NSSS supplier's response to differing safety criteria

Energy Technology Data Exchange (ETDEWEB)

Cremades, J; Filkin, R; Franke, T [Westinghouse Electric Nuclear Energy Systems Europe (WENESE), Brussels (Belgium)

1980-11-01

The limited progress achieved to date in harmonizing national criteria has led to the development of designs which include the most common national requirements. Progress towards harmonization of safety criteria can be accelerated by expanding the IAEA leadership and co-ordination activities, and implementing an integrated approach to criteria development. National and International safety criteria are examined.

Radiation Safety Professional Certification Process in a Multi-Disciplinary Association

International Nuclear Information System (INIS)

Wilson, G.; Jones, P.; Ilson, R.

2004-01-01

There is no one set of criteria that defines the radiation safety professional in Canada. The many varied positions, from university and medical to industry and mining, define different qualifications to manage radiation safety programs. The national regulatory body has to assess many different qualifications when determining if an individual is acceptable to be approved for the role of radiation safety officer under any given licence. Some professional organizations specify education requirements and work experience as a prerequisite to certification. The education component specifies a degree of some type but does not identify specific courses or competencies within that degree. This could result in individuals with varying levels of radiation safety experience and training. The Canadian Radiation Protection Association (CRPA), responding to a need identified by the membership of the association, has initiated a process where the varying levels of knowledge of radiation safety can be addressed for radiation safety professionals. By identifying a core level set of radiation safety competencies, the basic level of radiation safety officer for smaller organizations can be met. By adding specialty areas, education can be pursued to define the more complex needs of larger organizations. This competency based process meets the needs of licensees who do not require highly trained health physicists in order to meet the licensing requirements and at the same time provides a stepping stone for those who wish to pursue a more specialized health physics option. (Author) 8 refs

Radiation safety

International Nuclear Information System (INIS)

Van Riessen, A.

2002-01-01

Full text: Experience has shown that modem, fully enclosed, XRF and XRD units are generally safe. This experience may lead to complacency and ultimately a lowering of standards which may lead to accidents. Maintaining awareness of radiation safety issues is thus an important role for all radiation safety officers. With the ongoing progress in technology, a greater number of radiation workers are more likely to use a range of instruments/techniques - eg portable XRF, neutron beam analysis, and synchrotron radiation analysis. The source for each of these types of analyses is different and necessitates an understanding of the associated dangers as well as use of specific radiation badges. The trend of 'suitcase science' is resulting in scientists receiving doses from a range of instruments and facilities with no coordinated approach to obtain an integrated dose reading for an individual. This aspect of radiation safety needs urgent attention. Within Australia a divide is springing up between those who work on Commonwealth property and those who work on State property. For example a university staff member may operate irradiating equipment on a University campus and then go to a CSIRO laboratory to operate similar equipment. While at the University State regulations apply and while at CSIRO Commonwealth regulations apply. Does this individual require two badges? Is there a need to obtain two licences? The application of two sets of regulations causes unnecessary confusion and increases the workload of radiation safety officers. Radiation safety officers need to introduce risk management strategies to ensure that both existing and new procedures result in risk minimisation. A component of this strategy includes ongoing education and revising of regulations. AXAA may choose to contribute to both of these activities as a service to its members as well as raising the level of radiation safety for all radiation workers. Copyright (2002) Australian X-ray Analytical

Radiation safety

International Nuclear Information System (INIS)

1996-04-01

Most of the ionizing radiation that people are exposed to in day-to-day activities comes from natural, rather than manmade, sources. The health effects of radiation - both natural and artificial - are relatively well understood and can be effectively minimized through careful safety measures and practices. The IAEA, together with other international and expert organizations, is helping to promote and institute Basic Safety Standards on an international basis to ensure that radiation sources and radioactive materials are managed for both maximum safety and human benefit

Safety instruction for execution tasks involving ionizing radiations

International Nuclear Information System (INIS)

Fonseca, G.

1985-01-01

Basic directives are presented allow operations with ionizing radiations in industrial areas with high levels of safety. Contractual, technical, operational and administrative criteria are established for the safe performance of x-rays and gamographies and the use of fixed radiation based equipment (indicators of level, density, flow, etc) as well as precautions to be taken during project, procurement, transportation, assembly and maintenance of such equipment. Finally procedures are suggested for emergencies involving radioactive sources. (author)

A NSSS supplier's response to differing safety criteria

International Nuclear Information System (INIS)

Cremades, J.; Filkin, R.; Franke, Th.

1980-01-01

The limited progress achieved to date in harmonizing national criteria has led to the development of designs which include the most common national requirements. Progress towards harmonization of safety criteria can be accelerated by expanding the IAEA leadership and co-ordination activities, and implementing an integrated approach to criteria development. National and International safety criteria are examined. (author)

Squale: evaluation criteria of functioning safety

International Nuclear Information System (INIS)

Deswarte, Y.; Kaaniche, M.; Benoit, P.

1998-05-01

The SQUALE (security, safety and quality evaluation for dependable systems) project is part of the ACTS (advanced communications, technologies and services) European program. Its aim is to develop confidence evaluation criteria to test the functioning safety of systems. All industrial sectors that use critical applications (nuclear, railway, aerospace..) are concerned. SQUALE evaluation criteria differ from the classical evaluation methods: they are independent of the application domains and industrial sectors, they take into account the overall functioning safety attributes, and they can progressively change according to the level of severity required. In order to validate the approach and to refine the criteria, a first experiment is in progress with the METEOR automatic underground railway and another will be carried out on a telecommunication system developed by Bouygues company. (J.S.)

Radiation safety and quality control assurance in X-ray diagnostics 1998

International Nuclear Information System (INIS)

Servomaa, A.

1998-03-01

The report is based on a seminar course of lectures 'Radiation safety and quality assurance in X-ray diagnostics 1998' organized by the Radiation and Nuclear Safety Authority (STUK) in Finland. The lectures included actual information on X-ray examinations: methods of quality assurance, methods of measuring and calculating patient doses, examination frequencies, patient doses, occupational doses, and radiation risks. Paediatric X-ray examinations and interventional procedures were the most specific topics. The new Council Directive 97/43/Euratom on medical exposure, and the European Guidelines on quality criteria for diagnostic radiographic images, were discussed in several lectures. Lectures on general radiation threats and preparedness, examples of radiation accidents, and emergency preparedness in hospitals were also included. (editor)

Criteria for safety-related operator actions

International Nuclear Information System (INIS)

Gray, L.H.; Haas, P.M.

1983-01-01

The Safety-Related Operator Actions (SROA) Program was designed to provide information and data for use by NRC in assessing the performance of nuclear power plant (NPP) control room operators in responding to abnormal/emergency events. The primary effort involved collection and assessment of data from simulator training exercises and from historical records of abnormal/emergency events that have occurred in operating plants (field data). These data can be used to develop criteria for acceptability of the use of manual operator action for safety-related functions. Development of criteria for safety-related operator actions are considered

Safety and reliability criteria

International Nuclear Information System (INIS)

O'Neil, R.

1978-01-01

Nuclear power plants and, in particular, reactor pressure boundary components have unique reliability requirements, in that usually no significant redundancy is possible, and a single failure can give rise to possible widespread core damage and fission product release. Reliability may be required for availability or safety reasons, but in the case of the pressure boundary and certain other systems safety may dominate. Possible Safety and Reliability (S and R) criteria are proposed which would produce acceptable reactor design. Without some S and R requirement the designer has no way of knowing how far he must go in analysing his system or component, or whether his proposed solution is likely to gain acceptance. The paper shows how reliability targets for given components and systems can be individually considered against the derived S and R criteria at the design and construction stage. Since in the case of nuclear pressure boundary components there is often very little direct experience on which to base reliability studies, relevant non-nuclear experience is examined. (author)

TAPS safety evaluation criteria for reload fueling

International Nuclear Information System (INIS)

Mahendra Nath; Veeraraghavan, N.

1976-01-01

To improve operating performance of Tarapur reactors, several proposals are under consideration such as core expansion, change-over to an improved fuel design with lower heat rating, extension of fuel cycle lengths etc., which have a bearing on overall plant operating characteristics and reactor safety. For evaluating safety implications of the various proposals, it is necessary to formulate safety evaluation criteria for reload fuelling. Salient features of these criteria are discussed. (author)

Guide to the declaration procedure and coding system for criteria concerning significant events related to safety, radiation protection or the environment, applicable to basic nuclear installations and the transport of radioactive materials

International Nuclear Information System (INIS)

Lacoste, Andre-Claude

2005-01-01

This guide notably contains various forms associated with the declaration of significant events, and explanations to fill them in: significant event declaration form for a basic nuclear installation, significant event declaration form for radioactive material transport, significant event report for a basic nuclear installation, significant event report for radioactive material transport, declaration criteria for significant events related to the safety of non-PWR basic nuclear installations, declaration criteria for significant events related to PWR safety, significant events declared further to events resulting in group 1 unavailability and non-compliance with technical operating specifications, declaration criteria for significant events concerning radiation protection for basic nuclear installations, declaration criteria for significant events concerning environmental protection, applicable to basic nuclear installations, and declaration criteria for significant events concerning radioactive material transport

Criteria for Use in Preparedness and Response for a Nuclear or Radiological Emergency. General Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2013-01-01

This Safety Guide presents a coherent set of generic criteria (expressed numerically in terms of radiation dose) that form a basis for developing the operational levels needed for decision making concerning protective and response actions. The set of generic criteria addresses the requirements established in IAEA Safety Standards Series No. GS-R-2 for emergency preparedness and response, including lessons learned from responses to past emergencies, and provides an internally consistent foundation for the application of radiation protection. The publication also proposes a basis for a plain language explanation of the criteria for the public and for public officials. Contents: 1. Introduction; 2. Basic considerations; 3. Framework for emergency response criteria; 4. Guidance values for emergency workers; 5. Operational criteria; Appendix I: Dose concepts and dosimetric quantities; Appendix II: Examples of default oils for deposition, individual monitoring and contamination of food, milk and water; Appendix III: Development of EALs and example EALs for light water reactors; Appendix IV: Observables at the scene of a nuclear or radiological emergency

Criteria for Use in Preparedness and Response for a Nuclear or Radiological Emergency. General Safety Guide (Russian Ed.)

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide presents a coherent set of generic criteria (expressed numerically in terms of radiation dose) that form a basis for developing the operational levels needed for decision making concerning protective and response actions. The set of generic criteria addresses the requirements established in IAEA Safety Standards Series No. GS-R-2 for emergency preparedness and response, including lessons learned from responses to past emergencies, and provides an internally consistent foundation for the application of radiation protection. The publication also proposes a basis for a plain language explanation of the criteria for the public and for public officials. Contents: 1. Introduction; 2. Basic considerations; 3. Framework for emergency response criteria; 4. Guidance values for emergency workers; 5. Operational criteria; Appendix I: Dose concepts and dosimetric quantities; Appendix II: Examples of default oils for deposition, individual monitoring and contamination of food, milk and water; Appendix III: Development of EALs and example EALs for light water reactors; Appendix IV: Observables at the scene of a nuclear or radiological emergency.

Criteria for Use in Preparedness and Response for a Nuclear or Radiological Emergency. General Safety Guide (Arabic Edition)

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-11-01

This Safety Guide presents a coherent set of generic criteria (expressed numerically in terms of radiation dose) that form a basis for developing the operational levels needed for decision making concerning protective and response actions. The set of generic criteria addresses the requirements established in IAEA Safety Standards Series No. GS-R-2 for emergency preparedness and response, including lessons learned from responses to past emergencies, and provides an internally consistent foundation for the application of principles of radiation protection. The publication also provides a basis for a plain language explanation of the criteria for the public and for public officials. Contents: 1. Introduction; 2. Basic considerations; 3. Framework for emergency response criteria; 4. Guidance values for emergency workers; 5. Operational criteria; Appendix I: Dose concepts and dosimetric quantities; Appendix II: Examples of default OILs for deposition, individual contamination and contamination of food, milk and water; Appendix III: Development of EALs and example EALs for light water reactors; Appendix IV: Observables on the scene of a radiological emergency.

Occupational radiation protection. Safety guide

International Nuclear Information System (INIS)

2002-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. In 1996, the Agency published Safety Fundamentals on Radiation Protection and the Safety of Radiation Sources (IAEA Safety Series No. 120) and International Basic Safety Standards for Protection against Ionizing, Radiation and for the Safety of Radiation Sources (IAEA Safety Series No. 115), both of which were jointly sponsored by the Food and Agriculture Organization of the United Nations, the IAEA, the International Labour Organisation, the OECD Nuclear Energy Agency, the Pan American Health Organization and the World Health Organization. These publications set out, respectively, the objectives and principles for radiation safety and the requirements to be met to apply the principles and to achieve the objectives. The establishment of safety requirements and guidance on occupational radiation protection is a major component of the support for radiation safety provided by the IAEA to its Member States. The objective of the IAEA's occupational protection programme is to promote an internationally harmonized approach to the optimization of occupational radiation protection, through the development and application of guidelines for restricting radiation exposures and applying current radiation protection techniques in the workplace. Guidance on meeting the requirements of the Basic Safety Standards for occupational protection is provided in three interrelated Safety Guides, one giving general guidance on the development of occupational radiation protection programmes and two giving more detailed guidance on the monitoring and assessment of workers' exposure due to external radiation sources and from intakes of radionuclides, respectively. These Safety

Occupational radiation protection. Safety guide

International Nuclear Information System (INIS)

2006-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. In 1996, the Agency published Safety Fundamentals on Radiation Protection and the Safety of Radiation Sources (IAEA Safety Series No. 120) and International Basic Safety Standards for Protection against Ionizing, Radiation and for the Safety of Radiation Sources (IAEA Safety Series No. 115), both of which were jointly sponsored by the Food and Agriculture Organization of the United Nations, the IAEA, the International Labour Organisation, the OECD Nuclear Energy Agency, the Pan American Health Organization and the World Health Organization. These publications set out, respectively, the objectives and principles for radiation safety and the requirements to be met to apply the principles and to achieve the objectives. The establishment of safety requirements and guidance on occupational radiation protection is a major component of the support for radiation safety provided by the IAEA to its Member States. The objective of the IAEA's occupational protection programme is to promote an internationally harmonized approach to the optimization of occupational radiation protection, through the development and application of guidelines for restricting radiation exposures and applying current radiation protection techniques in the workplace. Guidance on meeting the requirements of the Basic Safety Standards for occupational protection is provided in three interrelated Safety Guides, one giving general guidance on the development of occupational radiation protection programmes and two giving more detailed guidance on the monitoring and assessment of workers' exposure due to external radiation sources and from intakes of radionuclides, respectively. These Safety

Occupational radiation protection. Safety guide

International Nuclear Information System (INIS)

1999-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. In 1996, the Agency published Safety Fundamentals on Radiation Protection and the Safety of Radiation Sources (IAEA Safety Series No. 120) and International Basic Safety Standards for Protection against Ionizing, Radiation and for the Safety of Radiation Sources (IAEA Safety Series No. 115), both of which were jointly sponsored by the Food and Agriculture Organization of the United Nations, the IAEA, the International Labour Organisation, the OECD Nuclear Energy Agency, the Pan American Health Organization and the World Health Organization. These publications set out, respectively, the objectives and principles for radiation safety and the requirements to be met to apply the principles and to achieve the objectives. The establishment of safety requirements and guidance on occupational radiation protection is a major component of the support for radiation safety provided by the IAEA to its Member States. The objective of the IAEA's occupational protection programme is to promote an internationally harmonized approach to the optimization of occupational radiation protection, through the development and application of guidelines for restricting radiation exposures and applying current radiation protection techniques in the workplace. Guidance on meeting the requirements of the Basic Safety Standards for occupational protection is provided in three interrelated Safety Guides, one giving general guidance on the development of occupational radiation protection programmes and two giving more detailed guidance on the monitoring and assessment of workers' exposure due to external radiation sources and from intakes of radionuclides, respectively. These Safety

Occupational radiation protection. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. In 1996, the Agency published Safety Fundamentals on Radiation Protection and the Safety of Radiation Sources (IAEA Safety Series No. 120) and International Basic Safety Standards for Protection against Ionizing, Radiation and for the Safety of Radiation Sources (IAEA Safety Series No. 115), both of which were jointly sponsored by the Food and Agriculture Organization of the United Nations, the IAEA, the International Labour Organisation, the OECD Nuclear Energy Agency, the Pan American Health Organization and the World Health Organization. These publications set out, respectively, the objectives and principles for radiation safety and the requirements to be met to apply the principles and to achieve the objectives. The establishment of safety requirements and guidance on occupational radiation protection is a major component of the support for radiation safety provided by the IAEA to its Member States. The objective of the IAEA's occupational protection programme is to promote an internationally harmonized approach to the optimization of occupational radiation protection, through the development and application of guidelines for restricting radiation exposures and applying current radiation protection techniques in the workplace. Guidance on meeting the requirements of the Basic Safety Standards for occupational protection is provided in three interrelated Safety Guides, one giving general guidance on the development of occupational radiation protection programmes and two giving more detailed guidance on the monitoring and assessment of workers' exposure due to external radiation sources and from intakes of radionuclides, respectively. These Safety

Nuclear Fuel Safety Criteria Technical Review - Second edition

International Nuclear Information System (INIS)

Beck, Winfried; Blanpain, Patrick; Fuketa, Toyoshi; Gorzel, Andreas; Hozer, Zoltan; Kamimura, Katsuichiro; Koo, Yang-Hyun; Maertens, Dietmar; Nechaeva, Olga; Petit, Marc; Rehacek, Radomir; Rey-Gayo, Jose Maria; Sairanen, Risto; Sonnenburg, Heinz-Guenther; Valach, Mojmir; Waeckel, Nicolas; Yueh, Ken; Zhang, Jinzhao; Voglewede, John

2012-01-01

Most of the current nuclear fuel safety criteria were established during the 1960's and early 1970's. Although these criteria were validated against experiments with fuel designs available at that time, a number of tests were based on unirradiated fuels. Additional verification was performed as these designs evolved, but mostly with the aim of showing that the new designs adequately complied with existing criteria, and not to establish new limits. In 1996, the OECD Nuclear Energy Agency (NEA) reviewed existing fuel safety criteria, focusing on new fuel and core designs, new cladding materials and industry manufacturing processes. The results were published in the Nuclear Fuel Safety Criteria Technical Review of 2001. The NEA has since re-examined the criteria. A brief description of each criterion and its rationale are presented in this second edition, which will be of interest to both regulators and industry (fuel vendors, utilities)

Laser Safety Inspection Criteria

International Nuclear Information System (INIS)

Barat, K

2005-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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.

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

International Nuclear Information System (INIS)

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

Radiation protection training of radiation safety officers in Finland in 2008

International Nuclear Information System (INIS)

Havukainen, R.; Bly, R.; Markkanen, M.

