. Brain dead donors and deceased donors have equivalent prognosis. Initial PaO2/FiO2 ratios less than 300 should not dissuade donor organ usage, although recruitment techniques should be implemented with intent to transplant. PMID:25132970

  9. Lung donor selection criteria.

    PubMed

    Chaney, John; Suzuki, Yoshikazu; Cantu, Edward; van Berkel, Victor

    2014-08-01

    The criteria that define acceptable physiologic and social parameters for lung donation have remained constant since their empiric determination in the 1980s. These criteria include a donor age between 25-40, a arterial partial pressure of oxygen (PaO2)/FiO2 ratio greater than 350, no smoking history, a clear chest X-ray, clean bronchoscopy, and a minimal ischemic time. Due to the paucity of organ donors, and the increasing number of patients requiring lung transplant, finding a donor that meets all of these criteria is quite rare. As such, many transplants have been performed where the donor does not meet these stringent criteria. Over the last decade, numerous reports have been published examining the effects of individual acceptance criteria on lung transplant survival and graft function. These studies suggest that there is little impact of the historical criteria on either short or long term outcomes. For age, donors should be within 18 to 64 years old. Gender may relay benefit to all female recipients especially in male to female transplants, although results are mixed in these studies. Race matched donor/recipients have improved outcomes and African American donors convey worse prognosis. Smoking donors may decrease recipient survival post transplant, but provide a life saving opportunity for recipients that may otherwise remain on the transplant waiting list. No specific gram stain or bronchoscopic findings are reflected in recipient outcomes. Chest radiographs are a poor indicator of lung donor function and should not adversely affect organ usage aside for concerns over malignancy. Ischemic time greater than six hours has no documented adverse effects on recipient mortality and should not limit donor retrieval distances. Brain dead donors and deceased donors have equivalent prognosis. Initial PaO2/FiO2 ratios less than 300 should not dissuade donor organ usage, although recruitment techniques should be implemented with intent to transplant. PMID:25132970

  10. 75 FR 63433 - National Advisory Committee on Microbiological Criteria for Foods; Re-Establishment

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-10-15

    ...; ] DEPARTMENT OF AGRICULTURE Food Safety and Inspection Service National Advisory Committee on Microbiological Criteria for Foods; Re-Establishment AGENCY: Food Safety and Inspection Service, USDA. ACTION: Notice of re... announcing the re-chartering of the National Advisory Committee on Microbiological Criteria for Foods...

  11. Maintaining radiation protection records

    SciTech Connect

    Not Available

    1992-11-30

    This Report is part of a series prepared under the auspices of Scientific Committee 46 on Operational Radiation Safety. It provides guidance on maintaining radiation protection records. Record keeping is an essential element of every radiation protection program. This Report describes the elements that should enter into the design of a program for the maintenance of operational radiation safety records. The problems of the length of time for retention of records for operational, regulatory, epidemiologic and legal uses are discussed in detail.

  12. Task D: Hydrogen safety analysis

    SciTech Connect

    Swain, M.R.; Sievert, B.G.; Swain, M.N.

    1996-10-01

    This report covers two topics. The first is a review of codes, standards, regulations, recommendations, certifications, and pamphlets which address safety of gaseous fuels. The second is an experimental investigation of hydrogen flame impingement. Four areas of concern in the conversion of natural gas safety publications to hydrogen safety publications are delineated. Two suggested design criteria for hydrogen vehicle fuel systems are proposed. It is concluded from the experimental work that light weight, low cost, firewalls to resist hydrogen flame impingement are feasible.

  13. DOE Standard: Fire protection design criteria

    SciTech Connect

    Not Available

    1999-07-01

    The development of this Standard reflects the fact that national consensus standards and other design criteria do not comprehensively or, in some cases, adequately address fire protection issues at DOE facilities. This Standard provides supplemental fire protection guidance applicable to the design and construction of DOE facilities and site features (such as water distribution systems) that are also provided for fire protection. It is intended to be used in conjunction with the applicable building code, National Fire Protection Association (NFPA) Codes and Standards, and any other applicable DOE construction criteria. This Standard replaces certain mandatory fire protection requirements that were formerly in DOE 5480.7A, ``Fire Protection``, and DOE 6430.1A, ``General Design Criteria``. It also contains the fire protection guidelines from two (now canceled) draft standards: ``Glove Box Fire Protection`` and ``Filter Plenum Fire Protection``. (Note: This Standard does not supersede the requirements of DOE 5480.7A and DOE 6430.1A where these DOE Orders are currently applicable under existing contracts.) This Standard, along with the criteria delineated in Section 3, constitutes the basic criteria for satisfying DOE fire and life safety objectives for the design and construction or renovation of DOE facilities.

  14. Revisiting Bioaccumulation Criteria

    EPA Science Inventory

    The objective of workgroup 5 was to revisit the B(ioaccumulation) criteria that are currently being used to identify POPs under the Stockholm Convention and PBTs under CEPA, TSCA, REACh and other programs. Despite the lack of a recognized definition for a B substance, we defined ...

  15. Laboratory Equipment Criteria.

    ERIC Educational Resources Information Center

    State Univ. Construction Fund, Albany, NY.

    Requirements for planning, designing, constructing and installing laboratory furniture are given in conjunction with establishing facility criteria for housing laboratory equipment. Furniture and equipment described include--(1) center tables, (2) reagent racks, (3) laboratory benches and their mechanical fixtures, (4) sink and work counters, (5)…

  16. Graphite criteria peer review

    SciTech Connect

    1986-09-01

    This report documents a review of the stress criteria proposed for the graphite components of the modular high temperature gas-cooled reactor (MHTGR) core. The review was conducted by a panel of six independent consultants, chosen for their expertise over a range of relevant disciplines.