2009-11-01

The Radiation and Nuclear Safety Authority (STUK) carried out a survey on the radiation protection training of radiation safety officers (RSO) in Finland in 2008. The aim of the survey was to obtain information on the conformity and uniformity of the training provided in different training organisations. A previous survey concerning radiation protection training was carried out in 2003. That survey determined the training needs of radiation users and radiation safety officers as well the radiation protection training included in vocational training and supplementary training. This report presents the execution and results of the survey in 2008. According to the responses, the total amount of RSO training fulfilled the requirements presented in Guide ST 1.8 in the most fields of competence. The emphasis of the RSO training differed between organisations, even for training in the same field of competence. Certain issues in Guide ST 1.8 were dealt quite superficially or even not at all in some training programmes. In some fields of competence, certain matters were entirely left to individual study. No practical training with radiation equipment or sources was included in the RSO training programme of some organisations. Practical training also varied considerably between organisations, even within the same field of competence. The duties in the use of radiation were often considered as practical training with radiation equipment and sources. Practical training from the point of view of a radiation safety officer was brought up in the responses of only one organisation. The number of questions and criteria for passing RSO exams also varied between organisations. Trainers who provided RSO training for the use of radiation in health care sectors had reached a higher vocational training level and received more supplementary training in radiation protection in the previous 5 years than trainers who provided RSO training for the use of radiation in industry, research, and

Radiation protection and the safety of radiation sources

International Nuclear Information System (INIS)

1996-01-01

These Safety Fundamentals cover the protection of human beings against ionizing radiation (gamma and X rays and alpha, beta and other particles that can induce ionization as they interact with biological materials), referred to herein subsequently as radiation, and the safety of sources that produce ionizing radiation. The Fundamentals do not apply to non-ionizing radiation such as microwave, ultraviolet, visible and infrared radiation. They do not apply either to the control of non-radiological aspects of health and safety. They are, however, part of the overall framework of health and safety

Review of fuel safety criteria in France

Energy Technology Data Exchange (ETDEWEB)

Boutin, Sandrine; Graff, Stephanie; Foucher-Taisne, Aude; Dubois, Olivier [Institut de Radioprotection et du Surete Nucleaire, Fontenay-aux-Roses (France)

2018-01-15

Fuel safety criteria for the first barrier, based on state-of-the-art at the time, were first defined in the 1970s and came from the United States, when the French nuclear program was initiated. Since then, there has been continuous progress in knowledge and in collecting experimental results thanks to the experiments carried out by utilities and research institutes, to the operating experience, as well as to the generic R and D programs, which aim notably at improving computation methodologies, especially in Reactivity-Initiated accident and Loss-of-Coolant Accident conditions. In this context, the French utility EDF proposed new fuel safety criteria, or reviewed and completed existing safety demonstration covering the normal operating, incidental and accidental conditions of Pressurised Water Reactors. IRSN assessed EDF's proposals and presented its conclusions to the Advisory Committee for Reactors Safety of the Nuclear Safety Authority in June 2017. This review focused on the relevance of historical limit values or parameters of fuel safety criteria and their adequacy with the state-of-the-art concerning fuel physical phenomena (e.g. Pellet-Cladding Mechanical Interaction in incidental conditions, clad embrittlement due to high temperature oxidation in accidental conditions, clad ballooning and burst during boiling crisis and fuel melting).

Review of fuel safety criteria in France

International Nuclear Information System (INIS)

Boutin, Sandrine; Graff, Stephanie; Foucher-Taisne, Aude; Dubois, Olivier

2018-01-01

Fuel safety criteria for the first barrier, based on state-of-the-art at the time, were first defined in the 1970s and came from the United States, when the French nuclear program was initiated. Since then, there has been continuous progress in knowledge and in collecting experimental results thanks to the experiments carried out by utilities and research institutes, to the operating experience, as well as to the generic R and D programs, which aim notably at improving computation methodologies, especially in Reactivity-Initiated accident and Loss-of-Coolant Accident conditions. In this context, the French utility EDF proposed new fuel safety criteria, or reviewed and completed existing safety demonstration covering the normal operating, incidental and accidental conditions of Pressurised Water Reactors. IRSN assessed EDF's proposals and presented its conclusions to the Advisory Committee for Reactors Safety of the Nuclear Safety Authority in June 2017. This review focused on the relevance of historical limit values or parameters of fuel safety criteria and their adequacy with the state-of-the-art concerning fuel physical phenomena (e.g. Pellet-Cladding Mechanical Interaction in incidental conditions, clad embrittlement due to high temperature oxidation in accidental conditions, clad ballooning and burst during boiling crisis and fuel melting).

Laser Safety Inspection Criteria

International Nuclear Information System (INIS)

Barat, K.

2005-01-01

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

Safety indicators in different time frames for the safety assessment of underground radioactive waste repositories. First report of the INWAC subgroup on principles and criteria for radioactive waste disposal

International Nuclear Information System (INIS)

1994-10-01

Principles and criteria for the disposal of long lived radioactive waste involve issues which go beyond those normally considered in the basic system of radiation protection. Safety criteria based on radiation risk an dose limitation are commonly accepted as the principal basis for judging the acceptability of radioactive waste repositories. However, the long time-scales of interest mean that risks or doses to future individuals cannot be predicted with any certainty as they depend, amongst other things, on assumptions made about the integrity of the waste matrix, the man-made barriers, the geology, the dispersion of groundwater, etc. and future biospheric conditions and human lifestyles. This document discusses various safety indicators and their applicability in the context of the future time-scales which have to be considered in safety assessments of deep geologic repositories. Quantitative assessment are based on numerical estimates of consequences (e.g. risk or dose) and the assessment is made against numerical criteria. Qualitative assessments are based on estimates of hazard potential which are not exact or absolute and the assessment is made against criteria which may not be numerically defined. Examples of such criteria are the convenient reference values provided by levels of radionuclides in the natural environment. Refs, figs and tabs

Promoting safety culture in radiation industry through radiation audit

International Nuclear Information System (INIS)

Noriah, M.A.

2007-01-01

This paper illustrates the Malaysian experience in implementing and promoting effective radiation safety program. Current management practice demands that an organization inculcate culture of safety in preventing radiation hazard. The aforementioned objectives of radiation protection can only be met when it is implemented and evaluated continuously. Commitment from the workforce to treat safety as a priority and the ability to turn a requirement into a practical language is also important to implement radiation safety policy efficiently. Maintaining and improving safety culture is a continuous process. There is a need to establish a program to measure, review and audit health and safety performance against predetermined standards. This program is known as radiation safety audit and is able to reveal where and when action is needed to make improvements to the systems of controls. A structured and proper radiation self-auditing system is seen as the sole requirement to meet the current and future needs in sustainability of radiation safety. As a result safety culture, which has been a vital element on safety in many industries can be improved and promote changes, leading to good safety performance and excellence. (author)

Licensed reactor nuclear safety criteria applicable to DOE reactors

International Nuclear Information System (INIS)

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

Safety Design Criteria of Indian Sodium Cooled Fast Reactors

International Nuclear Information System (INIS)

Pillai, P.; Chellapandi, P.; Chetal, S.C.; Vasudeva Rao, P.R.

2013-01-01

• Important feedback has been gained through the design and safety review of PFBR. • The safety criteria document prepared by AERB and IGCAR would provide important input to prepare the dedicated document for the Sodium cooled Fast Reactors at the national and international level. • A common approach with regard to safety, among countries pursuing fast reactor program, is desirable. • Sharing knowledge and experimental facilities on collaborative basis. • Evolution of strong safety criteria – fundamental to assure safety

Licensed reactor nuclear safety criteria applicable to DOE reactors

International Nuclear Information System (INIS)

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

Radiation protection and safety of radiation sources international basic safety standards

CERN Document Server

International Atomic Energy Agency. Vienna

2014-01-01

The Board of Governors of the IAEA first approved Basic Safety Standards in June 1962; they were published by the IAEA as IAEA Safety Series No. 9. A revised edition was issued in 1967. A third revision was published by the IAEA as the 1982 Edition of IAEA Safety Series No. 9 ; this edition was jointly sponsored by the IAEA, ILO, OECD/NEA and the WHO. The next edition was International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources, published by the IAEA as IAEA Safety Series No. 115 in February 1996, and jointly sponsored by the FAO, IAEA, ILO, OECD/NEA, PAHO and the WHO.

Fuel safety criteria and review by OECD / CSNI task force

International Nuclear Information System (INIS)

Van Doesburg, W.

1999-01-01

Full text of publication follows: with the advent of advanced fuel and core designs, and the implementation of more accurate (best estimate or statistical) design and analysis methods, there is a general feeling that safety margins have been or are being reduced. Historically, fuel safety margins were defined by adding conservatism to the safety limits, which in turn were also fixed in a conservative manner, here, the expression 'conservatism' expresses the fact that bounding or limiting numbers were chosen for model parameters, plant and fuel design data, and fuel operating history values. Unfortunately, as these conservatisms were not quantified (or quantifiable), the amount of safety available or the reduction thereof is difficult to substantiate. For the regulator, it is important to know the margin available with the utilities' request for approval of new fuel or methods; likewise, for the utility and vendor it is important to know what margins exist and what they are based on, to identify in which direction they can make further progress and optimize fuel and fuel cycle cost. Naturally, each party involved will have to decide on how much margin should be in place, to establish operational criteria and ensure that these can actually be met during operation. To assess the margins issue, safety criteria themselves need to be reviewed first. Most - if not all - of the currently existing safety criteria were established during the 60's and early 70's, and verified against experiments with fuel available at that time - mostly at zero exposure. Of course, verification was performed as designs progressed in later years, primarily with the aim to be able to prove that safety criteria were adequate as long as the said conservatisms would be retained, and not with the aim to reestablish limits. The mandate to the OECD/CSNI/PWG2 Task Force on Fuel Safety Criteria (TFFSC) is to assess the adequacy of existing fuel safety criteria, in view of the 'new design' elements (new

Provision of radiation safety at the designing of the industrial complex of solid radwaste management (ICSRM)

International Nuclear Information System (INIS)

Lobach, S.Yu.; Sevastyuk, O.V.

2003-01-01

The article presents the basic principles and criteria of the radiation safety provision, organization of the radiation control system, and dose calculation for the staff irradiation at the construction and operation of the Industrial complex of solid radwaste management (ICSRM)

The first symposium of Research Center for Radiation Safety, NIRS. Perspective of future studies of radiation safety

International Nuclear Information System (INIS)

Shimo, Michikuni

2002-03-01

This paper summarizes presentations given in the title symposium, held at the Conference Room of National Institute of Radiological Sciences (NIRS) on November 29 and 30, 2001. Contained are Introductory remarks: Basic presentations concerning exposure dose in man; Environmental levels of radiation and radioactivity, environmental radon level and exposure dose, and radiation levels in the specific environment (like in the aircraft): Special lecture (biological effects given by space environment) concerning various needs for studies of radiation safety; Requirement for open investigations, from the view of utilization, research and development of atomic energy, from the clinical aspect, and from the epidemiological aspect: Special lecture (safety in utilization of atomic energy and radiation-Activities of Nuclear Safety Commission of Japan) concerning present state and perspective of studies of radiation safety; Safety of radiation and studies of biological effects of radiation-perspective, and radiation protection and radiation safety studies: Studies in the Research Center for Radiation Safety; Summary of studies in the center, studies of the biological effects of neutron beam, carcinogenesis by radiation and living environmental factors-complicated effects, and studies of hereditary effects: Panel discussion (future direction of studies of radiation safety for the purpose of the center's direction): and concluding remarks. (N.I.)

Radiation safety among cardiology fellows.

Science.gov (United States)

Kim, Candice; Vasaiwala, Samip; Haque, Faizul; Pratap, Kiran; Vidovich, Mladen I

2010-07-01

Cardiology fellows can be exposed to high radiation levels during procedures. Proper radiation training and implementation of safety procedures is of critical importance in lowering physician health risks associated with radiation exposure. Participants were cardiology fellows in the United States (n = 2,545) who were contacted by e-mail to complete an anonymous survey regarding the knowledge and practice of radiation protection during catheterization laboratory procedures. An on-line survey engine, SurveyMonkey, was used to distribute and collect the results of the 10-question survey. The response rate was 10.5%. Of the 267 respondents, 82% had undergone formal radiation safety training. Only 58% of the fellows were aware of their hospital's pregnancy radiation policy and 60% knew how to contact the hospital's radiation safety officer. Although 52% of the fellows always wore a dosimeter, 81% did not know their level of radiation exposure in the previous year and only 74% of fellows knew the safe levels of radiation exposure. The fellows who had received formal training were more likely to be aware of their pregnancy policy, to know the contact information of their radiation safety officer, to be aware of the safe levels of radiation exposure, to use dosimeters and RadPad consistently, and to know their own level of radiation exposure in the previous year. In conclusion, cardiology fellows have not been adequately educated about radiation safety. A concerted effort directed at physician safety in the workplace from the regulatory committees overseeing cardiology fellowships should be encouraged. Published by Elsevier Inc.

Safety Criteria and Standards for Bearing Capacity of Foundation

Directory of Open Access Journals (Sweden)

Yanlong Li

2017-01-01

Full Text Available This paper focuses on the evaluation standards of factor of safety for foundation stability analysis. The problem of foundation stability is analyzed via the methods of risk analysis of engineering structures and reliability-based design, and the factor of safety for foundation stability is determined by using bearing capacity safety-factor method (BSFM and strength safety-factor method (SSFM. Based on a typical example, the admissible factors of safety were calibrated with a target reliability index specified in relevant standards. Two safety criteria and their standards of bearing capacity of foundation for these two methods (BSFM and SSFM were established. The universality of the safety criteria and their standards for foundation reliability was verified based on the concept of the ratio of safety margin (RSM.

Data survey about radiation protection and safety of radiation sources in research laboratories

International Nuclear Information System (INIS)

Paura, Clayton L.; Dantas, Ana Leticia A.; Dantas, Bernardo M.

2005-01-01

In Brazil, different types of research using unsealed sources are developed with a variety of radioisotopes. In such activities, professionals and students involved are potentially exposed to internal contamination by 14 C, 45 Ca, 51 Cr, 3 H, 125 I, 32 P, 33 P, 35 S, 90 Sr and 99m Tc. The general objective of this work is to evaluate radiological risks associated to these practices in order to supply information for planning actions aimed to improve radiation protection conditions in research laboratories. The criteria for risk evaluation and the safety aspects adopted in this work were based on CNEN Regulation 6.02 and in IAEA and NRPB publications. The survey of data was carried out during visits to laboratories in public Universities located in the city of Rio de Janeiro where unsealed radioactive sources are used in biochemistry, biophysics and genetic studies. According to the criteria adopted in this work, some practices developed in the laboratories require evaluation of risk of internal contamination depending on the conditions of source manipulation. It was verified the need for training of users of radioactive materials in this type of laboratory. This can be facilitated by the use of basic guides for the classification of areas, radiation protection, safety and source security in research laboratories. It was also observed the need for optimization of such practices in order to minimize the contact with sources. It is recommended to implement more effective source and access controls as a way to reduce risks of individual radiation exposure and loss of radioactive materials (author)

Radiation Safety for Sustainable Development

International Nuclear Information System (INIS)

2015-10-01

The objective of radiation safety is Assessments of Natural Radioactivity and its Radiological. The following topics were discussed during the conference: AFROSAFE Championing Radiation Safety in Africa, Radiation Calibration, and Development and Validation of a Laser Induced Breakdown Spectrometry Method for Cancer Detection and Characterization. Young Generation in NUCLEAR Initiative to Promote Nuclear Science and Technology, Radiation Protection Safety Culture and Application of Nuclear Techniques in Industry and the Environment were discuss. Rapid Chemometric X-Ray Fluorescence approaches for spectral Diagnostics of Cancer utilizing Tissue Trace Metals and Speciation profiles. Fundamental role of medical physics in Radiation Therapy

Radiation and waste safety

International Nuclear Information System (INIS)

1997-01-01

Most of the ionizing radiation that people are exposed to in day-to-day activities comes from natural, rather than manmade, sources. Nuclear radiation is a powerful source of benefit to mankind, whether applied in the field of medicine, agriculture, environmental management or elsewhere. The health effects of radiation - both natural and artificial - are relatively well understood and can be minimized through careful safety measures and practices. The Department of Technical Co-operation is sponsoring a programme with the support of the Nuclear Safety Department aiming at establishing Basic Safety Standard requirements in all Member States. (IAEA)

International comparison of safety criteria applied to radwaste repositories. Safety aspects of the post-operational phase

International Nuclear Information System (INIS)

Baltes, B.

1994-01-01

There is a generally accepted system of framework safety conditions governing the construction, operation, and post-operational monitoring of radwaste repositories. Although the development of these framework conditions may vary from country to country, the resulting criteria are based on the commonly accepted system of priciples and purposes established for ultimate radioactive waste disposal. The experience accumulated by GRS in the course of the plan approval procedure for the Konrad mine site and the safety-relevant studies performed for the planned Morsleben repository clearly show demand for further development of the safety criteria. In Germany, it is especially the safety criteria and detailed requirements filling the framework safety conditions that need revision and in-depth definition, as well as comparison and harmonisation with internationally applied criteria. These activities will particularly consider the international convention on radioactive waste management currently in preparation under the auspieces of the IAEA. (orig.) [de

Quality assurance and radiation safety in positron emission tomography

International Nuclear Information System (INIS)

Kmetyuk, Ya.V.; Radosh, H.V.; Bezshyyko, O.A.; Golinka-Bezshyyko, L.O.; Kadenko, I.M.; Kazinova, O.A.; Nagai, A.O.

2012-01-01

Scientific studies, clinical experience and economic analysis have shown that the positron emission tomography (PET) is clinically and cost effective cancer diagnostics method. Combined PET and computed tomography (PET/CT) has proven clinical utility, particularly in the diagnosis, staging or restaging malignant disease and metastases, surgical planning, radiation therapy planning and evaluation of treatment response. The use of PET/CT has grown substantially in the past few years, with an increasing number of hospitals and installations of PET/CT imaging centers each year. In the same time combination of 2 procedures, each of which impart a radiation dose and, as a result, increases the deleterious influence for health, creates additional radiation safety issues. In these conditions the role of quality assurance (QA) and quality control (QC) programs is getting more and more important. We considered main QA and radiation safety requirements for whole PET technology chain from radio-pharmacy facilities to PET/CT scanning and patient release criteria. All these issues were considered and assessed having the example of PET facilities and technology chain of All-Ukrainian Center for Radiosurgery of the Clinical Hospital 'Feofania'

Occupational safety meets radiation protection

International Nuclear Information System (INIS)

Severitt, S.; Oehm, J.; Sobetzko, T.; Kloth, M.

2012-01-01

The cooperation circle ''Synergies in operational Security'' is a joint working group of the Association of German Safety Engineers (VDSI) and the German-Swiss Professional Association for Radiation Protection (FS). The tasks of the KKSyS are arising from the written agreement of the two associations. This includes work on technical issues. In this regard, the KKSyS currently is dealing with the description of the interface Occupational Safety / Radiation Protection. ''Ignorance is no defense'' - the KKSyS creates a brochure with the working title ''Occupational Safety meets radiation protection - practical guides for assessing the hazards of ionizing radiation.'' The target groups are entrepreneurs and by them instructed persons to carry out the hazard assessment. Our aim is to create practical guides, simple to understand. The practical guides should assist those, who have to decide, whether an existing hazard potential through ionizing radiation requires special radiation protection measures or whether the usual measures of occupational safety are sufficient. (orig.)

Safety principles and design criteria for nuclear power stations

International Nuclear Information System (INIS)

Gazit, M.

1982-01-01

The criteria and safety principles for the design of nuclear power stations are presented from the viewpoint of a nuclear engineer. The design, construction and operation of nuclear power stations should be carried out according to these criteria and safety principles to ensure, to a reasonable degree, that the likelihood of release of radioactivity as a result of component failure or human error should be minimized. (author)

Safety criteria of uranium enrichment plants

International Nuclear Information System (INIS)

Nardocci, A.C.; Oliveira Neto, J.M. de

1994-01-01

The applicability of nuclear reactor safety criteria applied to uranium enrichment plants is discussed, and a new criterion based on the soluble uranium compounds and hexafluoride chemical toxicities is presented. (L.C.J.A.). 21 refs, 4 tabs

Radiation safety and quality control assurance in X-ray diagnostics 1998; Saeteilyturvallisuus ja laadunvarmistus roentgendiagnostiikassa 1998

Energy Technology Data Exchange (ETDEWEB)

Servomaa, A [ed.