  17. CRITERIA FOR COUNSELOR PERFORMANCE.

    ERIC Educational Resources Information Center

    MILLER, LEONARD A.; MUTHARD, JOHN E.

    THIS RESEARCH CONCERNS THE RELATIONSHIPS AMONG REHABILITATION COUNSELOR PERFORMANCE CRITERIA CURRENTLY BEING USED OR READILY AVAILABLE TO STATE VOCATIONAL REHABILITATION AGENCIES. THE 143 COUNSELORS STUDIED CAME FROM MIDDLE-SIZED AGENCIES IN SIX STATES AND, SINCE COWORKER RATINGS WERE REQUIRED, THE SAMPLE WAS LIMITED TO COUNSELORS WORKING WITH TWO…

  18. Safety system status monitoring

    SciTech Connect

    Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

    1984-03-01

    The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants. The goals of the study were to assess for the NRC the effectiveness of current monitoring systems and procedures, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue. A review of safety system status monitoring practices indicated that current systems and procedures do not adequately aid control room operators in monitoring safety system status. This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47). In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status. Also suggested are near-term guidelines that could reduce the likelihood of human errors in specific, high-priority status monitoring tasks. It is recommended that (1) Regulatory Guide 1.47 be revised to address these acceptance criteria, and (2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide.

  19. Unified nonclassicality criteria

    NASA Astrophysics Data System (ADS)

    Ryl, S.; Sperling, J.; Agudelo, E.; Mraz, M.; Köhnke, S.; Hage, B.; Vogel, W.

    2015-07-01

    In this work we generalize the Bochner criterion addressing the characteristic function, i.e., the Fourier transform, of the Glauber-Sudarshan phase-space function. For this purpose we extend the Bochner theorem by including derivatives of the characteristic function. The resulting necessary and sufficient nonclassicality criteria unify previously known moment-based criteria with those based on the characteristic function. For applications of the generalized nonclassicality probes, we provide direct sampling formulas for balanced homodyne detection. A squeezed vacuum state is experimentally realized and characterized with our method. This complete framework—theoretical unification, sampling approach, and experimental implementation—presents an efficient toolbox to characterize quantum states of light for applications in quantum technology.

  20. Falcon: automated optimization method for arbitrary assessment criteria

    DOEpatents

    Yang, Tser-Yuan; Moses, Edward I.; Hartmann-Siantar, Christine

    2001-01-01

    FALCON is a method for automatic multivariable optimization for arbitrary assessment criteria that can be applied to numerous fields where outcome simulation is combined with optimization and assessment criteria. A specific implementation of FALCON is for automatic radiation therapy treatment planning. In this application, FALCON implements dose calculations into the planning process and optimizes available beam delivery modifier parameters to determine the treatment plan that best meets clinical decision-making criteria. FALCON is described in the context of the optimization of external-beam radiation therapy and intensity modulated radiation therapy (IMRT), but the concepts could also be applied to internal (brachytherapy) radiotherapy. The radiation beams could consist of photons or any charged or uncharged particles. The concept of optimizing source distributions can be applied to complex radiography (e.g. flash x-ray or proton) to improve the imaging capabilities of facilities proposed for science-based stockpile stewardship.

  1. DOE 2011 Occupational Radiation Exposure report, _Prepared for the U.S. Department of Energy, Office of Health, Safety and Security. December 2012

    SciTech Connect

    Derek Hagemeyer, Yolanda McCormick

    2012-12-12

    This report discusses radiation protection and dose reporting requirements, presents the 2011 occupational radiation dose data along with trends over the past 5 years, and provides instructions to submit successful as low as reasonably achievable (ALARA) projects.

  2. PML diagnostic criteria

    PubMed Central

    Aksamit, Allen J.; Clifford, David B.; Davis, Larry; Koralnik, Igor J.; Sejvar, James J.; Bartt, Russell; Major, Eugene O.; Nath, Avindra

    2013-01-01

    Objective: To establish criteria for the diagnosis of progressive multifocal leukoencephalopathy (PML). Methods: We reviewed available literature to identify various diagnostic criteria employed. Several search strategies employing the terms “progressive multifocal leukoencephalopathy” with or without “JC virus” were performed with PubMed, SCOPUS, and EMBASE search engines. The articles were reviewed by a committee of individuals with expertise in the disorder in order to determine the most useful applicable criteria. Results: A consensus statement was developed employing clinical, imaging, pathologic, and virologic evidence in support of the diagnosis of PML. Two separate pathways, histopathologic and clinical, for PML diagnosis are proposed. Diagnostic classification includes certain, probable, possible, and not PML. Conclusion: Definitive diagnosis of PML requires neuropathologic demonstration of the typical histopathologic triad (demyelination, bizarre astrocytes, and enlarged oligodendroglial nuclei) coupled with the techniques to show the presence of JC virus. The presence of clinical and imaging manifestations consistent with the diagnosis and not better explained by other disorders coupled with the demonstration of JC virus by PCR in CSF is also considered diagnostic. Algorithms for establishing the diagnosis have been recommended. PMID:23568998

  3. EDITORIAL: Safety aspects of fusion power plants

    NASA Astrophysics Data System (ADS)

    Kolbasov, B. N.

    2007-07-01

    importance for the fusion power plant research programmes. The objective of this Technical Meeting was to examine in an integrated way all the safety aspects anticipated to be relevant to the first fusion power plant prototype expected to become operational by the middle of the century, leading to the first generation of economically viable fusion power plants with attractive S&E features. After screening by guest editors and consideration by referees, 13 (out of 28) papers were accepted for publication. They are devoted to the following safety topics: power plant safety; fusion specific operational safety approaches; test blanket modules; accident analysis; tritium safety and inventories; decommissioning and waste. The paper `Main safety issues at the transition from ITER to fusion power plants' by W. Gulden et al (EU) highlights the differences between ITER and future fusion power plants with magnetic confinement (off-site dose acceptance criteria, consequences of accidents inside and outside the design basis, occupational radiation exposure, and waste management, including recycling and/or final disposal in repositories) on the basis of the most recent European fusion power plant conceptual study. Ongoing S&E studies within the US inertial fusion energy (IFE) community are focusing on two design concepts. These are the high average power laser (HAPL) programme for development of a dry-wall, laser-driven IFE power plant, and the Z-pinch IFE programme for the production of an economically-attractive power plant using high-yield Z-pinch-driven targets. The main safety issues related to these programmes are reviewed in the paper `Status of IFE safety and environmental activities in the US' by S. Reyes et al (USA). The authors propose future directions of research in the IFE S&E area. In the paper `Recent accomplishments and future directions in the US Fusion Safety & Environmental Program' D. Petti et al (USA) state that the US fusion programme has long recognized that the S

  4. 10 CFR 39.67 - Radiation surveys.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Radiation surveys. 39.67 Section 39.67 Energy NUCLEAR REGULATORY COMMISSION LICENSES AND RADIATION SAFETY REQUIREMENTS FOR WELL LOGGING Radiation Safety Requirements § 39.67 Radiation surveys. (a) The licensee shall make radiation surveys, including but...

  5. 10 CFR 39.67 - Radiation surveys.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false Radiation surveys. 39.67 Section 39.67 Energy NUCLEAR REGULATORY COMMISSION LICENSES AND RADIATION SAFETY REQUIREMENTS FOR WELL LOGGING Radiation Safety Requirements § 39.67 Radiation surveys. (a) The licensee shall make radiation surveys, including but not limited to the surveys required under paragraphs...

  6. 10 CFR 39.67 - Radiation surveys.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 1 2013-01-01 2013-01-01 false Radiation surveys. 39.67 Section 39.67 Energy NUCLEAR REGULATORY COMMISSION LICENSES AND RADIATION SAFETY REQUIREMENTS FOR WELL LOGGING Radiation Safety Requirements § 39.67 Radiation surveys. (a) The licensee shall make radiation surveys, including but...

  7. 10 CFR 39.67 - Radiation surveys.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 1 2014-01-01 2014-01-01 false Radiation surveys. 39.67 Section 39.67 Energy NUCLEAR REGULATORY COMMISSION LICENSES AND RADIATION SAFETY REQUIREMENTS FOR WELL LOGGING Radiation Safety Requirements § 39.67 Radiation surveys. (a) The licensee shall make radiation surveys, including but...

  8. Preliminary criteria for the fracture control of space shuttle structures

    NASA Technical Reports Server (NTRS)

    1971-01-01

    The complex and multidisciplinary factors are presented which relate to the prevention of structural failure due to the initiation or propagation of cracks or crack-like defects. The fracture control criteria are applicable to space shuttle components which are: (1) susceptible to cracking or fracture on the basis of anticipated loads and environment, and (2) critical to either crew safety or system performance. The criteria define the design, fabrication, environmental control, inspection, maintenance, repair, and verification procedures required for adequate fracture control.

  9. 28 CFR 79.42 - Criteria for eligibility for claims by miners.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 28 Judicial Administration 2 2010-07-01 2010-07-01 false Criteria for eligibility for claims by miners. 79.42 Section 79.42 Judicial Administration DEPARTMENT OF JUSTICE (CONTINUED) CLAIMS UNDER THE RADIATION EXPOSURE COMPENSATION ACT Eligibility Criteria for Claims by Uranium Miners § 79.42 Criteria for eligibility for claims by miners....

  10. Criteria for Assessing Naturalistic Inquiries as Reports.

    ERIC Educational Resources Information Center

    Lincoln, Yvonna S.; Guba, Egon G.

    Research on the assessment of naturalistic inquiries is reviewed, and criteria for assessment are outlined. Criteria reviewed include early foundational and non-foundational criteria, trustworthiness criteria, axiomatic criteria, rhetorical criteria, action criteria, and application/transferability criteria. Case studies that are reports of…

  11. Science Goals in Radiation Protection for Exploration

    NASA Technical Reports Server (NTRS)

    Cucinotta, Francs A.

    2008-01-01

    Space radiation presents major challenges to future missions to the Earth s moon or Mars. Health risks of concern include cancer, degenerative and performance risks to the central nervous system, heart and lens, and the acute radiation syndromes. The galactic cosmic rays (GCR) contain high energy and charge (HZE) nuclei, which have been shown to cause qualitatively distinct biological damage compared to terresterial radiation, such as X-rays or gamma-rays, causing risk estimates to be highly uncertain. The biological effects of solar particle events (SPE) are similar to terresterial radiation except for their biological dose-rate modifiers; however the onset and size of SPEs are difficult to predict. The high energies of GCR reduce the effectiveness of shielding, while SPE s can be shielded however the current gap in radiobiological knowledge hinders optimization. Methods used to project risks on Earth must be modified because of the large uncertainties in projecting health risks from space radiation, and thus impact mission requirements and costs. We describe NASA s unique approach to radiation safety that applies probabilistic risk assessments and uncertainty based criteria within the occupational health program for astronauts and to mission design. The two terrestrial criteria of a point estimate of maximum acceptable level of risk and application of the principle of As Low As Reasonably Achievable (ALARA) are supplemented by a third requirement that protects against risk projection uncertainties using the upper 95% confidence level (CL) in radiation risk projection models. Exploration science goals in radiation protection are centered on ground-based research to achieve the necessary biological knowledge, and in the development of new technologies to improve SPE monitoring and optimize shielding. Radiobiology research is centered on a ground based program investigating the radiobiology of high-energy protons and HZE nuclei at the NASA Space Radiation Laboratory