1998-03-01

The report is based on a seminar course of lectures `Radiation safety and quality assurance in X-ray diagnostics 1998` organized by the Radiation and Nuclear Safety Authority (STUK) in Finland. The lectures included actual information on X-ray examinations: methods of quality assurance, methods of measuring and calculating patient doses, examination frequencies, patient doses, occupational doses, and radiation risks. Paediatric X-ray examinations and interventional procedures were the most specific topics. The new Council Directive 97/43/Euratom on medical exposure, and the European Guidelines on quality criteria for diagnostic radiographic images, were discussed in several lectures. Lectures on general radiation threats and preparedness, examples of radiation accidents, and emergency preparedness in hospitals were also included. (editor)

Investigation on regulatory requirements for radiation safety management

International Nuclear Information System (INIS)

Han, Eun Ok; Choi, Yoon Seok; Cho, Dae Hyung

2013-01-01

NRC recognizes that efficient management of radiation safety plan is an important factor to achieve radiation safety service. In case of Korea, the contents to perform the actual radiation safety management are legally contained in radiation safety management reports based on the Nuclear Safety Act. It is to prioritize the importance of safety regulations in each sector in accordance with the current situation of radiation and radioactive isotopes-used industry and to provide a basis for deriving safety requirements and safety regulations system maintenance by the priority of radiation safety management regulations. It would be helpful to achieve regulations to conform to reality based on international standards if consistent safety requirements is developed for domestic users, national standards and international standards on the basis of the results of questions answered by radiation safety managers, who lead on-site radiation safety management, about the priority of important factors in radioactive sources use, sales, production, moving user companies, to check whether derived configuration requirements for radiation safety management are suitable for domestic status

Improving safety margin of LWRs by rethinking the emergency core cooling system criteria and safety system capacity

Energy Technology Data Exchange (ETDEWEB)

Lee, Youho, E-mail: euo@kaist.ac.kr; Kim, Bokyung, E-mail: bkkim2@kaist.ac.kr; NO, Hee Cheon, E-mail: hcno@kaist.ac.kr

2016-10-15

Highlights: • Zircaloy embrittlement criteria can increase to 1370 °C for CP-ECR lower than 13%. • The draft ECCS criteria of U.S. NRC allow less than 5% in power margin. • The Japanese fracture-based criteria allow around 5% in power margin. • Increasing SIT inventory is effective in assuring safety margin for power uprates. - Abstract: This study investigates the engineering compatibility between emergency core cooling system criteria and safety water injection systems, in the pursuit of safety margin increase of light water reactors. This study proposes an acceptable temperature increase to 1370 °C as long as equivalent cladding reacted calculated by the Cathcart–Pawel equation is below 13%, after an extensive literature review. The influence of different ECCS criteria on the safety margin during large break loss of coolant accident is investigated for OPR-1000 by the system code MARS-KS, implemented with the KINS-REM method. The fracture-based emergency core cooling system (ECCS) criteria proposed in this study are shown to enable power margins up to 10%. In the meantime, the draft U.S. NRC’s embrittlement criteria (burnup-sensitive) and Japanese fracture-based criteria are shown to allow less than 5%, and around 5% of power margins, respectively. Increasing safety injection tank (SIT) water inventory is the key, yet convenient, way of assuring safety margin for power increase. More than 20% increase in the SIT water inventory is required to allow 15% power margins, for the U.S. NRC’s burnup-dependent embrittlement criteria. Controlling SIT water inventory would be a useful option that could allow the industrial desire to pursue power margins even under the recent atmosphere of imposing stricter ECCS criteria for the considerable burnup effects.

Radiation Safety (Qualifications) Regulations 1980

International Nuclear Information System (INIS)

1980-01-01

These Regulations, promulgated pursuant to the provisions of the Radiation Safety Act, 1975-1979, require persons engaged in activities involving radiation to pass a radiation safety examination or to possess an approved qualification in radiation. The National Health and Medical Research Council is authorised to exempt persons from compliance with these requirements or, conversely, to impose such requirements on persons other than those designated. (NEA) [fr

RF radiation safety handbook

International Nuclear Information System (INIS)

Kitchen, Ronald.

1993-01-01

Radio frequency radiation can be dangerous in a number of ways. Hazards include electromagnetic compatibility and interference, electro-explosive vapours and devices, and direct effects on the human body. This book is a general introduction to the sources and nature of RF radiation. It describes the ways in which our current knowledge, based on relevant safety standards, can be used to safeguard people from any harmful effects of RF radiation. The book is designed for people responsible for, or concerned with, safety. This target audience will primarily be radio engineers, but includes those skilled in other disciplines including medicine, chemistry or mechanical engineering. The book covers the problems of RF safety management, including the use of measuring instruments and methods, and a review of current safety standards. The implications for RF design engineers are also examined. (Author)

Panel 1: Safety design criteria

International Nuclear Information System (INIS)

Yllera, Javier

2013-01-01

There is general consensus in the nuclear community, and more after the Fukushima accident, that the deployment of nuclear energy has to be done at the highest levels of nuclear safety and that safety cannot be compromised by other factors. It is well understood that reactors that are being licensed and the new generations of reactors that will be constructed in the future will need to reach higher safety levels than the existing ones. Several countries and international organizations or international groups are launching initiatives to harmonise safety goals, safety requirements, safety objectives, regulations, criteria or safety reference levels. There are differences in the meanings of these terms and the working approaches, but the overall purpose is the same: to specify how new plants can be safer. In this context, the IAEA has an statutory function for developing international nuclear safety standards. The IAEA safety standards are per se not mandatory for IAEA Member States. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA’s standards for use in their national regulations in different ways. The IAEA Safety Standards represent international consensus on what must constitute a high level of safety for nuclear installations. In the area of NPP design, IAEA safety standards that are published are intended to apply primarily to new plants. It might not be practicable to apply all the requirements to plants that are already in operation. In addition, the focus is primarily on plants with water cooled reactors

International basic safety standards for protecting against ionizing radiation and for the safety of radiation sources

International Nuclear Information System (INIS)

1996-01-01

The purpose of the Standards is to establish basic requirements for protection against the risks associated with exposure to ionizing radiation (hereinafter termed radiation) and for the safety of radiation sources that may deliver such exposure. The Standards have been developed from widely accepted radiation protection and safety principles, such as those published in the Annals of the ICRP and the IAEA Safety Series. They are intended to ensure the safety of all types of radiation sources and, in doing so, to complement standards already developed for large and complex radiation sources, such as nuclear reactors and radioactive waste management facilities. For the sources, more specific standards, such as those issued by the IAEA, are typically needed to achieve acceptable levels of safety. As these more specific standards are generally consistent with the Standards, in complying with them, such more complex installations will also generally comply with the Standards. The Standards are limited to specifying basic requirements of radiation protection and safety, with some guidance on how to apply them. General guidance on applying some of the requirements is available in the publications of the Sponsoring Organizations and additional guidance will be developed as needed in the light of experience gained in the application of the Standards. Tabs

International basic safety standards for protecting against ionizing radiation and for the safety of radiation sources

International Nuclear Information System (INIS)

1997-01-01

The purpose of the Standards is to establish basic requirements for protection against the risks associated with exposure to ionizing radiation (hereinafter termed radiation) and for the safety of radiation sources that may deliver such exposure. The Standards have been developed from widely accepted radiation protection and safety principles, such as those published in the Annals of the ICRP and the IAEA Safety Series. They are intended to ensure the safety of all types of radiation sources and, in doing so, to complement standards already developed for large and complex radiation sources, such as nuclear reactors and radioactive waste management facilities. For the sources, more specific standards, such as those issued by the IAEA, are typically needed to achieve acceptable levels of safety. As these more specific standards are generally consistent with the Standards, in complying with them, such more complex installations will also generally comply with the Standards. The Standards are limited to specifying basic requirements of radiation protection and safety, with some guidance on how to apply them. General guidance on applying some of the requirements is available in the publications of the Sponsoring Organizations and additional guidance will be developed as needed in the light of experience gained in the application of the Standards

Licensing procedures and safety criteria for research reactors in France

International Nuclear Information System (INIS)

Berry, J.L.; Lerouge, B.

1980-11-01

This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. Some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors. At the end, a few considerations are given to the consequences of the Osiris core conversion

Regulatory control of radiation sources. Safety guide

International Nuclear Information System (INIS)

2004-01-01

The basic requirements for the protection of persons against exposure to ionizing radiation and for the safety of radiation sources were established in the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards), jointly sponsored by the Food and Agriculture Organization of the United Nations (FAO), the International Atomic Energy Agency (IAEA), the International Labour Organization (ILO), the OECD Nuclear Energy Agency (OECD/ NEA), the Pan American Health Organization (PAHO) and the World Health Organization (WHO) (the Sponsoring Organizations). The application of the Basic Safety Standards is based on the presumption that national infrastructures are in place to enable governments to discharge their responsibilities for radiation protection and safety. Requirements relating to the legal and governmental infrastructure for the safety of nuclear facilities and sources of ionizing radiation, radiation protection, the safe management of radioactive waste and the safe transport of radioactive material are established in the Safety Requirements on Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety, Safety Standards Series No. GS-R-1. This Safety Guide, which is jointly sponsored by the FAO, the IAEA, the International Labour Office, the PAHO and the WHO, gives detailed guidance on the key elements for the organization and operation of a national regulatory infrastructure for radiation safety, with particular reference to the functions of the national regulatory body that are necessary to ensure the implementation of the Basic Safety Standards. The Safety Guide is based technically on material first published in IAEA-TECDOC-10671, which was jointly sponsored by the FAO, the IAEA, the OECD/NEA, the PAHO and the WHO. The requirements established in GS-R-1 have been taken into account. The Safety Guide is oriented towards national

Occupational radiation safety in mining

International Nuclear Information System (INIS)

Stocker, H.

1985-01-01

The first International Conference on Occupational Radiation Safety in Mining was held three years ago in Golden, Colorado, U.S.A., and it provided an excellent forum for an exchange of information on the many scientific, technical and operational aspects of radiation safety in mining. I am aware of the broad spectrum of epidemiological, engineering and related studies which have been pursued during the past three years with a view to achieving further improvements in radiation protection and I expect that the information on these studies will contribute significantly to a wider understanding of subject, and in particular, the means by which radiation safety measures in mining can be optimized

AFROSAFE Championing Radiation Safety in Africa

International Nuclear Information System (INIS)

Nyabanda, R.

2015-01-01

AFRASAFE is a campaign that was formed by Pan African congress of Radiology and imaging (PACOR) and other radiation health workers in Africa in Feb 2015. Its main objective is to unite with a common goal to identify and address issues arising from radiation protection in medicine in Africa. Through this campaign, we state that we shall promote adherence to policies, strategies and activities for the promotion of radiation safety and for maximization of benefits from radiological medical procedures. The campaign strengthens the overall radiation protection of patients, health workers and public. It promotes safe and appropriate use of ionizing radiation in medicine and enhances global information to help improve the benefit/risk dialogue with patients and the public. It enhances the safety and quality of radiological procedures in medicine, and encourages safety in diagnostic and therapeutic equipment and facilities. The issue of research in radiation protection and safety needs to be promoted. This presentation will outline the six strategic objectives and the implementation tools for radiation safety in medicine in Kenya, the challenges and way forward to achieve our goal. (Author)

Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. General Safety Requirements. Pt. 3 (Chinese Edition)

International Nuclear Information System (INIS)

2014-01-01

This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

Radiation protection and safety of radiation sources: International basic safety standards. General safety requirements. Pt. 3 (French Edition)

International Nuclear Information System (INIS)

2016-01-01

This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. General Safety Requirements. Pt. 3 (Arabic Edition)

International Nuclear Information System (INIS)

2015-01-01

This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

Compilation of nuclear safety criteria potential application to DOE nonreactor facilities

International Nuclear Information System (INIS)

1992-03-01

This bibliographic document compiles nuclear safety criteria applied to the various areas of nuclear safety addressed in a Safety Analysis Report for a nonreactor nuclear facility (NNF). The criteria listed are derived from federal regulations, Nuclear Regulatory Commission (NRC) guides and publications, DOE and DOE contractor publications, and industry codes and standards. The titles of the chapters and sections of Regulatory Guide 3.26, ''Standard Format and Content of Safety Analysis Reports for Fuel Reprocessing Plants'' were used to format the chapters and sections of this compilation. In each section the criteria are compiled in four groups, namely: (1) Code of Federal Regulations, (2) USNRC Regulatory Guides, (3) Codes and Standards, and (4) Supplementary Information

Proceeding of Radiation Safety and Environment

International Nuclear Information System (INIS)

1996-01-01

Scientific Presentation of Radiation Safety and Environment was held on 20-21 august 1996 at Center of Research Atomic Energy Pasar Jum'at, Jakarta, Indonesia. Have presented 50 papers about Radiation Safety, dosimetry and standardization, environment protection and radiation effect

Nuclear and radiation safety policy

International Nuclear Information System (INIS)

Mikus, T; Strycek, E.

1998-01-01

Slovenske elektrarne (SE) is a producer of electricity and heat, including from nuclear fuel source. The board of SE is ultimately responsible for nuclear and radiation safety matters. In this leaflet main principles of maintaining nuclear and radiation safety of the Company SE are explained

Radiation safety: New international standards

International Nuclear Information System (INIS)

Gonzalez, A.J.

1994-01-01

This article highlights an important result of this work for the international harmonization of radiation safety: specifically, it present an overview of the forthcoming International Basic Safety Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources - the so-called BSS. They have been jointly developed by six organizations - the Food and Agriculture Organization of the United Nations (FAO), the International Atomic Energy Agency (IAEA), the International Labour Organization (ILO), the Nuclear Energy Agency of the Organization for Economic Co-operation and Development (NEA/OECD), the Pan American Health Organization (PAHO), and the World Health Organization (WHO)

Radiation safety of Takasaki ion accelerators for advanced radiation in JAERI

International Nuclear Information System (INIS)

Watanabe, Hiromasa; Tanaka, Susumu; Anazawa, Yutaka

1991-01-01

Building layout of Takasaki ion accelerator facility has been started since 1987, with the propulsion of research development of (1) cosmetic environment materials, (2) nuclear fusion reactors, (3) biotechnology, and (4) new functional materials. This paper deals with an AVF cyclotron and a tandem type accelerator, focusing on safety design, radiation safety management, and radioactive waste management. Safety design is discussed in view of radiation shielding and activation countermeasures. Radiation safety management covers radiation monitoring in the workplace, exhaust radioactivity, environment outside the facility, and the other equipments; personal monitoring; and protective management of exposure. For radiation waste management, basic concept and management methods are commented on. (N.K.)

Safety criteria for nuclear chemical plants

International Nuclear Information System (INIS)

Ball, P.W.; Curtis, L.M.

1983-01-01

Safety measures have always been required to limit the hazards due to accidental release of radioactive substances from nuclear power plants and chemical plants. The risk associated with the discharge of radioactive substances during normal operation has also to be kept acceptably low. BNFL (British Nuclear Fuels Ltd.) are developing risk criteria as targets for safe plant design and operation. The numerical values derived are compared with these criteria to see if plants are 'acceptably safe'. However, the criteria are not mandatory and may be exceeded if this can be justified. The risk assessments are subject to independent review and audit. The Nuclear Installations Inspectorate also has to pass the plants as safe. The assessment principles it uses are stated. The development of risk criteria for a multiplant site (nuclear chemical plants tend to be sited with many others which are related functionally) is discussed. This covers individual members of the general public, societal risks, risks to the workforce and external hazards. (U.K.)

Protection criteria from the non-ionizing radiations

International Nuclear Information System (INIS)

Touzet, Rodolfo E.

2004-01-01

The first objective of the protection philosophy is to determinate the relation reason-effect in order to establish the exposition thresholds to acceptable values. To establish the radioprotection criteria is important to considerate the following: a-) The damage and effects of the non-ionizing radiation; b-) The physical aspects of the fields exposition; and c-) The dosimetry of the involucrate tissues. The non-ionizing radiation includes the optics radiations (ultraviolet, visible, infrared and laser), and the electromagnetic radiations (microwave, radars, magnetic and electrostatics fields)

Radiation safety without borders initiative

International Nuclear Information System (INIS)

Dibblee, Martha; Dickson, Howard; Krieger, Ken; Lopez, Jose; Waite, David; Weaver, Ken

2008-01-01

The Radiation Safety Without Borders (RSWB) initiative provides peer support to radiation safety professionals in developing countries, which bolsters the country's infrastructure and may lead the way for IRPA Associate membership. The Health Physics Society (HPS) recognizes that many nations do not possess the infrastructure to adequately control and beneficially use ionizing radiation. In a substantial number of countries, organized radiation protection programs are minimal. The RSWB initiative relies on HPS volunteers to assist their counterparts in developing countries with emerging health physics and radiation safety programs, but whose resources are limited, to provide tools that promote and support infrastructure and help these professionals help themselves. RSWB experience to date has shown that by providing refurbished instruments, promoting visits to a HPS venue, or visiting a country just to look provide valuable technical and social infrastructure experiences often missing in the developing nation's cadre of radiation safety professionals. HPS/RSWB with the assistance of the International Atomic Energy Agency (IAEA) pairs chapters with a country, with the expectation that the country's professional radiation safety personnel will form a foreign HPS chapter, and the country eventually will become an IRPA Associate. Although still in its formative stage, RSWB nonetheless has gotten valuable information in spite of the small number of missions. The RSWB initiative continues to have significant beneficial impacts, including: Improving the radiation safety infrastructure of the countries that participate; Assisting those countries without professional radiation safety societies to form one; Strengthening the humanitarian efforts of the United States; Enhancing Homeland Security efforts through improved control of radioactive material internationally. Developing countries, including those in Latin America, underwritten by IAEA, may take advantage of resources

Radiation Safety in Industrial Radiography. Specific Safety Guide

International Nuclear Information System (INIS)

2011-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography.

Intervention criteria in a nuclear or radiation emergency

International Nuclear Information System (INIS)

1994-01-01

In September 1993, the IAEA convened a Technical Committee Meeting on intervention and accidents. This technical committee modified the text and values from member states and international organizations, and combined them with the draft revision of Safety Series No. 72. This Safety Guide is the result of that process and represents an international understanding on the principles for intervention and numerical values for generic intervention levels. The recommendations of the present Safety Guide are the basis for the International Basic Safety Standards for Protection against Ionizing Radiations and for the Safety of Radiation Sources of the FAO, the IAEA, the International Labour Organisations, the Nuclear Energy Agency of the Organisation for Economic Cooperation and Development, the Pan American Health Organization and the WHO. Refs, figs and tabs

Fuel safety criteria in NEA member countries - Compilation of responses received from member countries

International Nuclear Information System (INIS)

2003-03-01

In 2001 the Committee on the Safety of Nuclear Installations (CSNI) issued a report on Fuel Safety Criteria Technical Review. The objective was to review the present fuel safety criteria and judge to which extent they are affected by the 'new' design elements, such as different cladding materials, higher burnup, the use of MOX fuels, etc. The report stated that the current framework of fuel safety criteria remains generally applicable, being largely unaffected by the 'new' or modern design elements. The levels (numbers) in the individual safety criteria may, however, change in accordance with the particular fuel and core design features. Some of these levels have already been - or are continuously being - adjusted. The level adjustments of several other criteria (RIA, LOCA) also appears to be needed, on the basis of experimental data and the analysis thereof. As a follow-up, among its first tasks, the CSNI Special Expert Group on Fuel Safety Margins (SEG FSM) initiated the collection of information on the present fuel safety criteria used in NEA member states with the objective to solicit national practices in the use of fuel safety criteria, in particular to get information on their specific national levels/values, including their recent adjustments, and to identify the differences and commonalties between the different countries. Two sources of information were used to produce this report: a compilation of responses to a questionnaire prepared for the June 2000 CNRA meeting, and individual responses from the SEGFSM members to the new revised questionnaire issued by the task Force preparing this report. In accordance with the latter, the fuel safety criteria discussed in this report were divided into three categories: (A) safety criteria - criteria imposed by the regulator; (B) operational criteria - specific to the fuel design and provided by the fuel vendor as part of the licensing basis; (C) design criteria - limits employed by vendors and/or utilities for fuel

Implementation of radiation safety program in a medical institution

International Nuclear Information System (INIS)

Palanca, Elena D.