  12. 28 CFR 79.42 - Criteria for eligibility for claims by miners.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... RADIATION EXPOSURE COMPENSATION ACT Eligibility Criteria for Claims by Uranium Miners § 79.42 Criteria for... her mining employment to 40 or more working level months of radiation or worked for at least one year... claimant contracted lung cancer or a nonmalignant respiratory disease following such exposure....

  13. 28 CFR 79.42 - Criteria for eligibility for claims by miners.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... RADIATION EXPOSURE COMPENSATION ACT Eligibility Criteria for Claims by Uranium Miners § 79.42 Criteria for... her mining employment to 40 or more working level months of radiation or worked for at least one year... claimant contracted lung cancer or a nonmalignant respiratory disease following such exposure....

  14. 28 CFR 79.42 - Criteria for eligibility for claims by miners.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... RADIATION EXPOSURE COMPENSATION ACT Eligibility Criteria for Claims by Uranium Miners § 79.42 Criteria for... her mining employment to 40 or more working level months of radiation or worked for at least one year... claimant contracted lung cancer or a nonmalignant respiratory disease following such exposure....

  15. 28 CFR 79.42 - Criteria for eligibility for claims by miners.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... RADIATION EXPOSURE COMPENSATION ACT Eligibility Criteria for Claims by Uranium Miners § 79.42 Criteria for... her mining employment to 40 or more working level months of radiation or worked for at least one year... claimant contracted lung cancer or a nonmalignant respiratory disease following such exposure....

  16. [Substantiation of a complex of radiation-hygienic approaches to the management of very low-level waste].

    PubMed

    Korenkov, I P; Lashchenova, T N; Shandala, N K

    2015-01-01

    In the article there are presented materials on radiation-hygienic approaches to the treatment of very low level radioactive waste (VLLW) and industrial waste containing radionuclides. There is done detailed information on radiation-hygienic principles and criteria for the assurance ofradiation safety in the collection, transportation, storage and processing of VLLW as a category of radioactive waste.. Particular attention is paid to the problem of designing VLLW landfill site choice, system of radiation monitoring in operation and decommissioning of the landfill. There are presented data about the criteria for the release of VLLW buried at the site, from regulatory control. Also there are considered in detail the radiation-hygienic requirements for radiation safety of industrial waste containing radionuclides for which there is assumed unlimited and limited use of solid materials in economic activity, based on the requirements ofthe revised Basic Sanitary Rules for Radiation Safety - 99/2010. There are considered basic requirements for the organization of industrial waste landfill. As an example, there-are presented the hygiene requirements for industrial waste management and results of waste categorization in Northern Federal Enterprise for Radioactive Waste Management. PMID:26031036

  17. 30 CFR 75.222 - Roof control plan-approval criteria.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Roof control plan-approval criteria. 75.222 Section 75.222 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Roof Support § 75.222 Roof...

  18. 30 CFR 75.222 - Roof control plan-approval criteria.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 1 2014-07-01 2014-07-01 false Roof control plan-approval criteria. 75.222 Section 75.222 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Roof Support § 75.222 Roof...

  19. 30 CFR 75.222 - Roof control plan-approval criteria.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 1 2012-07-01 2012-07-01 false Roof control plan-approval criteria. 75.222 Section 75.222 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Roof Support § 75.222 Roof...

  20. 30 CFR 75.222 - Roof control plan-approval criteria.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 1 2013-07-01 2013-07-01 false Roof control plan-approval criteria. 75.222 Section 75.222 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Roof Support § 75.222 Roof...

  1. 30 CFR 75.222 - Roof control plan-approval criteria.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 1 2011-07-01 2011-07-01 false Roof control plan-approval criteria. 75.222 Section 75.222 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Roof Support § 75.222 Roof...

  2. Magnetic criteria of aromaticity.

    PubMed

    Gershoni-Poranne, Renana; Stanger, Amnon

    2015-09-21

    This review describes the current state of magnetic criteria of aromaticity. The introduction contains the fundamentals of ring currents in aromatic and antiaromatic systems, followed by a brief description of experimental and computational tools: NMR, diamagnetic susceptibility exaltation, current density analyses (CDA) and nucleus independent chemical shifts (NICS). This is followed by more comprehensive chapters: NMR - focusing on the work of R. Mitchell - NICS and CDA - describing the progress and development of the methods to their current state and presenting some examples of representative work. PMID:26035305

  3. Criteria for software modularization

    NASA Technical Reports Server (NTRS)

    Card, David N.; Page, Gerald T.; Mcgarry, Frank E.

    1985-01-01

    A central issue in programming practice involves determining the appropriate size and information content of a software module. This study attempted to determine the effectiveness of two widely used criteria for software modularization, strength and size, in reducing fault rate and development cost. Data from 453 FORTRAN modules developed by professional programmers were analyzed. The results indicated that module strength is a good criterion with respect to fault rate, whereas arbitrary module size limitations inhibit programmer productivity. This analysis is a first step toward defining empirically based standards for software modularization.