1999-01-01

A medical institution that utilizes radiation for the diagnosis and treatment of diseases of malignancies develops and implements a radiation safety program to keep occupational exposures of radiation workers and exposures of non-radiation workers and the public to the achievable and a more achievable minimum, to optimize the use of radiation, and to prevent misadministration. The hospital radiation safety program is established by a core medical radiation committee composed of trained radiation safety officers and head of authorized users of radioactive materials and radiation machines from the different departments. The radiation safety program sets up procedural guidelines of the safe use of radioactive material and of radiation equipment. It offers regular training to radiation workers and radiation safety awareness courses to hospital staff. The program has a comprehensive radiation safety information system or radsis that circularizes the radiation safety program in the hospital. The radsis keeps the drafted and updated records of safety guides and policies, radioactive material and equipment inventory, personnel dosimetry reports, administrative, regulatory and licensing activity document, laboratory procedures, emergency procedures, quality assurance and quality control program process, physics and dosimetry procedures and reports, personnel and hospital staff training program. The medical radiation protection committee is tasked to oversee the actual implementation of the radiation safety guidelines in the different radiation facilities in the hospital, to review personnel exposures, incident reports and ALARA actions, operating procedures, facility inspections and audit reports, to evaluate the existing radiation safety procedures, to make necessary changes to these procedures, and make modifications of course content of the training program. The effective implementation of the radiation safety program provides increased confidence that the physician and

Radiation safety and gynaecological brachytherapy

International Nuclear Information System (INIS)

Crawford, L.

1985-01-01

In 1983, the Radiation Control Section of the South Australian Health Commission conducted an investigation into radiation safety practices in gynaecological brachytherapy. Part of the investigation included a study of the transportation of radioactive sources between hospitals. Several deficiences in radiation safety were found in the way these sources were being transported. New transport regulations came into force in South Australia in July 1984 and since then there have been many changes in the transportation procedure

Operational safety

International Nuclear Information System (INIS)

Anon.

1977-01-01

The PNL Safety, Standards and Compliance Program contributed to the development and issuance of safety policies, standards, and criteria; for projects in the nuclear and nonnuclear areas. During 1976 the major emphasis was on developing criteria, instruments and methods to assure that radiation exposure to occupational personnel and to people in the environs of nuclear-related facilities is maintained at the lowest level technically and economically practicable. Progress in 1976 is reported on the preparation of guidelines for radiation exposure; Pu dosimetry studies; the preparation of an environmental monitoring handbook; and emergency instrumentation preparedness

Radiation Safety Aspects of Nanotechnology

Energy Technology Data Exchange (ETDEWEB)

Hoover, Mark [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Myers, David; Cash, Leigh Jackson [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Guilmette, Raymond [Ray Guilmette & Associates, LLC, Perry, ME (United States); Kreyling, Wolfgang [Helmholtz-Zentrum Munchen, (Germany); Oberdorster, Gunter [Univ. of Rochester, NY (United States); Smith, Rachel [Public Health England, Oxfordshire (United Kingdom). Centre for Radiation, Chemical and Environmental Hazards

2017-03-27

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

Radiation safety - an IAEA perspective

International Nuclear Information System (INIS)

Persson, L.

1993-01-01

The activities of the IAEA relating to radiation safety cover: The preparation of International Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources - it is expected that the new Basic Safety Standards will be adopted by the sponsoring organizations in 1994. The radiological consequences of the Chernobyl accident: the thyroid cancer controversy - the hypothesis that must be tested is whether the reported increased incidence of thyroid cancer due to exposure to radioactive iodine released in the Chernobyl accident, and there are several questions that must be answered before a firm conclusion can be reached. Emergency Response Services (ERS): In March 1993, at the request of Viet Nam, which invoked the Energency Assistance Convention, a medical team organized by the IAEA went to Hanoi and assisted in arranging for an overexposed person to be transferred from Viet Nam to Paris for specialized medical treatment. In April 1993, the ERS was used to inform Member States of the consequences of an explosion at the Tomsk 7 fuel reprocessing plant in Siberia, Russia, which caused a radiation leak. Reassessing the long range transport of radioactive material through the environment: Data from the Chernobyl accident have been used for model validation in the Atmospheric Transport Model Evaluation Study (ATMES). A follow-up programme, the European Tracer Experiment (ETEX) with experimental studies of long range atmospheric movements over Europe has been established in order to increase knowledge and prediction capability. As part of the programme, a non-toxic atmospheric tracer will be released under suitable conditions in 1994. The Radiation Protection Advisory Teams Service (RAPAT): In many of the developing countries visited, the lack of an adequate infrastructure for radiation protection is the main obstacle to improved radiation protection. Strengthening radiation and nuclear safety infrastructures in successor states of the USSR: The

Radiation protection and safety infrastructures in Albania

International Nuclear Information System (INIS)

Paci, Rustem; Ylli, Fatos

2008-01-01

The paper intends to present the evolution and actual situation of radiation protection and safety infrastructure in Albania, focusing in its establishing and functioning in accordance with BBS and other important documents of specialized international organizations. There are described the legal framework of radiation safety, the regulatory authority, the services as well the practice of their functioning. The issue of the establishing and functioning of the radiation safety infrastructure in Albania was considered as a prerequisite for a good practices development in the peaceful uses of radiation sources . The existence of the adequate legislation and the regulatory authority, functioning based in the Basic Safety Standards (BSS), are the necessary condition providing the fulfilment of the most important issues in the mentioned field. The first document on radiation protection in Albania stated that 'for the safe use of radiation sources it is mandatory that the legal person should have a valid permission issued by Radiation Protection Commission'. A special organ was established in the Ministry of Health to supervise providing of the radiation protection measures. This organization of radiation protection showed many lacks as result of the low efficiency . The personnel monitoring, import, transport, waste management and training of workers were in charge of Institute of Nuclear Physics (INP). In 1992 an IAEA RAPAT mission visited Albania and proposed some recommendations for radiation protection improvements. The mission concluded that 'the legislation of the radiation protection should be developed'. In 1995 Albania was involved in the IAEA Model Project 'Upgrading of Radiation Protection Infrastructure'. This project, which is still in course, intended to establish the modern radiation safety infrastructures in the countries with low efficiency ones and to update and upgrade all aspects related with radiation safety: legislation and regulations, regulatory

Safety-related operator actions: methodology for developing criteria

International Nuclear Information System (INIS)

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

Effective education in radiation safety for nurses

International Nuclear Information System (INIS)

Ohno, K.; Kaori, T.

2011-01-01

In order to establish an efficient training program of radiation safety for nurses, studies have been carried out on the basis of questionnaires. Collaboration of nurses, who are usually standing closest to the patient, is necessary in order to offer safe radiological diagnostics/treatment. The authors distributed the questionnaire to 134 nurses in five polyclinic hospitals in Japan. Important questions were: fear of radiation exposure, knowledge on the radiation treatment, understanding the impact on pregnancy, and so on. Most of the nurses feel themselves uneasy against exposure to radiation. They do not have enough knowledge of radiological treatment. They do not know exactly what is the impact of the radiation on pregnant women. Such tendency is more pronounced, when nurses spend less time working in the radiological department. Nurses play important roles in radiological diagnostics/treatment. Therefore, a well-developed education system for radiation safety is essential. The training for the radiation safety in medicine should be done in the context of general safety in medicine. Education programs in undergraduate school and at the working place should be coordinated efficiently in order to ensure that both nurses and patients are informed about the meaning of radiation safety. (authors)

The increased use of radiation requires enhanced activities regarding radiation safety control

International Nuclear Information System (INIS)

Lee, Yun Jong; Lee, Jin Woo; Jeong, Gyo Seong

2015-01-01

More recently, companies that have obtained permission to use radioactive materials or radiation device and registered radiation workers have increased by 10% and 4% respectively. The increased use of radiation could have an effect on radiation safety control. However, there is not nearly enough manpower and budget compared to the number of workers and facilities. This paper will suggest a counteroffer thought analyzing pending issues. The results of this paper indicate that there are 47 and 31.3 workers per radiation protection officer in educational and research institutes, respectively. There are 20.1 persons per RPO in hospitals, even though there are 2 RPOs appointed. Those with a special license as a radioisotope handler were ruled out as possible managers because medical doctors who have a special license for radioisotope handling normally have no experience with radiation safety. The number of staff members and budget have been insufficient for safety control at most educational and research institutes. It is necessary to build an optimized safety control system for effective Radiation Safety Control. This will reduce the risk factor of safety, and a few RPOs can be supplied for efficiency and convenience

The increased use of radiation requires enhanced activities regarding radiation safety control

Energy Technology Data Exchange (ETDEWEB)

Lee, Yun Jong; Lee, Jin Woo; Jeong, Gyo Seong [Korea Atomic Energy Research Institute, Jeongeup (Korea, Republic of)

2015-05-15

More recently, companies that have obtained permission to use radioactive materials or radiation device and registered radiation workers have increased by 10% and 4% respectively. The increased use of radiation could have an effect on radiation safety control. However, there is not nearly enough manpower and budget compared to the number of workers and facilities. This paper will suggest a counteroffer thought analyzing pending issues. The results of this paper indicate that there are 47 and 31.3 workers per radiation protection officer in educational and research institutes, respectively. There are 20.1 persons per RPO in hospitals, even though there are 2 RPOs appointed. Those with a special license as a radioisotope handler were ruled out as possible managers because medical doctors who have a special license for radioisotope handling normally have no experience with radiation safety. The number of staff members and budget have been insufficient for safety control at most educational and research institutes. It is necessary to build an optimized safety control system for effective Radiation Safety Control. This will reduce the risk factor of safety, and a few RPOs can be supplied for efficiency and convenience.

The role of probabilistic safety assessment and probabilistic safety criteria in nuclear power plant safety

International Nuclear Information System (INIS)

1992-01-01

The purpose of this Safety Report is to provide guidelines on the role of probabilistic safety assessment (PSA) and a range of associated reference points, collectively referred to as probabilistic safety criteria (PSC), in nuclear safety. The application of this Safety Report and the supporting Safety Practice publication should help to ensure that PSA methodology is used appropriately to assess and enhance the safety of nuclear power plants. The guidelines are intended for use by nuclear power plant designers, operators and regulators. While these guidelines have been prepared with nuclear power plants in mind, the principles involved have wide application to other nuclear and non-nuclear facilities. In Section 2 of this Safety Report guidelines are established on the role PSA can play as part of an overall safety assurance programme. Section 3 summarizes guidelines for the conduct of PSAs, and in Section 4 a PSC framework is recommended and guidance is provided for the establishment of PSC values

Criteria Document for B-plant's Surveillance and Maintenance Phase Safety Basis Document

International Nuclear Information System (INIS)

SCHWEHR, B.A.

1999-01-01

This document is required by the Project Hanford Managing Contractor (PHMC) procedure, HNF-PRO-705, Safety Basis Planning, Documentation, Review, and Approval. This document specifies the criteria that shall be in the B Plant surveillance and maintenance phase safety basis in order to obtain approval of the DOE-RL. This CD describes the criteria to be addressed in the S and M Phase safety basis for the deactivated Waste Fractionization Facility (B Plant) on the Hanford Site in Washington state. This criteria document describes: the document type and format that will be used for the S and M Phase safety basis, the requirements documents that will be invoked for the document development, the deactivated condition of the B Plant facility, and the scope of issues to be addressed in the S and M Phase safety basis document

Human factors engineering design review acceptance criteria for the safety parameter display

International Nuclear Information System (INIS)

McGevna, V.; Peterson, L.R.

1981-01-01

This report contains human factors engineering design review acceptance criteria developed by the Human Factors Engineering Branch (HFEB) of the Nuclear Regulatory Commission (NRC) to use in evaluating designs of the Safety Parameter Display System (SPDS). These criteria were developed in response to the functional design criteria for the SPDS defined in NUREG-0696, Functional Criteria for Emergency Response Facilities. The purpose of this report is to identify design review acceptance criteria for the SPDS installed in the control room of a nuclear power plant. Use of computer driven cathode ray tube (CRT) displays is anticipated. General acceptance criteria for displays of plant safety status information by the SPDS are developed. In addition, specific SPDS review criteria corresponding to the SPDS functional criteria specified in NUREG-0696 are established

Safety Design Criteria (SDC) for Gen-IV Sodium-cooled Fast Reactor

International Nuclear Information System (INIS)

Nakai, Ryodai

2013-01-01

SDC Development Background & Objectives: • Safety Design Criteria (SDC) Development for Gen-IV SFR: – Proposed at the GIF Policy Group (PG) meeting in October 2010 –SDC “harmonization” is increasingly important for: • Realization of enhanced safety designs meeting to Gen-IV safety goals and safety approach common to SFR systems; • Preparation for the forthcoming licensing in the near future; • Because Gen-IV SFR are progressing into conceptual design stage. • The SDC is the Reference criteria: – Of the designs of safety-related Structures, Systems & Components that are specific to the SFR system; – For clarifying the requisites systematically & comprehensively; – When the technology developers apply the basic safety approach and use the codes & standards for conceptual design of the Gen-IV SFR system

Radiation safety in X-ray facilities

International Nuclear Information System (INIS)

2001-09-01

The guide specifies the radiation safety requirements for structural shielding and other safety arrangements used in X-ray facilities in medical and veterinary X-ray activities and in industry, research and education. The guide is also applicable to premises in which X-ray equipment intended for radiation therapy and operating at a voltage of less than 25 kV is used. The guide applies to new X-ray facilities in which X-ray equipment that has been used elsewhere is transferred. The radiation safety requirements for radiation therapy X-ray devices operating at a voltage exceeding 25 kV, and for the premices in which such devices are used, are set out in Guide ST 2.2

Radiation safety in X-ray facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-09-01

The guide specifies the radiation safety requirements for structural shielding and other safety arrangements used in X-ray facilities in medical and veterinary X-ray activities and in industry, research and education. The guide is also applicable to premises in which X-ray equipment intended for radiation therapy and operating at a voltage of less than 25 kV is used. The guide applies to new X-ray facilities in which X-ray equipment that has been used elsewhere is transferred. The radiation safety requirements for radiation therapy X-ray devices operating at a voltage exceeding 25 kV, and for the premices in which such devices are used, are set out in Guide ST 2.2.

Improving patient safety in radiation oncology

International Nuclear Information System (INIS)

Hendee, William R.; Herman, Michael G.

2011-01-01

Beginning in the 1990s, and emphasized in 2000 with the release of an Institute of Medicine report, healthcare providers and institutions have dedicated time and resources to reducing errors that impact the safety and well-being of patients. But in January 2010 the first of a series of articles appeared in the New York Times that described errors in radiation oncology that grievously impacted patients. In response, the American Association of Physicists in Medicine and the American Society of Radiation Oncology sponsored a working meeting entitled ''Safety in Radiation Therapy: A Call to Action''. The meeting attracted 400 attendees, including medical physicists, radiation oncologists, medical dosimetrists, radiation therapists, hospital administrators, regulators, and representatives of equipment manufacturers. The meeting was cohosted by 14 organizations in the United States and Canada. The meeting yielded 20 recommendations that provide a pathway to reducing errors and improving patient safety in radiation therapy facilities everywhere.

Radiological Protection Criteria for the Safety of LILW Repository in Croatia

International Nuclear Information System (INIS)

Levanat, I.; Lokner, V.; Subasic, D.

2000-01-01

Preparations for a LILW repository development in Croatia, conducted by APO Hazardous Waste Management Agency, have reached a point where the first safety assessment of the prospective facility is being attempted. For evaluation of the calculated radiological impact in the assessed option of repository development, a set of radiological protection criteria should be included in the definition of the assessment context. The Croatian regulations do not explicitly require that the repository development be supported by such safety assessment process, and do not provide a specific set of radiological criteria intended for the repository assessment which would be suitable for the constrained optimization of protection. For the initial safety assessment iterations of the prospective repository, which will address long term performance of the facility for various design and other safety options, we propose to use relatively simple radiological protection criteria, consisting only of individual dose and risk constraints for the general population. The numerical values for these constraints are established in accordance with the recognized international recommendations and in compliance with all possibly relevant Croatian safety requirements. (author)

Working Towards Unified Safety Design Criteria for Modular High Temperature Gas-cooled Reactor Designs

International Nuclear Information System (INIS)

Reitsma, Frederik; Silady, Fred; Kunitomi, Kazuhiko

2014-01-01

The Nuclear Power Development Section of the IAEA recently received approval for a Coordinated Research Project (CRP) to investigate and make proposals on modular High Temperature Gas-cooled Reactor (HTGR) Safety design criteria. It is expected that these criteria would consider past experience and existing safety standards in the light of modular HTGR material and design characteristics to propose safety design criteria. It will consider the deterministic and risk-informed safety design standards that apply to the wide spectrum of Off- normal events under development worldwide for existing and planned HTGRs. The CRP would also take into account lessons from the Fukushima Daiichi accident, clarifying the safety approach and safety evaluation criteria for design and beyond design basis events, including those events that can affect multiple reactor modules and/or are dependent on the application proximate to the plant site. (e. g., industrial process steam/heat). The logical flow of criteria is from the fundamental inherent safety characteristics of modular HTGRs and associated expected performance characteristics, to the safety functions required to ensure those characteristics during the wide spectrum of Off-normal events, and finally to specific criteria related to those functions. This is detailed in the paper with specific examples included of how it may be applied. The results of the CRP will be made available to the member states and HTGR community. (author)

Radiation safety in aviation

International Nuclear Information System (INIS)

2005-06-01

The guide presents the requirements governing radiation safety of aircrews exposed to cosmic radiation and monitoring of such exposure. It applies to enterprises engaged in aviation under a Finnish operating licence and to Finnish military aviation at altitudes exceeding 8,000 metres. The radiation exposure of aircrews at altitudes of less than 8,000 metres is so minimal that no special measures are generally required to investigate or limit exposure to radiation

Safety approach to the selection of design criteria for the CRBRP reactor refueling system

International Nuclear Information System (INIS)

Meisl, C.J.; Berg, G.E.; Sharkey, N.F.

1979-01-01

The selection of safety design criteria for Liquid Metal Fast Breeder Reactor (LMFBR) refueling systems required the extrapolation of regulations and guidelines intended for Light Water Reactor refueling systems and was encumbered by the lack of benefit from a commercially licensed predecessor other than Fermi. The overall approach and underlying logic are described for developing safety design criteria for the reactor refueling system (RRS) of the Clinch River Breeder Reactor Plant (CRBRP). The complete selection process used to establish the criteria is presented, from the definition of safety functions to the finalization of safety design criteria in the appropriate documents. The process steps are illustrated by examples

Radiation and waste safety: Strengthening national capabilities

International Nuclear Information System (INIS)

Barretto, P.; Webb, G.; Mrabit, K.

1997-01-01

For many years, the IAEA has been collecting information on national infrastructures for assuring safety in applications of nuclear and radiation technologies. For more than a decade, from 1984-95, information relevant to radiation safety particularly was obtained through more than 60 expert missions undertaken by Radiation Protection Advisory Teams (RAPATs) and follow-up technical visits and expert missions. The RAPAT programme documented major weaknesses and the reports provided useful background for preparation of national requests for IAEA technical assistance. Building on this experience and subsequent policy reviews, the IAEA took steps to more systematically evaluate the needs for technical assistance in areas of nuclear and radiation safety. The outcome was the development of an integrated system designed to more closely assess national priorities and needs for upgrading their infrastructures for radiation and waste safety

Explanation of diagnostic criteria for radiation-induced nervous system disease

International Nuclear Information System (INIS)

Xing Zhiwei; Jiang Enhai

2012-01-01

National occupational health standard-Diagnostic Criteria for Radiation-Induced Nervous System Disease has been issued and implemented by the Ministry of health. This standard contained three independent criteria of the brain, spinal cord and peripheral nerve injury. These three kinds of disease often go together in clinic,therefore,the three diagnostic criteria were merged into radioactive nervous system disease diagnostic criteria for entirety and maneuverability of the standard. This standard was formulated based on collection of the clinical practice experience, extensive research of relevant literature and foreign relevant publications. It is mainly applied to diagnosis and treatment of occupational radiation-induced nervous system diseases, and to nervous system diseases caused by medical radiation exposure as well. In order to properly implement this standard, also to correctly deal with radioactive nervous system injury, the main contents of this standard including dose threshold, clinical manifestation, indexing standard and treatment principle were interpreted in this article. (authors)

Development of regulatory criteria applicable to control of radiation exposures to the population from products containing radioactive material

Energy Technology Data Exchange (ETDEWEB)

Rogers, L R; Western, F [U.S. Atomic Energy Commission, Germantown, MD (United States)

1969-07-01

Under the Atomic Energy Act of 1954 as amended, the Atomic Energy Commission is responsible for regulating the possession, use and transfer of byproduct, source and special nuclear materials in accordance with safety standards established by rule of the Commission to protect health and minimize danger to life and property. This paper describes some of the basic considerations in establishing safety criteria and regulations for authorizing the transfer and use of byproduct material (radioisotopes) in products for distribution to the general public. It discusses problems encountered in extending the broad guidance provided by the Federal Radiation Council (FRC) and by the International Commission of Radiological Protection and the National Council on Radiation Protection and Measurements (ICRP-NCRP), which is limited to total exposures of individuals and population groups to radiation from many sources, to appropriate controls on radioactivity in an individual consumer product which represents only one source of population exposures. The paper also discusses possible approaches to accomplishing the regulatory objectives of providing reasonable assurance that (1) the contribution of an individual product to total exposures that might be permitted under FRC and ICRP-NCRP guidance should not be disproportionate to the benefits to be derived, and (2) appropriate efforts are made to limit exposures to the population from individual classes of sources of exposure as far as practicable. Existing criteria and regulations pertaining to the control of radiation exposure to the population from products into which radioactive material is purposely introduced are described, and additional considerations which must be taken into account for the development of further criteria and regulations which are applicable to the possible wide-scale distribution of products containing radioactive material as a result of the Plowshare Programs are explored. (author)

Development of regulatory criteria applicable to control of radiation exposures to the population from products containing radioactive material

International Nuclear Information System (INIS)

Rogers, L.R.; Western, F.

1969-01-01

Under the Atomic Energy Act of 1954 as amended, the Atomic Energy Commission is responsible for regulating the possession, use and transfer of byproduct, source and special nuclear materials in accordance with safety standards established by rule of the Commission to protect health and minimize danger to life and property. This paper describes some of the basic considerations in establishing safety criteria and regulations for authorizing the transfer and use of byproduct material (radioisotopes) in products for distribution to the general public. It discusses problems encountered in extending the broad guidance provided by the Federal Radiation Council (FRC) and by the International Commission of Radiological Protection and the National Council on Radiation Protection and Measurements (ICRP-NCRP), which is limited to total exposures of individuals and population groups to radiation from many sources, to appropriate controls on radioactivity in an individual consumer product which represents only one source of population exposures. The paper also discusses possible approaches to accomplishing the regulatory objectives of providing reasonable assurance that (1) the contribution of an individual product to total exposures that might be permitted under FRC and ICRP-NCRP guidance should not be disproportionate to the benefits to be derived, and (2) appropriate efforts are made to limit exposures to the population from individual classes of sources of exposure as far as practicable. Existing criteria and regulations pertaining to the control of radiation exposure to the population from products into which radioactive material is purposely introduced are described, and additional considerations which must be taken into account for the development of further criteria and regulations which are applicable to the possible wide-scale distribution of products containing radioactive material as a result of the Plowshare Programs are explored. (author)

Radiation safety at CERN

Energy Technology Data Exchange (ETDEWEB)

Hoefert, M [CERN, Geneva (Switzerland)

1995-09-01

CERN, the European Laboratory for Particle Physics, operates proton accelerators up to an energy of 450 GeV and an electron-positron storage ring in the 50 GeV energy range for fundamental high-energy particle physics. A strong radiation protection group assures the radiation safety of these machines both during their operation and in periods of maintenance and repair. Particular radiation problems in an accelerator laboratory are presented and recent developments in radiation protection at CERN discussed. (author)

Hinkley Point 'C' power station public inquiry: proof of evidence on safety criteria

International Nuclear Information System (INIS)

Taylor, R.H.

1988-09-01

A public inquiry has been set up to examine the planning application made by the Central Electricity Generating Board (CEGB) for the construction of a 1200 MW Pressurized Water Reactor power station at Hinkley Point (Hinkley Point ''C'') in the United Kingdom. The policy is to replicate the Sizewell ''B'' PWR design which was accepted as safe by an earlier enquiry. In this evidence to the Inquiry, subsequent developments are examined with a view to determining whether these would reverse the Sizewell decision. They are: the possible revision of radiation risk estimates upwards; whether cases of leukaemia occur with greater frequency around nuclear sites than elsewhere; publication of the Health and Safety Executive's consultative document ''The Tolerability of Risk from Nuclear Power Stations''. The overall conclusion is that these developments do not undermine the findings of the Sizewell ''B'' inquiry or the validity of the CEGB's safety criteria. (author)

Innovation research on the safety supervision system of nuclear and radiation safety in Jiangsu province

International Nuclear Information System (INIS)

Zhang Qihong; Lu Jigen; Zhang Ping; Wang Wanping; Dai Xia

2012-01-01

As the rapid development of nuclear technology, the safety supervision of nuclear and radiation becomes very important. The safety radiation frame system should be constructed, the safety super- vision ability for nuclear and radiation should be improved. How to implement effectively above mission should be a new subject of Provincial environmental protection department. Through investigating the innovation of nuclear and radiation supervision system, innovation of mechanism, innovation of capacity, innovation of informatization and so on, the provincial nuclear and radiation safety supervision model is proposed, and the safety framework of nuclear and radiation in Jiangsu is elementally established in the paper. (authors)

Health effects of radiation and the implications for radiation safety

International Nuclear Information System (INIS)

Gonzalez, A.J.; Anderer, J.

1991-01-01

In this Paper two elements of a multiphase analysis of radiation exposures in the living environment - the human health effects of ionizing radiation and the implications for radiation safety policy and practices - are presented. Part 1 draws together the current state of scientific knowledge and insight about the human health effects of radiation, describing these in terms of known cause-related deterministic effects and of the estimated incidence of stochastic effects as defined by biostatistics and biological models. The 1988 UNSCEAR report provides an authoritative basis for such an examination. Part 2 explores some of the major implications that the state-of-the-art of radiation biology has - or should have - for radiation safety policy and practices. (author)

Challenges in promoting radiation safety culture

International Nuclear Information System (INIS)

Mod Ali, Noriah

2008-01-01

Safety has quickly become an industry performance measure, and the emphasis on its reliability has always been part of a strategic commitment. This paper presents an approach taken by Malaysian Nuclear Agency (Nuclear Malaysia) and authority to develop and implement safety culture for industries that uses radioactive material and radiation sources. Maintaining and improving safety culture is a continuous process. There is a need to establish a program to measure, review and audit health and safety performance against predetermined standards. Proper safety audit will help to identify the non-compliance of safety culture as well as the deviation of management, individual and policy level commitment; review of radiation protection program and activities should be preceded. (author)

Probabilistic safety criteria at the safety function/system level

International Nuclear Information System (INIS)

1989-09-01

A Technical Committee Meeting was held in Vienna, Austria, from 26-30 January 1987. The objectives of the meeting were: to review the national developments of PSC at the level of safety functions/systems including future trends; to analyse basic principles, assumptions, and objectives; to compare numerical values and the rationale for choosing them; to compile the experience with use of such PSC; to analyse the role of uncertainties in particular regarding procedures for showing compliance. The general objective of establishing PSC at the level of safety functions/systems is to provide a pragmatic tool to evaluate plant safety which is placing emphasis on the prevention principle. Such criteria could thus lead to a better understanding of the importance to safety of the various functions which have to be performed to ensure the safety of the plant, and the engineering means of performing these functions. They would reflect the state-of-the-art in modern PSAs and could contribute to a balance in system design. This report, prepared by the participants of the meeting, reviews the current status and future trends in the field and should assist Member States in developing their national approaches. The draft of this document was also submitted to INSAG to be considered in its work to prepare a document on safety principles for nuclear power plants. Five papers presented at the meeting are also included in this publication. A separate abstract was prepared for each of these papers. Refs, figs and tabs

Radiation safety in nuclear medicine procedures

International Nuclear Information System (INIS)

Cho, Sang Geon; Kim, Ja Hae; Song, Ho Chun

2017-01-01

Since the nuclear disaster at the Fukushima Daiichi Nuclear Power Plant in 2011, radiation safety has become an important issue in nuclear medicine. Many structured guidelines or recommendations of various academic societies or international campaigns demonstrate important issues of radiation safety in nuclear medicine procedures. There are ongoing efforts to fulfill the basic principles of radiation protection in daily nuclear medicine practice. This article reviews important principles of radiation protection in nuclear medicine procedures. Useful references, important issues, future perspectives of the optimization of nuclear medicine procedures, and diagnostic reference level are also discussed

Radiation safety in nuclear medicine procedures

Energy Technology Data Exchange (ETDEWEB)

Cho, Sang Geon; Kim, Ja Hae; Song, Ho Chun [Dept. of Nuclear Medicine, Medical Radiation Safety Research Center, Chonnam National University Hospital, Gwangju (Korea, Republic of)

2017-03-15

Since the nuclear disaster at the Fukushima Daiichi Nuclear Power Plant in 2011, radiation safety has become an important issue in nuclear medicine. Many structured guidelines or recommendations of various academic societies or international campaigns demonstrate important issues of radiation safety in nuclear medicine procedures. There are ongoing efforts to fulfill the basic principles of radiation protection in daily nuclear medicine practice. This article reviews important principles of radiation protection in nuclear medicine procedures. Useful references, important issues, future perspectives of the optimization of nuclear medicine procedures, and diagnostic reference level are also discussed.

Explanation of diagnostic criteria for radiation thyroid diseases

International Nuclear Information System (INIS)

Liu Libo; Luo Yunxiao; Wang Jianfeng; Chen Dawei; Cheng Guanghui; Jin Yuke

2012-01-01

National occupational health standard-Diagnostic Criteria for Radiation Thyroid Diseases has been approved and issued by the Ministry of Health. Based on the extensive research of literature, this standard was enacted according to the relevant laws and regulations. It is mainly used for diagnosis of thyroid diseases caused by occupational radiation, and it also can serve as a guide to diagnose thyroid disease induced by medical radiation. To implement this standard, and to diagnose and treat the radiation thyroid diseases patient correctly and timely, the contents of this standard were interpreted in this article. (authors)

Radiation protection criteria in the long-range view

International Nuclear Information System (INIS)

Snihs, J.O.; Bergman, C.

1989-01-01

The report presents by way of introduction radiation protection criteria applied to radiological activities and to disposal of low-level and intermediate-level radioactive waste. In these cases it is primarily short-range views that are relevant, up to a few thousand years as a maximum. In the case of high-level wastes where the views may extend to more than hundreds of thousands years, there are not for the present any equally well stablished criteria. Based upon preliminary results from a Nordic team for criteria for high-level radioactive wastes, dose estimates in the long-range view and alternative assessment criteria are discussed. Proposals are also presented for 12 criteria that may be applicable. As the work is not yet finshed, the criteria are however merely preliminary

Radiation safety in welding and testing

International Nuclear Information System (INIS)

King, B.E.; Malaxos, M.; Hartley, B.M.

1985-01-01

There are a number of ways of achieving radiation safety in the workplace. The first is by engineering radiation safety into the equipment, providing shielded rooms and safety interlocks. The second is by following safe working procedures. The National Health and Medical Research Council's Code of practice for the control and safe handling of sealed radioactive sources used in industrial radiography (1968) sets out the standards which must be met by equipment to be used in industrial radiography

Preliminary radiation criteria and nuclear analysis for ETF

International Nuclear Information System (INIS)

Engholm, B.A.

1980-09-01

Preliminary biological and materials radiation dose criteria for the Engineering Test Facility are described and tabulated. In keeping with the ETF Mission Statement, a key biological dose criterion is a 24-hour shutdown dose rate of 2 mrem/hr on the surface of the outboard bulk shield. Materials dose criteria, which primarily govern the inboard shield design, include 10 9 rads exposure limit to epoxy insulation, 3 x 10 -4 dpa damage to the TF coil copper stabilizer, and a total nuclear heating rate of 5 kW in the inboard TF coils. Nuclear analysis performed during FY 80 was directed primarily at the inboard and outboard bulk shielding, and at radiation streaming in the neutral beam drift ducts. Inboard and outboard shield thicknesses to achieve the biological and materials radiation criteria are 75 cm inboard and 125 cm outboard, the configuration consisting of alternating layers of stainless steel and borated water. The outboard shield also includes a 5 cm layer of lead. NBI duct streaming analyses performed by ORNL and LASL will play a key role in the design of the duct and NBI shielding in FY 81. The NBI aluminum cryopanel nuclear heating rate during the heating cycle is about 1 milliwatt/cm 3 , which is far less than the permissible limit

Radiation protection and safety culture for cyclotron workers

International Nuclear Information System (INIS)

Gomaa, M.A.

1998-01-01

The main aim of the present study is to review radiation protection and safety culture measures to be applied to cyclotron workers. The radiation protection (measures are based on Basic Safety standards for the protection) of the health of workers and the general public against the dangers arising from ionizing radiation, while the safety culture are based on IAEA publications

Radiation safety requirements for radionuclide laboratories

International Nuclear Information System (INIS)

1993-01-01

In accordance with the section 26 of the Finnish Radiation Act (592/91) the safety requirements to be taken into account in planning laboratories and other premises, which affect safety in the use of radioactive materials, are confirmed by the Finnish Centre for Radiation and Nuclear Safety. The guide specifies the requirements for laboratories and storage rooms in which radioactive materials are used or stored as unsealed sources. There are also some general instructions concerning work procedures in a radionuclide laboratory

Criteria for radiological protection against exposure to natural radiation

International Nuclear Information System (INIS)

Cardenas Herrera, Juan

2012-01-01

Ionizing radiation includes natural radiation which has been part cosmic radiation. Radon in homes, irradiation, gamma, among others, they have also been part of ionizing radiation. The activities that have lead to natural radiation materials are: mining and processing of uranium, radio application and thorium, phosphate industry, mining and smelting of metals, oil and gas extraction, coal mining and power generation, rare earth industry and titanium, zirconium and ceramics, building materials, waste water purification. Therefore, different criteria for radiation protection have had to create against exposure to natural radiation. Distinct rules and regulations to control were created in that sense [es

Nonreactor nuclear facilities: standards and criteria guide

International Nuclear Information System (INIS)

Brynda, W.J.; Junker, L.; Karol, R.C.; Lobner, P.R.; Goldman, L.A.

1981-09-01

This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE Order 5480.1, Chapter V, Safety of Nuclear Facilities. The guidance and criteria provided are directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. These general guidelines may have limited applicability to subsurface facilities such as waste repositories. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines

Nonreactor nuclear facilities: Standards and criteria guide

International Nuclear Information System (INIS)

Brynda, W.J.; Scarlett, C.H.; Tanguay, G.E.; Lobner, P.R.

1986-09-01

This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE 5480.1A, Chapter V, ''Safety of Nuclear Facilities.'' The guidance and criteria provided is directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, conduct of operations, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines. 25 figs., 62 tabs

Radiation safety for the emergency situation of the power plant accident. Radiation safety in society and its education

International Nuclear Information System (INIS)

Kosako, Toshiso

2012-01-01

Great East Japan Earthquake and Tsunamis, and following Fukushima Daiichi Nuclear Power Accident brought about great impact on society in Japan. Accident analysis of inside reactor was studied by reactor physics or reactor engineering knowledge, while dissipation of a large amount of radioactive materials outside reactor facilities, and radiation and radioactivity effects on people by way of atmosphere, water and soil were dealt with radiation safety or radiation protection. Due to extremely low frequency and experience of an emergency, there occurred a great confusion in the response of electric power company concerned, relevant regulating competent authorities, local government and media, and related scholars and researchers, which caused great anxieties amount affected residents and people. This article described radiation safety in the society and its education. Referring to actual examples, how radiation safety or radiation protection knowledge should be dealt with emergency risk management in the society was discussed as well as problem of education related with nuclear power, radiation and prevention of disaster and fostering of personnel for relevant people. (T. Tanaka)

Radiation safety management system in a radioactive facility

International Nuclear Information System (INIS)

Amador, Zayda H.

2008-01-01

Full text: This paper illustrates the Cuban experience in implementing and promoting an effective radiation safety system for the Centre of Isotopes, the biggest radioactive facility of our country. Current management practice demands that an organization inculcate culture of safety in preventing radiation hazard. The aforementioned objectives of radiation protection can only be met when it is implemented and evaluated continuously. Commitment from the workforce to treat safety as a priority and the ability to turn a requirement into a practical language is also important to implement radiation safety policy efficiently. Maintaining and improving safety culture is a continuous process. There is a need to establish a program to measure, review and audit health and safety performance against predetermined standards. All those areas of the radiation protection program are considered (e.g. licensing and training of the staff, occupational exposure, authorization of the practices, control of the radioactive material, radiological occurrences, monitoring equipment, radioactive waste management, public exposure due to airborne effluents, audits and safety costs). A set of indicators designed to monitor key aspects of operational safety performance are used. Their trends over a period of time are analyzed with the modern information technologies, because this can provide an early warning to plant management for searching causes behind the observed changes. In addition to analyze the changes and trends, these indicators are compared against identified targets and goals to evaluate performance strengths and weaknesses. A structured and proper radiation self-auditing system is seen as a basic requirement to meet the current and future needs in sustainability of radiation safety. The integrated safety management system establishment has been identified as a goal and way for the continuous improvement. (author)

Integration of radiation and physical safety in large radiator facilities

International Nuclear Information System (INIS)

Lima, P.P.M.; Benedito, A.M.; Lima, C.M.A.; Silva, F.C.A. da

2017-01-01

Growing international concern about radioactive sources after the Sept. 11, 2001 event has led to a strengthening of physical safety. There is evidence that the illicit use of radioactive sources is a real possibility and may result in harmful radiological consequences for the population and the environment. In Brazil there are about 2000 medical, industrial and research facilities with radioactive sources, of which 400 are Category 1 and 2 classified by the - International Atomic Energy Agency - AIEA, where large irradiators occupy a prominent position due to the very high cobalt-60 activities. The radiological safety is well established in these facilities, due to the intense work of the authorities in the Country. In the paper the main aspects on radiological and physical safety applied in the large radiators are presented, in order to integrate both concepts for the benefit of the safety as a whole. The research showed that the items related to radiation safety are well defined, for example, the tests on the access control devices to the irradiation room. On the other hand, items related to physical security, such as effective control of access to the company, use of safety cameras throughout the company, are not yet fully incorporated. Integration of radiation and physical safety is fundamental for total safety. The elaboration of a Brazilian regulation on the subject is of extreme importance

Radiation Safety in Industrial Radiography. Specific Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2013-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography

Radiation Safety in Industrial Radiography. Specific Safety Guide (French Edition)

International Nuclear Information System (INIS)

2013-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in … shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography

Radiation Safety in Industrial Radiography. Specific Safety Guide (Arabic Edition)

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography.