  4. RADIATION PROTECTION SYSTEM INSTALLATION FOR THE ACCELERATOR PRODUCTION OF TRITIUM/LOW ENERGY DEMONSTRATION ACCELERATOR PROJECT (APT/LEDA)

    SciTech Connect

    J. WILMARTH; M. SMITH; T. TOMEI

    1999-07-01

    The APT/LEDA personnel radiation protection system installation was accomplished using a flexible, modular proven system which satisfied regulatory orders, project design criteria, operational modes, and facility requirements. The goal of providing exclusion and safe access of personnel to areas where prompt radiation in the LEDA facility is produced was achieved with the installation of a DOE-approved Personnel Access Control System (PACS). To satisfy the facility configuration design, the PACS, a major component of the overall radiation safety system, conveniently provided five independent areas of personnel access control. Because of its flexibility and adaptability the Los Alamos Neutron Science Center (LANSCE) designed Radiation Security System (RSS) was efficiently configured to provide the desired operational modes and satisfy the APT/LEDA project design criteria. The Backbone Beam Enable (BBE) system based on the LANSCE RSS provided the accelerator beam control functions with redundant, hardwired, tamper-resistant hardware. The installation was accomplished using modular components.

  5. Performance-based waste acceptance criteria preliminary baseline assumptions

    SciTech Connect

    Not Available

    1994-10-24

    The Department of Energy`s (DOE`s) strategy for the management of transuranic (TRU) and TRU mixed wastes has focused on the development of the Waste Isolation Pilot Plant (WIPP). The WIPP repository is designated to receive DOE defense wastes that meet the established criteria for acceptance. As a national strategy [DOE, 1993], DOE does not intend to treat candidate wastes unless treatment or processing are necessary to meet the safety, health, and regulatory criteria for transport and disposal at WIPP. The WIPP WAC has evolved over the past 10 years to include criteria and requirements in support of the Waste Characterization program and other related compliance programs. In aggregate, the final health, safety and regulatory criteria for the waste will be documented in the Disposal WAC. This document serves two purposes. First, it familiarizes regulators and stakeholders with the concept of performance based waste acceptance criteria as an augmentation within a final Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria. Second, the document preliminarily identifies certain waste characteristics that appear important to the performance assessment process for WIPP; therefore, these could become component characteristics in the Performance Based Waste Acceptance Criteria (PBWAC). Identification of the final PBWAC will be accomplished through iterative runs of the System Prioritization Method (SPM). These iterations will serve to more clearly isolate and identify those waste characteristics that directly and predominately impact on the performance assessment.

  6. HSE's safety assessment principles for criticality safety.

    PubMed

    Simister, D N; Finnerty, M D; Warburton, S J; Thomas, E A; Macphail, M R

    2008-06-01

    The Health and Safety Executive (HSE) published its revised Safety Assessment Principles for Nuclear Facilities (SAPs) in December 2006. The SAPs are primarily intended for use by HSE's inspectors when judging the adequacy of safety cases for nuclear facilities. The revised SAPs relate to all aspects of safety in nuclear facilities including the technical discipline of criticality safety. The purpose of this paper is to set out for the benefit of a wider audience some of the thinking behind the final published words and to provide an insight into the development of UK regulatory guidance. The paper notes that it is HSE's intention that the Safety Assessment Principles should be viewed as a reflection of good practice in the context of interpreting primary legislation such as the requirements under site licence conditions for arrangements for producing an adequate safety case and for producing a suitable and sufficient risk assessment under the Ionising Radiations Regulations 1999 (SI1999/3232 www.opsi.gov.uk/si/si1999/uksi_19993232_en.pdf). PMID:18495990

  7. Performance objectives and criteria for conducting DOE environmental audits

    SciTech Connect

    1994-01-01

    This document contains the Performance Objectives and Criteria (POC) that have been developed for environmental audits and assessments conducted by the Office of the Assistant Secretary for Environment, Safety and Health. The Environmental POC can serve multiple purposes. Primarily, they are to serve as guidelines for the technical specialists conducted the audits and assessments, and for the team management. The POC can also serve as supporting documents for training of technical discipline specialists and Team Leaders and as bases for DOE programs and field offices and contractors conducting audit or assessment activities or improving environmental protection programs. It must be recognized that not all of the POC will necessarily apply to all DOE facilities. The users of this document must rely upon their knowledge of the facility and their professional judgment, or the judgment of qualified environmental professionals to determine the applicability of each POC. The POC cover eleven technical disciplines: air; surface water and drinking water quality; groundwater; waste management; toxic and chemical materials; radiation; quality assurance; inactive waste sites and releases; ecological and cultural resources; the National Environmental Policy Act (NEPA); and environmental management systems.

  8. Annual report on the administration of the Radiation Control for health and Safety Act of 1968, Public Law 90-602, April 1, 1991. Rept. for Jan-Dec 90

    SciTech Connect

    Not Available

    1991-04-01

    The Secretary of Health and Human Services is required by Subpart 3, Part F of Title III of the Public Health Service Act; 42 USC 263b et seq. (Public Law 90-602) to submit an annual report to the President for transmittal to the Congress on or before April 1 on the administration of the Radiation Control for Health and Safety Act. The detailed information required in the report is outlined in Section 360D of the Public Health Service Act. The Food and Drug Administration, through its Center for Devices and Radiological Health, is responsible for the day-to-day administration of the Radiation Control for Health and Safety Act of 1968. The report provides a summary of the operations of the Center in carrying out that responsibility for calendar year 1990. In reviewing the operations of the Center for Devices and Radiological Health as reported in the document, it should be kept in mind that the day-to-day administration of the Act is only part of the Center's function. Other responsibilities include the administration and enforcement of the 1976 Medical Device Amendments to the Federal Food, Drug, and Cosmetic Act (not covered in the report). Manufacturers of electronic products are required by 21 CFR 1002.20 to report accidental radiation occurrences to the Center for Devices and Radiological Health. The Center no longer maintains a Radiation Incidents Registry, since accidental radiation occurrences are reported through the Device Experience Network (DEN) and through the requirements of the Medical Device Reporting (MDR) Regulations.