WE-F-209-02: Radiation Safety Surveys of Linear Accelerators

International Nuclear Information System (INIS)

Martin, M.

2016-01-01

Over the past few years, numerous Accreditation Bodies, Regulatory Agencies, and State Regulations have implemented requirements for Radiation Safety Surveys following installation or modification to x-ray rooms. The objective of this session is to review best practices in performing radiation safety surveys for both Therapy and Diagnostic installations, as well as a review of appropriate survey instruments. This session will be appropriate for both therapy and imaging physicists who are looking to increase their working knowledge of radiation safety surveys. Learning Objectives: Identify Appropriate Survey Meters for Radiation Safety Surveys Develop best practices for Radiation Safety Surveys for Therapy units that include common areas of concern. Develop best practices for Radiation Safety Surveys of Diagnostic and Nuclear Medicine rooms. Identify acceptable dose levels and the factors that affect the calculations associated with performing Radiation Safety Surveys.

Nuclear Malaysia. Towards being a certification body for radiation safety auditors

International Nuclear Information System (INIS)

Nik Ali, Nik Arlina; Mudri, Nurul Huda; Mod Ali, Noriah

2012-01-01

Current management practice demands that an organisation inculcate safety culture in preventing radiation hazard. Radiation safety audit is known as a step in ensuring radiation safety compliance at all times. The purpose of Radiation Safety Auditing is to ensure that the radiation safety protection system is implemented in accordance to Malaysia Atomic Energy Licensing Act 1984, or Act 304, and International Standards. Competent radiation safety auditors are the main element that contributes to the effectiveness of the audit. To realise this need, Innovation Management Centre (IMC) is now in progress to be a certification body for safety auditor in collaboration with Nuclear Malaysia Training Centre (NMTC). NMTC will offer Radiation Safety Management Auditor (RSMA) course, which provide in depth knowledge and understanding on requirement on radiation safety audit that comply with the ISO/IEC 17024 General Requirements for Bodies Operating Certification Systems of Persons. Candidates who pass the exam will be certified as Radiation Safety Management Auditor, whose competency will be evaluated every three years. (author)

Investigation of radiation safety and safety culture of medical sanitation vocation in Suzhou

International Nuclear Information System (INIS)

Tang Bo; Tu Yu; Zhang Yin

2009-01-01

Objective: To investigate the construction of radiation safety and safety culture of medical sanitation vocation in Suzhou. Methods: All medical units registered in administration center of Suzhou were included. The above selected medical units were completely investigated, district and county under the same condition of quality control. Results: The radiation safety and safety culture are existing differences among different property and grade hospitals of medicai sanitation vocation in Suzhou. Conclusion: The construction of radiation safety and safety culture is generally occupying in good level in suhzou, but there are obvious differences among different property and grade hospitals. The main reason for the differences in the importance attached to by the hospital decision-making and department management officials as well as the staff personal. (authors)

Radiation shielding and safety design

Energy Technology Data Exchange (ETDEWEB)

Lee, Yong Ouk; Gil, C. S.; Cho, Y. S.; Kim, D. H.; Kim, H. I.; Kim, J. W.; Lee, C. W.; Kim, K. Y.; Kim, B. H. [KAERI, Daejeon (Korea, Republic of)

2011-07-15

A benchmarking for the test facility, evaluations of the prompt radiation fields, evaluation of the induced activities in the facility, and estimation of the radiological impact on the environment were performed in this study. and the radiation safety analysis report for nuclear licensing was written based on this study. In the benchmark calculation, the neutron spectra was measured in the 20 Mev test facility and the measurements were compared with the computational results to verify the calculation system. In the evaluation of the prompt radiation fields, the shielding design for 100 MeV target rooms, evaluations of the leakage doses from the accidents and skyshine analysis were performed. The evaluation of the induced activities were performed for the coolant, inside air, structural materials, soil and ground-water. At last, the radiation safety analysis report was written based on results from these studies

Research on crisis communication of nuclear and radiation safety

International Nuclear Information System (INIS)

Cao Yali; Zhang Ying

2013-01-01

Insufficient public cognition of nuclear and radiation safety and absence of effective method to handle crisis lead to common crisis events of nuclear and radiation safety, which brings about unfavorable impact on the sound development of nuclear energy exploring and application of nuclear technology. This paper, based on crisis communication theory, analyzed the effect of current situation on nuclear and radiation safety crisis, discussed how to handle crisis, and tried to explore the effective strategies for nuclear and radiation safety crisis handling. (authors)

Regulation on the organizatjon of radiation safety control bodies

International Nuclear Information System (INIS)

1975-01-01

This is a basic document on matters of structure, organization, objectives, rights, and responsibilities of agencies enforcing compliance with radiation safety standards set up in Bulgaria. Under Public Health Law and Ministerial Council Decree No. 117, the organization and management of radiation safety in Bulgaria is entrusted to the Ministry of Public Health (MPH). Within its agency, the State Sanitary Control, authorities specialized in the area of radiation safety are as follows: the Radiation Hygiene Division (RHD) of the MPH Hygiene-and Epidemiology Bureau (HEB); the Specialized Radiation Safety Inspectorate of the Research Institute of Radiobiology and Radiation Hygiene (RIRRH); the Radiation Hygiene Sections of country HEBs; and State sanitary Inspectors assigned to large establishments in the country. (G.G.)

The Australian radiation protection and Nuclear Safety Agency

International Nuclear Information System (INIS)

Macnab, D.; Burn, P.; Rubendra, R.

1998-01-01

The author talks about the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA), the new regulatory authority which will combine the existing resources of the Australian Radiation Laboratory and the Nuclear Safety Bureau. Most uses of radiation in Australia are regulated by State or Territory authorities, but there is presently no regulatory authority for Commonwealth uses of radiation. To provide for regulation of the radiation practices of the Commonwealth, the Australian Government has decided to establish the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) and a Bill has passed through the House of Representatives and will go to the Spring sitting of the Senate. The new agency will subsume the resources and functions of the Nuclear Safety Bureau and the Australian Radiation Laboratory, with additional functions including the regulation of radiation protection and nuclear safety of Commonwealth practices. Another function of ARPANSA will be the promotion of uniform regulatory requirements for radiation protection across Australia. This will be done by developing, in consultation with the States and Territories, radiation health policies and practices for adoption by the Commonwealth, States and Territories. ARPANSA will also provide research and services for radiation health, and in support of the regulatory and uniformity functions. The establishment of ARPANSA will ensure that the proposed replacement research reactor, the future low level radioactive waste repository and other Commonwealth nuclear facilities and radiation practices are subject to a regulatory regime which reflects the accumulated experience of the States and Territories and best international practice, and meets public expectations

Radiation safety aspects at Indus accelerator complex

International Nuclear Information System (INIS)

Marathe, R.G.

2011-01-01

Indus Accelerator Complex at Raja Ramanna Center for Advanced Technology houses two synchrotron radiation sources Indus-1 and Indus-2 that are being operated round-the-clock to cater to the needs of the research community. Indus-1 is a 450 MeV electron storage ring and Indus-2 is presently being operated with electrons stored at 2 GeV. Bremsstrahlung radiation and photo-neutrons form the major radiation environment in Indus Accelerator Complex. They are produced due to loss of electron-beam occurring at different stages of operation of various accelerators located in the complex. The synchrotron radiation (SR) also contributes as a potential hazard. In order to ensure safety of synchrotron radiation users and operation and maintenance staff working in the complex from this radiation, an elaborate radiation safety system is in place. The system comprises a Personnel Protection System (PPS) and a Radiation Monitoring System (RMS). The PPS includes zoning, radiation shielding, door interlocks, a search and scram system and machine operation trip-interlocks. The RMS consists of area radiation monitors and beam loss monitors, whose data is available online in the Indus control room. Historical data of radiation levels is also available for data analysis. Synchrotron radiation beamlines at Indus-2 are handled in a special manner owing to the possibility of exposure to synchrotron radiation. Shielding hutches with SR monitors are installed at each beamline of Indus-2. Health Physics Unit also carries out regular radiological surveillance for photons and neutrons during various modes of operation and data is logged shift wise. The operation staff is appropriately trained and qualified as per the recommendations of Atomic Energy Regulatory Board (AERB). Safety training is also imparted to the beamline users. Safe operation procedures and operation checklists are being followed strictly. A radiation instrument calibration facility is also being set-up at RRCAT. The radiation

Overview of physical safety of radiation sources in Brazil

International Nuclear Information System (INIS)

Lima, A.R.; Silva, F.C.A. da

2017-01-01

The threat of 'radiological terrorism' has been recognized worldwide after the event of September 11, 2001. Radioactive sources can be used for the development of DDR ('dirty bomb') devices. Studies show that the use of a DDR could cause health damage, psychosocial and economic and environmental damage. Brazil follows this worldwide concern, since it has a large medical-industrial park that uses radioactive sources. This paper presents an overview of the physical safety of radioactive sources in Brazil, based on the inventory of radiative facilities, regulatory aspects and international recommendations. For the preparation of the study, the database of radioactive sources of the regulatory body, the current normative status and the international recommendations were used. In Brazil there are approximately 2,500 radiative installations, with about 400 radioactive sources Category 1 and 2, which are the biggest concern in terms of physical safety. The Brazilian licensing standard addresses only some aspects of physical protection, not providing a clear orientation for the elaboration and implementation of physical protection systems, in accordance with international recommendations. For Brazil to be included in the world scenario of physical safety of radioactive sources, it is urgent to elaborate specific legislation with well-defined regulatory criteria. The lack of more detailed requirements makes it difficult to make a more careful regulatory assessment of the physical protection conditions of the facilities, either through the evaluation of plans and other physical protection documents or through regulatory inspections

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

International Nuclear Information System (INIS)

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

Criteria for onsite transfers of radioactive material

International Nuclear Information System (INIS)

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

1992-01-01

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

Interactive software automates personalized radiation safety plans for Na131I therapy.

Science.gov (United States)

Friedman, Marvin I; Ghesani, Munir

2002-11-01

NRC regulations have liberalized the criteria for release from control of patients administered radioactive materials but require written radiation safety instruction if another individual is expected to receive more than 1 mSv. This necessitates calculation of expected doses, even when the calculated maximum likely dose is well below the 5 mSv release criterion. NRC interpretations of the regulation provide the biokinetic model to be used to evaluate the release criterion for patients administered Na131I, but do not provide guidance as to either the specifics of minimizing the dose of others or the length of time restrictions should remain in effect. Interactive software has been developed to facilitate creation of radiation safety plans tailored to patients' expected interactions. Day-by-day and cumulative effective exposures at several separation distances, including sleeping, are presented in grid format in a graphic interface. In an interview session, the patient proposes daily contacts, which are entered separately for each individual by point-and-click operation. Total dose estimates are accumulated and modified while negotiating contact schedules, guided by suggested age-specific limits. The software produces printed radiation safety recommendations specific to the clinical, dosing, and social situations and reflective of the patient's choice of combinations of close contact with others. It has been used in treating more than 100 patients and has been found to be very useful and well received.

Radiation safety standards and regulations

International Nuclear Information System (INIS)

Ermolina, E.P.; Ivanov, S.I.

1993-01-01

Radiation protection laws of Russia concerning medical application of ionizing radiation are considered. Main concepts of the documents and recommendations are presented. Attention was paid to the ALARA principle, safety standrds for paietients, personnel and population, radiation protection. Specific feature of the standardization of radiation factors is the establishment of two classes of norms: main dose limits and permissible levels. Maximum dose commitment is the main standard. Three groups of critical organs and three categories of the persons exposed to radiation are stated. Main requirements for radiation protection are shown

10 CFR 34.42 - Radiation Safety Officer for industrial radiography.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Radiation Safety Officer for industrial radiography. 34.42 Section 34.42 Energy NUCLEAR REGULATORY COMMISSION LICENSES FOR INDUSTRIAL RADIOGRAPHY AND RADIATION... Radiation Safety Officer for industrial radiography. The RSO shall ensure that radiation safety activities...

Qualification criteria for persons responsible for radiation protection

International Nuclear Information System (INIS)

Wehner, G

1980-01-01

A survey of the qualification criteria included in the German atomic law (Atomic Energy Act, Radiological Protection Ordinance and X-ray Protection Ordinance) for persons responsible for radiation protection is given. Especially the various activities for which a health physics officer is required, the range of qualification in each case and the way the qualification has to be proved, are pointed out. Also the different guides that are issued to complete the legal requirements are mentioned. The definitions of the term qualification for health physics given in the different guides are cited and it is shown, that the qualification of a healt physics officer has to be based on the three criteria (I) vocational training. (II) professional experience and (III) the necessary knowledge in radiation protection. (orig./HP) [de

Criteria for guidance in the safety assessment of nuclear installations in the United Kingdom

International Nuclear Information System (INIS)

Gausden, R.; Fryer, D.R.H.

1977-01-01

There is an increasing appreciation of the need for a consistent approach to nuclear safety between various groups having an interest in safety and between various types of installation. Licensing for construction and ultimate approval to operate any nuclear installation depend in the United Kingdom upon a searching assessment of the design, construction and operation of the proposed plant. Criteria of the kind discussed in this paper have been used by the Nuclear Installations Inspectorate in this assessment process. From time to time they are subject to comments from other bodies in the U.K. One aim of the criteria is to set out the broad objectives that should be met regarding the magnitude of radiological consequences of accidents or normal operation. In addition, the criteria give guidance on the design philosophy for nuclear safety and the principles of fault evaluation. Criteria must be conceived so that while maintaining safety standards their application does not frustrate design and development. It is also important that undue formalism is not induced in the assessment process at the expense of inhibiting the judgement of safety assessors. A balance must, therefore, be struck between detailed and generalised guidance. It is also accepted that experience in the use and interpretation of criteria will indicate a need for improvement and additions: the criteria are, therefore, regarded as living rather than fixed statements which are expected to develop in response to any need for change in a safe direction that may arise. In developing them, the Inspectorate has drawn heavily upon the experience accumulated during its 16 years of operation and has also referred to criteria published by other organisations. The paper deals specifically with certain of the most important sections of the criteria and indicates the total range of subjects which need to be included in such criteria

Interface between radiation protection and nuclear safety

International Nuclear Information System (INIS)

Bengtsson, G.; Hoegberg, L.

1991-01-01

Interface issues concern the character and management of overlaps between radiation protection and nuclear safety in nuclear power plants. Typical examples include the selection of inspection and maintenance volumes in order to balance occupational radiation doses versus the safety status of the plant, and the intentional release to the environment in the course of an accident in order to secure better plant control. The paper discusses whether it is desirable and possible to employ a consistent management of interface issues with trade-offs between nuclear safety and radiation protection. Illustrative examples are quoted from a major Nordic research programme on risk analysis and safety rationale. These concern for instance in-service inspections, modifications of plant systems and constructions after the plant has been taken into operation, and studies on the limitations of probabilistic safety assessment. They indicate that in general there are no simple rules for such trade-offs

Argentine criteria on nuclear safety and emergencies: their impact on the Argos PHWR 380 design

International Nuclear Information System (INIS)

Gonzalez, A. J.

1988-01-01

This paper describes first the safety criteria of the Argentine regulatory authority with emphasis on the probabilistic safety criteria based on a limitation of individual risks. Then, it is presented a discussion on emergency criteria in relation to evacuation and relocation measures. Finally, the paper briefly describes the design of an Argentine offer for a safer heavy water reactor where these criteria are applied. 9 figs., 1 tab., 46 refs. (author)

Acceptance criteria for deposition of low-level and intermediate-level radiation levels radioactive wastes

International Nuclear Information System (INIS)

2002-09-01

This norm establishes the criteria for acceptance low and intermediate radiation level for safe deposition in repositories, for assuring the protection of workers, population and environment against the hazardous effects of the ionizing radiations. The criteria of this norm applies to the low and intermediate radiation levels

Radiation Safety Culture in Medicine AFROSAFE_R_A_D

International Nuclear Information System (INIS)

Nyabanda, R.

2017-01-01

Ionizing radiation that include X-rays and Gamma rays Radio waves, infrared and visible light carries sufficient energy to free electrons from atoms or molecules. Becquerel first person to discover evidence of radioactivity, who shared a Nobel Prize for physics in 1903 with Marie and Pierre Curie. Prof Sievert and Louis Harold Gray are the Medical physicists who had major contribution in the study of the biological effects of radiation. Ionizing radiation causes displacement of an electron which can inflict damage on DNA either directly or indirectly. A radiation-safety campaign developed by the radiation health workers in Africa. Radiosensitive organs is highest in cells which are highly mitotic or undifferentiated. E.g basal epidermis, bone marrow, thymus, gonads, and lens cells. Relatively low radiosensitivity in muscle, bones, and nervous system tissues. A radiation-safety campaign developed by the radiation health workers in Africa. AFROSAFE Strategies Strengthen radiation protection of patients, health workers and public, Promote safe and appropriate use of ionizing radiation in medicine. Foster improvement of the benefit-risk dialogue with patients and the public. Enhance the safety and quality of radiological procedures in medicine, Promote safety in radiological equipment and facilities and Promote research in radiation protection and safety

The radiation safety self-assessment program of Ontario Hydro

International Nuclear Information System (INIS)

Armitage, G.; Chase, W.J.

1987-01-01

Ontario Hydro has developed a self-assessment program to ensure that high quality in its radiation safety program is maintained. The self-assessment program has three major components: routine ongoing assessment, accident/incident investigation, and detailed assessments of particular radiation safety subsystems or of the total radiation safety program. The operation of each of these components is described

The radiation safety standards programme

International Nuclear Information System (INIS)

Bilbao, A.A.

2000-01-01

In this lecture the development of radiation safety standards by the IAEA which is a statutory function of the IAEA is presented. The latest editions of the basic safety standards published by the IAEA in cooperation with ICRP, FAO, ILO, NEA/OECD, PAHO and WHO are reviewed

radiation safety culture for developing country: Basis for s minimum operational radiation protection programme

International Nuclear Information System (INIS)

Rozental, J. J.

1997-01-01

The purpose of this document is to present a methodology for an integrated strategy aiming at establishing an adequate radiation Safety infrastructure for developing countries, non major power reactor programme. Its implementation will allow these countries, about 50% of the IAEA's Member States, to improve marginal radiation safety, specially to those recipients of technical assistance and do not meet the Minimum radiation Safety Requirements of the IAEA's Basic Safety Standards for radiation protection Progress in the implementation of safety regulations depends on the priority of the government and its understanding and conviction about the basic requirements for protection against the risks associated with exposure to ionizing radiation. There is no doubt to conclude that the reasons for the deficiency of sources control and dose limitation are related to the lack of an appropriate legal and regulatory framework, specially considering the establishment of an adequate legislation; A minimum legal infrastructure; A minimum operational radiation safety programme; Alternatives for a Point of Optimum Contact, to avoid overlap and conflict, that is: A 'Memorandum of Understanding' among Regulatory Authorities in the Country, dealing with similar type of licensing and inspection

Safety Analysis Report for Primary Capsule of Ir-192 Radiation Source

International Nuclear Information System (INIS)

Lee, J. C.; Bang, K. S.; Choi, W. S.; Seo, K. S.; Son, K. J.; Park, W. J.

2008-12-01

All of the source capsules to transport a special form radioactive material should be designed and fabricated in accordance with the design criteria prescribed in IAEA standards and domestic regulations. The objective of this project is to prove the safety of a primary capsule for Ir-192 radiation source which produced in the HANARO. The safety tests of primary capsules were carried out for the impact, percussion and heat conditions. And leakage tests were carried out before and after the each tests. The capsule showed slight scratches and their deformations were not found after each tests. It also met the allowable limits of leakage rate after each test. Therefore, it has been verified that the capsule was designed and fabricated to meet all requirements for the special form radioactive materials

Licensing procedures and safety criteria for research reactors in France

International Nuclear Information System (INIS)

Berry, J.L.; Lerouge, B.

1983-01-01

From the very beginning of the CEA up to now, a great deal of work has been devoted to the development and utilization of research reactors in France for the needs of fundamental and applied research, production of radioisotopes, and training. In recent years, new reactors were commissioned while others were decommissioned. Moreover some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors (Osiris and Isis). This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. At the end, a few considerations are given to the consequences of the Osiris core conversion. Safety of research reactors has been studied in detail and many improvements have been brought due to: implementation of a specific experimental program, and adaptation of safety principles and rules elaborated for power reactors. Research reactors in operation in France have been built within a 22 year period. Meanwhile, safety rules have been improved. Old reactors do not comply with all the new rules but modifications are continuously made: after analysis of incidents, when replacement of equipment has to be carried out, when an important modification (fuel conversion for example) is decided upon

Licensing procedures and safety criteria for research reactors in France

Energy Technology Data Exchange (ETDEWEB)

Berry, J L; Lerouge, B [Centre d' Etudes Nucleaires de Saclay (France)

1983-08-01

From the very beginning of the CEA up to now, a great deal of work has been devoted to the development and utilization of research reactors in France for the needs of fundamental and applied research, production of radioisotopes, and training. In recent years, new reactors were commissioned while others were decommissioned. Moreover some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors (Osiris and Isis). This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. At the end, a few considerations are given to the consequences of the Osiris core conversion. Safety of research reactors has been studied in detail and many improvements have been brought due to: implementation of a specific experimental program, and adaptation of safety principles and rules elaborated for power reactors. Research reactors in operation in France have been built within a 22 year period. Meanwhile, safety rules have been improved. Old reactors do not comply with all the new rules but modifications are continuously made: after analysis of incidents, when replacement of equipment has to be carried out, when an important modification (fuel conversion for example) is decided upon.

Recent trends in particle accelerator radiation safety

International Nuclear Information System (INIS)

Ohnesorge, W.F.; Butler, H.M.

1974-01-01

The use of particle accelerators in applied and research activities continues to expand, bringing new machines with higher energy and current capabilities which create radiation safety problems not commonly encountered before. An overview is given of these increased ionizing radiation hazards, along with a discussion of some of the new techniques required in evaluating and controlling them. A computer search of the literature provided a relatively comprehensive list of publications describing accelerator radiation safety problems and related subjects

LMFBR safety criteria and guidelines for consideration in the design of future plants

International Nuclear Information System (INIS)

1990-01-01

For many years the Commission of the European Communities has been conducting activities aimed at the progressive harmonization of safety requirements and criteria applied to nuclear installations in the Community. These activities cover thermal and fast reactors. This publication represents a major achievement in reaching this goal. The document, which has been prepared in the framework of activities of the CEC fast-reactor safety working group (SWG), consists of safety criteria and guidelines for fast reactors. It represents the common view of all EC Member States which have a fast-reactor programme or are interested in fast-reactor development. The criteria and guidelines are structured according to different types of possible faults, such as core reactivity faults, general cooling faults, subassembly faults, faults outside the core and causes external to the station. Only those events are considered which are in the design basis of current fast-reactor projects. Proposed measures or guidelines to satisfy the criteria are based on the present knowledge and proven technology

Safety criteria for siting a nuclear power plant

International Nuclear Information System (INIS)

2001-01-01

The guide sets forth requirements for safety of the population and the environment in nuclear power plant siting. It also sets out the general basis for procedures employed by other competent authorities when they issue regulations or grant licences. On request STUK (Radiation and Nuclear Safety Authority of Finland) issues case-specific statements about matters relating to planning and about other matters relating to land use in the environment of nuclear power plants

Measuring safety culture: Application of the Hospital Survey on Patient Safety Culture to radiation therapy departments worldwide.

Science.gov (United States)

Leonard, Sarah; O'Donovan, Anita

Minimizing errors and improving patient safety has gained prominence worldwide in high-risk disciplines such as radiation therapy. Patient safety culture has been identified as an important factor in reducing the incidence of adverse events and improving patient safety in the health care setting. The aim of distributing the Hospital Survey on Patient Safety Culture (HSPSC) to radiation therapy departments worldwide was to assess the current status of safety culture, identify areas for improvement and areas that excel, examine factors that influence safety culture, and raise staff awareness. The safety culture in radiation therapy departments worldwide was evaluated by distributing the HSPSC. A total of 266 participants were recruited from radiation therapy departments and included radiation oncologists, radiation therapists, physicists, and dosimetrists. The positive percent scores for the 12 dimensions of the HSPSC varied from 50% to 79%. The highest composite score among the 12 dimensions was teamwork within units; the lowest composite score was handoffs and transitions. The results indicated that health care professionals in radiation therapy departments felt positively toward patient safety. The HSPSC was successfully applied to radiation therapy departments and provided valuable insight into areas of potential improvement such as teamwork across units, staffing, and handoffs and transitions. Managers and policy makers in radiation therapy may use this assessment tool for focused improvement efforts toward patient safety culture. Copyright © 2017 American Society for Radiation Oncology. Published by Elsevier Inc. All rights reserved.

A proposal for an international convention on radiation safety

International Nuclear Information System (INIS)

Ahmed, J.U.

1998-01-01

One century has passed since harmful effects of radiation on living tissues were recognized. Organized efforts to reduce radiation hazards began in early 1920s. Major efforts by the ICRP since 1928, aided by ICRU, greatly helped in formulating principles, policies and guidance for radiation protection. The WHO formally recognized ICRP in 1956 and began implementing ICRP recommendations and guidance throughout the world. The IAEA, after it took office in 1957, began to establish or adopt standards of safety based on ICRP recommendations and provide for application of these standards in the field of atomic energy. Later on, other pertinent international organizations joined IAEA in establishing the Basic Safety Standards on radiation safety. The IAEA has issued, until now, nearly couple of hundred safety related documents on radiation safety and waste management. However, in spite of all such international efforts for three quarter of a century, there has been no effective universal control in radiation safety. Problems exist at the user, national, international and manufacturers and suppliers levels. Other problems are management of spent sources and smuggling of sources across international borders. Although, radiation and radionuclides are used by all countries of the world, regulatory and technical control measures in many countries are either lacking or inadequate. The recommendations and technical guidance provided by the international organizations are only advisory and carry no mandatory force to oblige countries to apply them. Member States approve IAEA safety standards and guides at the technical meetings and General Conference, but many of them do not apply these. An International Convention is, therefore, essential to establish international instrument to ensure universal application of radiation safety. (author)

A Study on Enhancement of Understanding of Radiation and Safety Management

Energy Technology Data Exchange (ETDEWEB)

Yoo, Dong Han; Park, Ji Young; Lee, Jae Uk; Bae, Jun Woo; Kim, Hee Reyoung [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

2014-10-15

Concerns for radiation exposure have been increased from small and big radiation works or experiments with radiation generator (RG) or radiation isotopes (RI) at institutions using radiation in Korea. Actually, due to radiation exposure occurred on the process of handling RI, etc., The exposure should be maintained as low as reasonably possible. To do this, above all, suitable training and establishment of safety culture have to be preceded. In this respect, an education institution is a place where people learn first about handling radiations in various specialties with purposes including academic research, and the first learned habits and practices acts as the basis for safety management of radiation when they continue to do radiation work after going into the society. Hereford, it is needed to establish the right safety culture on radiation for its safe managing. In the present study, the direction for the right understandings and safety improvement are suggested through the radiation survey on education institutions and preparation of safety guidances for users. The basic guidance at the radiation experiment was prepared for the right understanding of the radiation to prevent radiation accidents from careless handling by workers based on the surveyed results for education institutions. It is expected to be used as fundamentals for improvement for radiation safety management of workers and researchers and, further, safety policy for national nuclear energy and radiations.

A Study on Enhancement of Understanding of Radiation and Safety Management

International Nuclear Information System (INIS)

Yoo, Dong Han; Park, Ji Young; Lee, Jae Uk; Bae, Jun Woo; Kim, Hee Reyoung

2014-01-01

Concerns for radiation exposure have been increased from small and big radiation works or experiments with radiation generator (RG) or radiation isotopes (RI) at institutions using radiation in Korea. Actually, due to radiation exposure occurred on the process of handling RI, etc., The exposure should be maintained as low as reasonably possible. To do this, above all, suitable training and establishment of safety culture have to be preceded. In this respect, an education institution is a place where people learn first about handling radiations in various specialties with purposes including academic research, and the first learned habits and practices acts as the basis for safety management of radiation when they continue to do radiation work after going into the society. Hereford, it is needed to establish the right safety culture on radiation for its safe managing. In the present study, the direction for the right understandings and safety improvement are suggested through the radiation survey on education institutions and preparation of safety guidances for users. The basic guidance at the radiation experiment was prepared for the right understanding of the radiation to prevent radiation accidents from careless handling by workers based on the surveyed results for education institutions. It is expected to be used as fundamentals for improvement for radiation safety management of workers and researchers and, further, safety policy for national nuclear energy and radiations

A survey of radiation safety training among South African interventionalists

Directory of Open Access Journals (Sweden)

A Rose

2018-04-01

Full Text Available Background. Ionising radiation is increasingly being used in modern medicine for diagnostic, interventional and therapeutic purposes. There has been an improvement in technology, resulting in lower doses being emitted. However, an increase in the number of procedures has led to a greater cumulative dose for patients and operators, which places them at increased risk of the effects of ionising radiation. Radiation safety training is key to optimising medical practice.Objective. To present the perceptions of South African interventionalists on the radiation safety training they received and to offer insights into the importance of developing and promoting such training programmes for all interventionalists.Methods. In this cross-sectional study, we collected data from interventionalists (N=108 using a structured questionnaire.Results. All groups indicated that radiation exposure in the workplace is important (97.2%. Of the participants, the radiologists received the most training (65.7%. Some participants (44.1% thought that their radiation safety training was adequate. Most participants (95.4% indicated that radiation safety should be part of their training curriculum. Few (34.3% had received instruction on radiation safety when they commenced work. Only 62% had been trained on how to protect patients from ionising radiation exposure.Conclusion. Radiation safety training should be formalised in the curriculum of interventionalists’ training programmes, as this will assist in stimulating a culture of radiation protection, which in turn will improve patient safety and improve quality of care.

Generic radiation safety design for SSRL synchrotron radiation beamlines

Energy Technology Data Exchange (ETDEWEB)

Liu, James C. [Radiation Protection Department, Stanford Linear Accelerator Center (SLAC), MS 48, P.O. Box 20450, Stanford, CA 94309 (United States)]. E-mail: james@slac.stanford.edu; Fasso, Alberto [Radiation Protection Department, Stanford Linear Accelerator Center (SLAC), MS 48, P.O. Box 20450, Stanford, CA 94309 (United States); Khater, Hesham [Radiation Protection Department, Stanford Linear Accelerator Center (SLAC), MS 48, P.O. Box 20450, Stanford, CA 94309 (United States); Prinz, Alyssa [Radiation Protection Department, Stanford Linear Accelerator Center (SLAC), MS 48, P.O. Box 20450, Stanford, CA 94309 (United States); Rokni, Sayed [Radiation Protection Department, Stanford Linear Accelerator Center (SLAC), MS 48, P.O. Box 20450, Stanford, CA 94309 (United States)

2006-12-15

To allow for a conservative, simple, uniform, consistent, efficient radiation safety design for all SSRL beamlines, a generic approach has been developed, considering both synchrotron radiation (SR) and gas bremsstrahlung (GB) hazards. To develop the methodology and rules needed for generic beamline design, analytic models, the STAC8 code, and the FLUKA Monte Carlo code were used to pre-calculate sets of curves and tables that can be looked up for each beamline safety design. Conservative beam parameters and standard targets and geometries were used in the calculations. This paper presents the SPEAR3 beamline parameters that were considered in the design, the safety design considerations, and the main pre-calculated results that are needed for generic shielding design. In the end, the rules and practices for generic SSRL beamline design are summarized.

Radiation safety systems at the NSLS

International Nuclear Information System (INIS)

Dickinson, T.

1987-04-01

This report describes design principles that were used to establish the radiation safety systems at the National Synchrotron Light Source. The author described existing safety systems and the history of partial system failures. 1 fig

Safety guide data on radiation shielding in a reprocessing facility

International Nuclear Information System (INIS)

Sekiguchi, Noboru; Naito, Yoshitaka

1986-04-01

In a reprocessing facility, various radiation sources are handled and have many geometrical conditions. To aim drawing up a safety guidebook on radiation shielding in order to evaluate shielding safety in a reprocessing facility with high reliability and reasonableness, JAERI trusted investigation on safety evaluation techniques of radiation shielding in a reprocessing facility to Nuclear Safety Research Association. This report is the collection of investigation results, and describes concept of shielding safety design principle, radiation sources in reprocessing facility and estimation of its strength, techniques of shielding calculations, and definite examples of shielding calculation in reprocessing facility. (author)

Towards an international regime on radiation and nuclear safety

International Nuclear Information System (INIS)

Gonzalez, A.J.

2000-01-01

The 1990s have seen the de facto emergence of what might be called an 'international regime on nuclear and radiation safety'. It may be construed to encompass three key elements: legally binding international undertakings among States; globally agreed international safety standards; and provisions for facilitating the application of those standards. While nuclear and radiation safety are national responsibilities, governments have long been interested in formulating harmonised approaches to radiation and nuclear safety. A principal mechanism for achieving harmonisation has been the establishment of internationally agreed safety standards and the promotion of their global application. The development of nuclear and radiation safety standards is a statutory function of the IAEA, which is unique in the United Nations system. The IAEA Statute expressly authorises the Agency 'to establish standards of safety' and 'to provide for the application of these standards'. As the following articles and supplement in this edition of the IAEA Bulletin point out, facilitating international conventions; developing safety standards; and providing mechanisms for their application are high priorities for the IAEA. (author)

Postgraduate educational course in radiation protection and the safety of radiation sources. Standard syllabus

International Nuclear Information System (INIS)

2003-01-01

The aim of the Postgraduate Educational Course in Radiation Protection and the Safety of Radiation Sources is to meet the needs of professionals at graduate level, or the equivalent, for initial training to acquire a sound basis in radiation protection and the safety of radiation sources. The course also aims to provide the necessary basic tools for those who will become trainers in radiation protection and in the safe use of radiation sources in their countries. It is designed to provide both theoretical and practical training in the multidisciplinary scientific and/or technical bases of international recommendations and standards on radiation protection and their implementation. The participants should have had a formal education to a level equivalent to a university degree in the physical, chemical or life sciences or engineering and should have been selected to work in the field of radiation protection and the safe use of radiation sources in their countries. The present revision of the Standard Syllabus takes into account the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS), IAEA Safety Series No. 115 (1996) and recommendations of related Safety Guides, as well as experience gained from the Postgraduate Educational Course on Radiation Protection and Safety of Radiation Sources held in several regions in recent years. The general aim of the course, as mentioned, is the same. Some of the improvements in the present version are as follows: The learning objective of each part is specified. The prerequisites for each part are specified. The structure of the syllabus has been changed: the parts on Principles of Radiation Protection and on Regulatory Control were moved ahead of Dose Assessment and after Biological Effects of Radiation. The part on the interface with nuclear safety was dropped and a module on radiation protection in nuclear power plants has been included. A

Postgraduate educational course in radiation protection and the safety of radiation sources. Standard syllabus

International Nuclear Information System (INIS)

2002-01-01

The aim of the Postgraduate Educational Course in Radiation Protection and the Safety of Radiation Sources is to meet the needs of professionals at graduate level, or the equivalent, for initial training to acquire a sound basis in radiation protection and the safety of radiation sources. The course also aims to provide the necessary basic tools for those who will become trainers in radiation protection and in the safe use of radiation sources in their countries. It is designed to provide both theoretical and practical training in the multidisciplinary scientific and/or technical bases of international recommendations and standards on radiation protection and their implementation. The participants should have had a formal education to a level equivalent to a university degree in the physical, chemical or life sciences or engineering and should have been selected to work in the field of radiation protection and the safe use of radiation sources in their countries. The present revision of the Standard Syllabus takes into account the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS), IAEA Safety Series No. 115 (1996) and recommendations of related Safety Guides, as well as experience gained from the Postgraduate Educational Course on Radiation Protection and Safety of Radiation Sources held in several regions in recent years. The general aim of the course, as mentioned, is the same. Some of the improvements in the present version are as follows: The learning objective of each part is specified. The prerequisites for each part are specified. The structure of the syllabus has been changed: the parts on Principles of Radiation Protection and on Regulatory Control were moved ahead of Dose Assessment and after Biological Effects of Radiation. The part on the interface with nuclear safety was dropped and a module on radiation protection in nuclear power plants has been included. A

Report for spreading culture of medical radiation safety in Korea: Mainly the activities of the Korean alliance for radiation safety and culture in medicine (KARSM)

International Nuclear Information System (INIS)

Yoon, Yong Su; Kim, Jung Min; Kim, Ji Hyun; Choi, In Seok; Sung, Dong Wook; Do, Kyung Hyun; Jung, Seung Eun; Kim, Hyung Soo

2013-01-01

There are many concerns about radiation exposure in Korea after Fukushima Nuclear Plant Accident on 2011 in Japan. As some isotope materials are detected in Korea, people get worried about the radioactive material. In addition, the mass media create an air of anxiety that jump on the people’s fear instead of scientific approach. Therefore, for curbing this flow, health, medical institute from the world provide a variety of information about medical radiation safety and hold the campaign which can give people the image that medical radiation is safe. At this, the Korean Food and Drug Administration(KFDA) suggested that make the alliance of medical radiation safety and culture on August, 2011. Seven societies and institutions related medical radiation started to research and advertise the culture of medical radiation safety in Korea. In this report, mainly introduce the activities of the Korean Alliance for Radiation Safety and Culture in Medicine(KARSM) for spreading culture of medical radiation safety from 2011 to 2012

Report for spreading culture of medical radiation safety in Korea: Mainly the activities of the Korean alliance for radiation safety and culture in medicine (KARSM)

Energy Technology Data Exchange (ETDEWEB)

Yoon, Yong Su; Kim, Jung Min; Kim, Ji Hyun; Choi, In Seok [Dept. of Radiologic Science, Korea University, Seoul (Korea, Republic of); Sung, Dong Wook [Dept. of Radiology, Kyunghee University Hospital, Seoul (Korea, Republic of); Do, Kyung Hyun [Dept. of Radiology, University of Ulsan College of Medicine, Asan Medical Center, Seoul (Korea, Republic of); Jung, Seung Eun [Dept. of Radiology, College of Medicine, The Catholic University of Korea, Seoul (Korea, Republic of); Kim, Hyung Soo [Dept. of Radiation Safety, National Institute of Food and Drug Safety Evaluation, Korea Food and Drug Administration, Seoul (Korea, Republic of)

2013-09-15

There are many concerns about radiation exposure in Korea after Fukushima Nuclear Plant Accident on 2011 in Japan. As some isotope materials are detected in Korea, people get worried about the radioactive material. In addition, the mass media create an air of anxiety that jump on the people’s fear instead of scientific approach. Therefore, for curbing this flow, health, medical institute from the world provide a variety of information about medical radiation safety and hold the campaign which can give people the image that medical radiation is safe. At this, the Korean Food and Drug Administration(KFDA) suggested that make the alliance of medical radiation safety and culture on August, 2011. Seven societies and institutions related medical radiation started to research and advertise the culture of medical radiation safety in Korea. In this report, mainly introduce the activities of the Korean Alliance for Radiation Safety and Culture in Medicine(KARSM) for spreading culture of medical radiation safety from 2011 to 2012.