  9. Quartic Rotation Criteria and Algorithms.

    ERIC Educational Resources Information Center

    Clarkson, Douglas B.; Jennrich, Robert I.

    1988-01-01

    Most of the current analytic rotation criteria for simple structure in factor analysis are summarized and identified as members of a general symmetric family of quartic criteria. A unified development of algorithms for orthogonal and direct oblique rotation using arbitrary criteria from this family is presented. (Author/TJH)

  10. Summertime Safety

    MedlinePlus

    ... Violence & Safety Life Stages & Populations Travelers' Health Workplace Safety & Health Features Media Sign up for Features Get Email Updates ... Submit What's this? Submit Button Past Emails CDC Features Summertime Safety Recommend on Facebook Tweet Share Compartir The feature ...

  11. Drug Safety

    MedlinePlus

    ... over-the-counter drug. The FDA evaluates the safety of a drug by looking at Side effects ... clinical trials The FDA also monitors a drug's safety after approval. For you, drug safety means buying ...

  12. Safety Education.

    ERIC Educational Resources Information Center

    Daniels, James H.; And Others

    1980-01-01

    Five articles in this issue focus on safety education in agricultural laboratories. Topics discussed include teacher liability; elements of a safety instruction program; state and federal safety standards; ground fault current protection; and eye protection requirements and equipment. (SK)

  13. Quasi-Static Probabilistic Structural Analyses Process and Criteria

    NASA Technical Reports Server (NTRS)

    Goldberg, B.; Verderaime, V.

    1999-01-01

    Current deterministic structural methods are easily applied to substructures and components, and analysts have built great design insights and confidence in them over the years. However, deterministic methods cannot support systems risk analyses, and it was recently reported that deterministic treatment of statistical data is inconsistent with error propagation laws that can result in unevenly conservative structural predictions. Assuming non-nal distributions and using statistical data formats throughout prevailing stress deterministic processes lead to a safety factor in statistical format, which integrated into the safety index, provides a safety factor and first order reliability relationship. The embedded safety factor in the safety index expression allows a historically based risk to be determined and verified over a variety of quasi-static metallic substructures consistent with the traditional safety factor methods and NASA Std. 5001 criteria.

  14. Infectious waste management and laboratory design criteria.

    PubMed

    Zaki, A N; Campbell, J R

    1997-11-01

    Infectious waste management and laboratory design criteria are provided to help in recognizing what information needs to be included in an individual program and to develop an infectious waste management plan. Relevant engineering aspects of a containment laboratory are described in detail, and suggested equipment and operating procedures for collection, sterilization, and disposal of solid and liquid waste are discussed. The need for public awareness regarding infectious waste is discussed, including liability considerations associated with improper disposal. This study shows how proper management of infectious waste results in lower disposal cost, lower operating costs, reduction in liabilities, increased worker safety, and a cleaner environment. PMID:9373926

  15. 49 CFR 193.2511 - Personnel safety.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY LIQUEFIED NATURAL GAS FACILITIES... building or yard, where they could be harmed by thermal radiation from a burning pool of impounded...

  16. 49 CFR 193.2511 - Personnel safety.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY LIQUEFIED NATURAL GAS FACILITIES... building or yard, where they could be harmed by thermal radiation from a burning pool of impounded...

  17. Use of E-beam radiation to eliminate Listeria monocytogenes from surface mould cheese.

    PubMed

    Velasco, Raquel; Ordóñez, Juan A; Cambero, M Isabel; Cabeza, M Concepción

    2015-03-01

    Camembert and Brie soft cheese varieties were subjected to E-beam irradiation as a sanitation treatment. The effects of treatments on microbiota and selected physicochemical properties were also studied. The absorbed doses required to meet the food safety objective (FSO) according to EU and USDA criteria for Listeria monocytogenes were 1.27 and 2.59 kGy, respectively. The bacterial load, mainly lactic acid bacteria, was reduced by the treatment but injured cells were recovered during storage at 14°C. The radiation treatment gave rise to negligible changes in the pH and water activity at doses required to achieve microbial safety. PMID:26415665

  18. Alternative food safety intervention technologies

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Alternative nonthermal and thermal food safety interventions are gaining acceptance by the food processing industry and consumers. These technologies include high pressure processing, ultraviolet and pulsed light, ionizing radiation, pulsed and radiofrequency electric fields, cold atmospheric plasm...

  19. Universal Steering Criteria

    NASA Astrophysics Data System (ADS)

    Zhu, Huangjun; Hayashi, Masahito; Chen, Lin

    2016-02-01

    We propose a general framework for constructing universal steering criteria that are applicable to arbitrary bipartite states and measurement settings of the steering party. The same framework is also useful for studying the joint measurement problem. Based on the data-processing inequality for an extended Rényi relative entropy, we then introduce a family of steering inequalities, which detect steering much more efficiently than those inequalities known before. As illustrations, we show unbounded violation of a steering inequality for assemblages constructed from mutually unbiased bases and establish an interesting connection between maximally steerable assemblages and complete sets of mutually unbiased bases. We also provide a single steering inequality that can detect all bipartite pure states of full Schmidt rank. In the course of study, we generalize a number of results intimately connected to data-processing inequalities, which are of independent interest.

  20. Universal Steering Criteria.

    PubMed

    Zhu, Huangjun; Hayashi, Masahito; Chen, Lin

    2016-02-19

    We propose a general framework for constructing universal steering criteria that are applicable to arbitrary bipartite states and measurement settings of the steering party. The same framework is also useful for studying the joint measurement problem. Based on the data-processing inequality for an extended Rényi relative entropy, we then introduce a family of steering inequalities, which detect steering much more efficiently than those inequalities known before. As illustrations, we show unbounded violation of a steering inequality for assemblages constructed from mutually unbiased bases and establish an interesting connection between maximally steerable assemblages and complete sets of mutually unbiased bases. We also provide a single steering inequality that can detect all bipartite pure states of full Schmidt rank. In the course of study, we generalize a number of results intimately connected to data-processing inequalities, which are of independent interest. PMID:26943513

  1. UO3 deactivation end point criteria

    SciTech Connect

    Stefanski, L.D.

    1994-10-01

    The UO{sub 3} Deactivation End Point Criteria are necessary to facilitate the transfer of the UO{sub 3} Facility from the Office of Facility Transition and Management (EM-60) to the office of Environmental Restoration (EM-40). The criteria were derived from a logical process for determining end points for the systems and spaces at the UO{sub 3}, Facility based on the objectives, tasks, and expected future uses pertinent to that system or space. Furthermore, the established criteria meets the intent and supports the draft guidance for acceptance criteria prepared by EM-40, {open_quotes}U.S. Department of Energy office of Environmental Restoration (EM-40) Decontamination and Decommissioning Guidance Document (Draft).{close_quotes} For the UO{sub 3} Facility, the overall objective of deactivation is to achieve a safe, stable and environmentally sound condition, suitable for an extended period, as quickly and economically as possible. Once deactivated, the facility is kept in its stable condition by means of a methodical surveillance and maintenance (S&M) program, pending ultimate decontamination and decommissioning (D&D). Deactivation work involves a range of tasks, such as removal of hazardous material, elimination or shielding of radiation fields, partial decontamination to permit access for inspection, installation of monitors and alarms, etc. it is important that the end point of each of these tasks be established clearly and in advance, for the following reasons: (1) End points must be such that the central element of the deactivation objective - to achieve stability - is unquestionably achieved. (2) Much of the deactivation work involves worker exposure to radiation or dangerous materials. This can be minimized by avoiding unnecessary work. (3) Each task is, in effect, competing for resources with other deactivation tasks and other facilities. By assuring that each task is appropriately bounded, DOE`s overall resources can be used most fully and effectively.

  2. Evaluation Criteria for Solid Waste Processing Research and Technology Development

    NASA Technical Reports Server (NTRS)

    Levri, Julie A.; Hogan, J. A.; Alazraki, M. P.

    2001-01-01

    A preliminary list of criteria is proposed for evaluation of solid waste processing technologies for research and technology development (R&TD) in the Advanced Life Support (ALS) Program. Completion of the proposed list by current and prospective ALS technology developers, with regard to specific missions of interest, may enable identification of appropriate technologies (or lack thereof) and guide future development efforts for the ALS Program solid waste processing area. An attempt is made to include criteria that capture information about the technology of interest as well as its system-wide impacts. Some of the criteria in the list are mission-independent, while the majority are mission-specific. In order for technology developers to respond to mission-specific criteria, critical information must be available on the quantity, composition and state of the waste stream, the wast processing requirements, as well as top-level mission scenario information (e.g. safety, resource recovery, planetary protection issues, and ESM equivalencies). The technology readiness level (TRL) determines the degree to which a technology developer is able to accurately report on the list of criteria. Thus, a criteria-specific minimum TRL for mandatory reporting has been identified for each criterion in the list. Although this list has been developed to define criteria that are needed to direct funding of solid waste processing technologies, this list processes significant overlap in criteria required for technology selection for inclusion in specific tests or missions. Additionally, this approach to technology evaluation may be adapted to other ALS subsystems.

  3. 47 CFR 90.313 - Frequency loading criteria.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 47 Telecommunication 5 2011-10-01 2011-10-01 false Frequency loading criteria. 90.313 Section 90.313 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES PRIVATE LAND MOBILE RADIO SERVICES Authorization in the Band 470-512 MHz (UHF-TV Sharing) §...

  4. 47 CFR 90.313 - Frequency loading criteria.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 47 Telecommunication 5 2013-10-01 2013-10-01 false Frequency loading criteria. 90.313 Section 90.313 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES PRIVATE LAND MOBILE RADIO SERVICES Authorization in the Band 470-512 MHz (UHF-TV Sharing) §...

  5. 47 CFR 90.313 - Frequency loading criteria.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 47 Telecommunication 5 2014-10-01 2014-10-01 false Frequency loading criteria. 90.313 Section 90.313 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES PRIVATE LAND MOBILE RADIO SERVICES Authorization in the Band 470-512 MHz (UHF-TV Sharing) §...

  6. 47 CFR 90.313 - Frequency loading criteria.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 47 Telecommunication 5 2012-10-01 2012-10-01 false Frequency loading criteria. 90.313 Section 90.313 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES PRIVATE LAND MOBILE RADIO SERVICES Authorization in the Band 470-512 MHz (UHF-TV Sharing) §...

  7. 47 CFR 90.313 - Frequency loading criteria.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Frequency loading criteria. 90.313 Section 90.313 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES PRIVATE LAND MOBILE RADIO SERVICES Authorization in the Band 470-512 MHz (UHF-TV Sharing) §...

  8. 9 CFR 439.10 - Criteria for obtaining accreditation.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 9 Animals and Animal Products 2 2014-01-01 2014-01-01 false Criteria for obtaining accreditation. 439.10 Section 439.10 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE REGULATORY REQUIREMENTS UNDER THE FEDERAL MEAT INSPECTION ACT AND THE POULTRY PRODUCTS INSPECTION ACT ACCREDITATION OF...

  9. 16 CFR 1610.7 - Test sequence and classification criteria.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    .... 1610.7 Section 1610.7 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION FLAMMABLE FABRICS ACT... classification. (b) Test sequence and classification criteria. (1) Step 1, Plain Surface Textile Fabrics in the... burning direction of the fabric. (ii) Prepare and test five specimens from the fastest burning...

  10. 16 CFR 1610.7 - Test sequence and classification criteria.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    .... 1610.7 Section 1610.7 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION FLAMMABLE FABRICS ACT... classification. (b) Test sequence and classification criteria. (1) Step 1, Plain Surface Textile Fabrics in the... burning direction of the fabric. (ii) Prepare and test five specimens from the fastest burning...

  11. 9 CFR 439.20 - Criteria for maintaining accreditation.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Criteria for maintaining accreditation. 439.20 Section 439.20 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE REGULATORY REQUIREMENTS UNDER THE FEDERAL MEAT INSPECTION ACT AND THE POULTRY PRODUCTS INSPECTION ACT ACCREDITATION OF...

  12. 10 CFR 830.122 - Quality assurance criteria.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 4 2013-01-01 2013-01-01 false Quality assurance criteria. 830.122 Section 830.122 Energy DEPARTMENT OF ENERGY NUCLEAR SAFETY MANAGEMENT Quality Assurance Requirements § 830.122 Quality assurance...) Criterion 1—Management/Program. (1) Establish an organizational structure, functional...

  13. 10 CFR 830.122 - Quality assurance criteria.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 4 2010-01-01 2010-01-01 false Quality assurance criteria. 830.122 Section 830.122 Energy DEPARTMENT OF ENERGY NUCLEAR SAFETY MANAGEMENT Quality Assurance Requirements § 830.122 Quality assurance...) Criterion 3—Management/Quality Improvement. (1) Establish and implement processes to detect and...

  14. 20 CFR 410.422 - Determining total disability: General criteria.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 20 Employees' Benefits 2 2011-04-01 2011-04-01 false Determining total disability: General... HEALTH AND SAFETY ACT OF 1969, TITLE IV-BLACK LUNG BENEFITS (1969- ) Total Disability or Death Due to Pneumoconiosis § 410.422 Determining total disability: General criteria. (a) A determination of total...

  15. 10 CFR 100.21 - Non-seismic siting criteria.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... access, shorter transmission line requirements, or less environmental impact on undeveloped areas, wetlands or endangered species, etc. Some of these factors are included in, or impact, the other criteria... populated center but not in an area of low density, consideration will be given to safety,...

  16. 20 CFR 410.422 - Determining total disability: General criteria.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 20 Employees' Benefits 2 2010-04-01 2010-04-01 false Determining total disability: General... HEALTH AND SAFETY ACT OF 1969, TITLE IV-BLACK LUNG BENEFITS (1969- ) Total Disability or Death Due to Pneumoconiosis § 410.422 Determining total disability: General criteria. (a) A determination of total...

  17. Annual report on the administration of the Radiation Control for Health and Safety Act of 1968, Public Law 90-602, April 1, 1990. Report for January-December 1989

    SciTech Connect

    Not Available

    1990-04-01

    The Food and Drug Administration, through its Center for Devices and Radiological Health, is responsible for the day-to-day administration of the Radiation Control for Health and Safety Act of 1968. The report provides a summary of the operations of the Center in carrying out that responsibility for calendar year 1989. In reviewing the operations of the Center for Devices and Radiological Health as reported in the document, it should be kept in mind that the day-to-day administration of the Act is only part of the Center's function. Other responsibilities include the administration and enforcement of the 1976 Medical Device Amendments to the Federal Food, Drug, and Cosmetic Act (not covered in the report). Manufacturers of electronic products are required by 21 CFR 1003.20 to report accidental radiation occurrences to the Center for Devices and Radiological Health. The Center no longer maintains a Radiation Incidents Registry, since accidental radiation occurrences are reported through the Device Experience Network (DEN) and through the requirements of the Medical Device Reporting (MDR) regulations.

  18. 30 CFR 250.1917 - What criteria for pre-startup review must be in my SEMS program?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 2 2014-07-01 2014-07-01 false What criteria for pre-startup review must be in... SHELF Safety and Environmental Management Systems (SEMS) § 250.1917 What criteria for pre-startup review...-startup safety and environmental review for new and significantly modified facilities that are subject...

  19. 30 CFR 250.1917 - What criteria for pre-startup review must be in my SEMS program?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 2 2013-07-01 2013-07-01 false What criteria for pre-startup review must be in... SHELF Safety and Environmental Management Systems (SEMS) § 250.1917 What criteria for pre-startup review...-startup safety and environmental review for new and significantly modified facilities that are subject...

  20. 30 CFR 250.1917 - What criteria for pre-startup review must be in my SEMS program?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 2 2012-07-01 2012-07-01 false What criteria for pre-startup review must be in... SHELF Safety and Environmental Management Systems (SEMS) § 250.1917 What criteria for pre-startup review...-startup safety and environmental review for new and significantly modified facilities that are subject...