Radiation Safety System for SPIDER Neutral Beam Accelerator

International Nuclear Information System (INIS)

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

2011-01-01

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.

New Radiation Safety Standards of the Russian Federation

International Nuclear Information System (INIS)

Kutkov, V.A.

2001-01-01

Full text: The new Radiation Safety Standards of the Russian Federation are a first step in an implementation of the 1990 Recommendations of the ICRP into the existing national system of providing a radiation safety of the public. In new System the radiation source is examined as a source of harm and danger for the public. So the System shall include not only the measures for limitation of actual exposures, but also an assessment of efficiency of radiation protection in the practical activity, based on the analysis of a distribution of doses received and on the assessment of actions initiated to restrict the probability of potential exposures. The occupational and public exposure doses are only the indices of the quality of management of the source. In this System a radiation monitoring is a feedback for assessing the stability of the source and how it is controllable. It is a tool for predicting the levels of potential exposure and the relevant danger associated with the source. It is important to underline that the System of Providing a Radiation Safety is an interrelated system. None of its parts may be individually used. In particular, the mere conformity with dose limits is not yet a sufficient evidence of the successful operation of the safety system, because the normal exposure doses reflect only a source-related harm. The problems of implementation of this System of radiation protection and safety into the contemporary practice in the Russia is discussed. (author)

Radiation safety and regulatory aspects in Medical Facilities

International Nuclear Information System (INIS)

Banerjee, Sharmila

2017-01-01

Radiation safety and regulatory aspect of medical facilities are relevant in the context where radiation is used in providing healthcare to human patients. These include facilities, which carry out radiological procedures in diagnostic radiology, including dentistry, image-guided interventional procedures, nuclear medicine, and radiation therapy. The safety regulations provide recommendations and guidance on meeting the requirements for the safe use of radiation in medicine. The different safety aspects which come under its purview are the personnel involved in medical facilities where radiological procedures are performed which include the medical practitioners, radiation technologists, medical physicists, radiopharmacists, radiation protection and over and above all the patients. Regulatory aspects cover the guidelines provided by ethics committees, which regulate the administration of radioactive formulation in human patients. Nuclear medicine is a modality that utilizes radiopharmaceuticals either for diagnosis of physiological disorders related to anatomy, physiology and patho-physiology and for diagnosis and treatment of cancer

A National Institute of Radiation Protection and Nuclear Safety?

International Nuclear Information System (INIS)

Hartley, B.M.

1993-01-01

The practice of radiation protection within Australia is fragmented on a number of different levels. Each state has its own radiation protection organisation. Within the Commonwealth there is also a large number of bodies which deal with different aspects of radiation protection or nuclear safety. There is also an interest in occupational radiation protection by Departments responsible for Occupational Health and Safety. It is estimated that this fragmentation affects the practice of radiation protection at a State level and also the role which Australia can play internationally. The establishment of a National Institute of Radiation Protection and Nuclear Safety is therefore proposed. Possible structures and organizational arrangements for such an institute are discussed. 4 refs., 4 tabs., 3 figs

Challenges in strengthening radiation safety and security programme in Malaysia

International Nuclear Information System (INIS)

Noriah, M.A.

2010-01-01

This paper illustrates the Malaysian experience in implementing steps in strengthening radiation safety and security through certification of radiation safety personnel, which is dedicated to meet the current and future needs in sustainability of radiation safety and security systems. Commitment from the workforce to treat safety as a priority and the ability to turn a requirement into a practical language is also important in implementing the radiation safety policy efficiently. Through this effort, we are able to create a basis for adequate protection of workers, the public and the environment and encourage licensees to manage radiation safety and security based on performance, and not on compliance culture, with the final objective of professing a safety culture through self regulation. This will certainly benefit an organisation with ultimate goals are to continuously strive for a healthy, accident free and environmentally sound workplace and community, while providing the technical support needed to meet the national mission. This will strengthen the radiation safety and security programme and could be used to assist in manpower development once Malaysia makes the decision to embark on a nuclear power programme. (author)

INSAG's ongoing work on nuclear, radiation and waste safety

International Nuclear Information System (INIS)

Baer, A.J.

1999-01-01

The International Nuclear Safety Advisory Group (INSAG) is an advisory group to the Director General of the IAEA. It identifies current nuclear safety issues, draws conclusions from its analyses and gives advice on those issues. INSAG is currently working on four documents: a complete revision of INSAG-3, the classical paper on safety principles for nuclear plants, published in 1988; 'Safety Management', the effective system for the management of operational strategy; 'Safe Management of the Life Cycle of Nuclear Power Plants'; and the fourth document in preparation entitled 'The Safe Management of Sources of Radiation: Principles and Strategies'. The fourth document is aimed primarily at political decision makers who have no knowledge of radiation safety or of nuclear matters generally but are called upon to make important decisions in this field. INSAG has attempted to present them with a 'unified doctrine' of the management of all radiation sources, even though, for historical reasons radiation protection and nuclear safety have evolved largely independently of each other. The major conclusion to be drawn from the paper is that a systematic application of protection and safety principles, and of appropriate strategies, goes a long way towards ensuring the safe management of technologies involving radiation. Furthermore, the management of sources of radiation could benefit from the experience accumulated in other industries facing comparable challenges

The practice of safety culture construction in radiation processing enterprise

International Nuclear Information System (INIS)

Kong Xiangshan; Zhang Yue; Yang Bin; Xu Tao; Liu Wei; Hao Jiangang

2014-01-01

Security is an integral part of the process of business operations. The radiation processing enterprises due to their own particularity, more need to focus on the operation of the safety factors, the construction of corporate safety culture is of great significance in guiding carry out the work of the Radiation Protection. Radiation processing enterprises should proceed from their own characteristics, the common attitude of security systems and security construction, and constantly improved to ensure the personal safety of radiation workers in the area of safety performance. (authors)

Radiation protection and safety in industrial radiography

International Nuclear Information System (INIS)

1999-01-01

The use of ionizing radiation, particularly in medicine and industry, is growing throughout the world, with further expansion likely as technical developments result from research. One of the longest established applications of ionizing radiation is industrial radiography, which uses both X radiation and gamma radiation to investigate the integrity of equipment and structures. Industrial radiography is widespread in almost all Member States. It is indispensable to the quality assurance required in modern engineering practice and features in the work of multinational companies and small businesses alike. Industrial radiography is extremely versatile. The equipment required is relatively inexpensive and simple to operate. It may be highly portable and capable of being operated by a single worker in a wide range of different conditions, such as at remote construction sites, offshore locations and cross-country pipelines as well as in complex fabrication facilities. The associated hazards demand that safe working practices be developed in order to minimize the potential exposure of radiographers and other persons who may be in the vicinity of the work. The use of shielded enclosures (fixed facilities), with effective safety devices, significantly reduces any radiation exposures arising from the work. This Safety Report summarizes good and current state of the art practices in industrial radiography and provides technical advice on radiation protection and safety. It contains information for Regulatory Authorities, operating organizations, workers, equipment manufacturers and client organizations, with the intention of explaining their responsibilities and means to enhance radiation protection and safety in industrial radiography

Survey and analysis of radiation safety management systems at medical institutions. Initial report. Radiation protection supervisor, radiation safety organization, and education and training

International Nuclear Information System (INIS)

Ohba, Hisateru; Ogasawara, Katsuhiko; Aburano, Tamio

2005-01-01

In this study, a questionnaire survey was carried out to determine the actual situation of radiation safety management systems in Japanese medical institutions with nuclear medicine facilities. The questionnaire consisted of questions concerning the Radiation Protection Supervisor license, safety management organizations, and problems related to education and training in safety management. Analysis was conducted according to region, type of establishment, and number of beds. The overall response rate was 60%, and no significant difference in response rate was found among regions. Medical institutions that performed nuclear medicine practices without a radiologist participating accounted for 10% of the total. Medical institutions where nurses gave patients intravenous injections of radiopharmaceuticals as part of the nuclear medicine practices accounted for 28% of the total. Of these medical institutions, 59% provided education and training in safety management for nurses. The rate of acquisition of Radiation Protection Supervisor licenses was approximately 70% for radiological technologists and approximately 20% for physicians (regional difference, p=0.02). The rate of medical institutions with safety management organizations was 71% of the total. Among the medical institutions (n=208) without safety management organizations, approximately 56% had 300 beds or fewer. In addition, it became clear that 35% of quasi-public organizations and 44% of private organizations did not provide education and training in safety management (p<0.001, according to establishment). (author)

The international standard for protection from ionizing radiation and safety of radiation sources

Energy Technology Data Exchange (ETDEWEB)

Schlesinger, T [Israel Atomic Energy Commission, Yavne (Israel). Soreq Nuclear Research Center

1995-06-01

This document is a review in hebrew of the new 1994 international standard of the IAEA. The new standard title is `Basic safety standards for radiation protection and for the safety of radiation sources`, which were published in the ICRP Pub. 9.

Radiation safety and radiation protection problems on the TESLA Accelerator Installation

International Nuclear Information System (INIS)

Pavlovic, R.; Pavlovic, S.; Orlic, M.

1997-01-01

As we can see from the examples of many accelerator facilities installed throughout the world with ion beam energy, mass and charge characteristics and design similar to the TESLA Accelerator Installation, there is a great diversity among them, and each radiation protection and safety programme must be designed to facilitate the safe and effective operation of the accelerator according to the needs of the operating installation. Although there is no standard radiation protection and safety organization suitable for all institutions, experience suggests some general principles that should be integrated with all the disciplines involved in a comprehensive safety programme. (author)

Radiation safety and protection on the nuclear power plants

International Nuclear Information System (INIS)

Nosovskij, A.V.; Bogorad, V.I.; Vasil'chenko, V.N.; Klyuchnikov, A.A.; Litvinskaya, T.V.; Slepchenko, A.Yu.

2008-01-01

The main issues of the radiation safety and protection provision on the nuclear power plants are considered in this monograph. The description of the basic sources of the radiation danger on NPPs, the principles, the methods and the means of the safety and radiation monitoring provision are shown. The special attention is paid to the issues of the ionizing radiation regulation

Nuclear safety and radiation protection in France in 2011

International Nuclear Information System (INIS)

2012-01-01

The first part of this voluminous report describe the different ASN (Nuclear Safety Authority) actions: nuclear activities (ionising radiation and health and environmental risks), principles and stakeholders in nuclear safety regulation, radiation protection and protection of the environment, regulation, regulation of nuclear activities and exposure to ionizing radiation, radiological emergencies, public information and transparency, international relations. It also gives an overview of nuclear safety and radiation protection activities in the different French regions. The second part addresses activities regulated by the ASN: medical uses of ionizing radiation, non-medical uses of ionizing radiation, transport of radioactive materials, nuclear power plants, nuclear fuel cycle installations, nuclear research facilities and various nuclear installations, safe decommissioning of basic nuclear installations, radioactive waste and contaminated sites and soils

Education of radiation safety specialists at Faculty of Medicine of Vilnius University

International Nuclear Information System (INIS)

Urbelis, A.; Surkiene, G.

2004-01-01

Vilnius University is the first institution of higher education in Lithuania that began to teach students on radiation safety. The special course of radiation hygiene was delivered to students in 1962-1992. In 1992 it was introduced residency of radiation hygiene and graduated students qualified for title of radiation hygiene specialist. The residency lasted one year and included six cycles: fundamentals of nuclear physics, statistics and noninfectious epidemiology, radiobiology, radiological research methods, controls of radiation safety and hygienic analysis of radiation safety. From 1994 Vilnius University has been educating and training professionals of public health. The specialists of radiation safety aren't been training as isolated branch. All courses is divided into two parts. The first one is included into bachelor, the second part - into master study. The bachelor study consists of 2 credits (16 hours for lectures and 32 hours for practical studies). The future bachelors study introduction of radiation safety, elements of nuclear physics, dose limit values, fundamentals of radiological protection, natural radiation. The master study consists of 2 credits (8 hours for lectures and 48 hours for practical studies). The future masters study specific problems of radiation safety in medicine and industry, the safety problems of nuclear power - stations, the problems of radioactive wastes, radiation biology, radiation risk. Radiation safety study model in Faculty of medicine of Vilnius University differs from study model in most European countries as it makes great play of radiation safety while usual model includes radiation safety as insignificant part of environmental health. (author)

Progress report: 1996 Radiation Safety Systems Division

International Nuclear Information System (INIS)

Bhagwat, A.M.; Sharma, D.N.; Abani, M.C.; Mehta, S.K.

1997-01-01

The activities of Radiation Safety Systems Division include (i) development of specialised monitoring systems and radiation safety information network, (ii) radiation hazards control at the nuclear fuel cycle facilities, the radioisotope programmes at Bhabha Atomic Research Centre (BARC) and for the accelerators programme at BARC and Centre for Advanced Technology (CAT), Indore. The systems on which development and upgradation work was carried out during the year included aerial gamma spectrometer, automated environment monitor using railway network, radioisotope package monitor and air monitors for tritium and alpha active aerosols. Other R and D efforts at the division included assessment of risk for radiation exposures and evaluation of ICRP 60 recommendations in the Indian context, shielding evaluation and dosimetry for the new upcoming accelerator facilities and solid state nuclear track detector techniques for neutron measurements. The expertise of the divisional members was provided for 36 safety committees of BARC and Atomic Energy Regulatory Board (AERB). Twenty three publications were brought out during the year 1996. (author)

Radiation safety in nuclear industry in retrospect and perspective

International Nuclear Information System (INIS)

Pan Ziqiang

1993-01-01

More than 30 years have passed since the starting up of nuclear industry in China from the early 1950's. Over the past 30-odd years, nuclear industry has always kept a good record in China thanks to the policy of 'quality first, safety first' clearly put forward for nuclear industry from the outset and a lot of suitable effective measures taken over that period. Internationally, there is rapid progress in radiation protection and nuclear safety (hereafter refereed to as radiation safety) and a number of new concepts in the field of radiation protection have been advanced. Nuclear industry is developing based on the international standardization. To ensure the further development of nuclear utility, radiation safety needs to be further strengthened

Towards a radiation safety culture at Universidad Nacional de Colombia

International Nuclear Information System (INIS)

Poveda, Jairo F.; Munera, Hector A.

2008-01-01

Full text: During the 20th century, nuclear and radiation techniques for research, teaching, and medical and engineering practice slowly appeared at the National University of Colombia, mainly at the Bogota, Medellin and Manizales branches. Each individual laboratory or researcher obtained the license for the use of the radioactive source, or radiation emitting apparatus. However, the University as a whole does not have as yet a Radiation Safety Manual, nor an inventory of laboratories using radiation. From the viewpoint of radiation safety and culture, this situation is undesirable, and may easily lead to inappropriate waste management practices, including the possibility of orphan sources (one such source has been already found). As part of the program of environmental management of dangerous wastes promoted by the National Division of Laboratories of our University, an office of radiation safety was created in the year 2006. This paper describes the situation that was found, the activities that have been carried out, some of the difficulties that we have met, and the plans that we have to help shape a safety culture at our institution. Currently we are pursuing an inventory of laboratories using radioactive sources and radiation emitting apparatuses, starting with the branches in Bogota and Manizales which are perceived as the most urgent to deal with. Fortunately, the branch in Medellin has been for about a decade under the care of a former radiation safety officer of our national Institute of Nuclear Affairs, who presently teaches there. During 2006 and 2007, 13 laboratories using radioactive sources were visited in the Bogota branch. Safety procedures and waste handling protocols were checked, safety manuals prepared and/or revised, and recommendations for safety culture provided. During 2008 we will visit Manizales, and will continue visiting a number of X-ray machines used in the Bogota branch for engineering, veterinary, and diagnostic, and surgery medical

Radiation safety and inventory of sealed radiation sources in Pakistan

International Nuclear Information System (INIS)

Ali, M.; Mannan, A.

2001-01-01

Sealed radiation sources (SRS) of various types and activities are widely used in industry, medicine, agriculture, research and teaching in Pakistan. The proper maintenance of records of SRS is mandatory for users/licensees. Since 1956, more than 2000 radiation sources of different isotopes having activities of Bq to TBq have been imported. Of these, several hundred sources have been disposed of and some have been exported/returned to the suppliers. To ensure the safety and security of the sources and to control and regulate the safe use of radiation sources in various disciplines, the Directorate of Nuclear Safety and Radiation Protection (DNSRP), the implementing arm of the regulatory authority in the country, has introduced a system for notifying, registering and licensing the use of all types of SRS. In order to update the inventory of SRS used throughout the country, the DNSRP has developed a database. (author)

Radiation safety and control

International Nuclear Information System (INIS)

Kim, Jang Hee; Kim, Gi Sub.

1996-12-01

The principal objective of radiological safety control is intended for achievement and maintenance of appropriately safe condition in environmental control for activities involving exposure from the use of radiation. In order to establish these objective, we should be to prevent deterministic effects and to limit the occurrence stochastic effects to level deemed to be acceptable by the application of general principles of radiation protection and systems of dose limitation based on ICRP recommendations. (author). 22 tabs., 13 figs., 11 refs

Ordinance on the Implementation of Atomic Safety and Radiation Protection

International Nuclear Information System (INIS)

1984-01-01

In execution of the new Atomic Energy Act the Ordinance on the Implementation of Atomic Safety and Radiation Protection was put into force on 1 February 1985. It takes into account all forms of peaceful nuclear energy and ionizing radiation uses in nuclear installations, irradiation facilities and devices in research, industries, and health services, and in radioactive isotope production and laboratories. It covers all aspects of safety and protection and defines atomic safety as nuclear safety and nuclear safeguards and physical protection of nuclear materials and facilities, whereas radiation protection includes the total of requirements, measures, means and methods necessary to protect man and the environment from the detrimental effects of ionizing radiation. It has been based on ICRP Recommendation No. 26 and the IAEA's Basic Safety Standards and supersedes the Radiation Protection Ordinance of 1969

Efficacy of a radiation safety education initiative in reducing radiation exposure in the pediatric IR suite

International Nuclear Information System (INIS)

Sheyn, David D.; Racadio, John M.; Patel, Manish N.; Racadio, Judy M.; Johnson, Neil D.; Ying, Jun

2008-01-01

The use of ionizing radiation is essential for diagnostic and therapeutic imaging in the interventional radiology (IR) suite. As the complexity of procedures increases, radiation exposure risk increases. We believed that reinforcing staff education and awareness would help optimize radiation safety. To evaluate the effect of a radiation safety education initiative on IR staff radiation safety practices and patient radiation exposure. After each fluoroscopic procedure performed in the IR suite during a 4-month period, dose-area product (DAP), fluoroscopy time, and use of shielding equipment (leaded eyeglasses and hanging lead shield) by IR physicians were recorded. A lecture and article were then given to IR physicians and technologists that reviewed ALARA principles for optimizing radiation dose. During the following 4 months, those same parameters were recorded after each procedure. Before education 432 procedures were performed and after education 616 procedures were performed. Physician use of leaded eyeglasses and hanging shield increased significantly after education. DAP and fluoroscopy time decreased significantly for uncomplicated peripherally inserted central catheters (PICC) procedures and non-PICC procedures after education, but did not change for complicated PICC procedures. Staff radiation safety education can improve IR radiation safety practices and thus decrease exposure to radiation of both staff and patients. (orig.)

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

International Nuclear Information System (INIS)

Almen, A.; Lundh, C.

2015-01-01

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. (authors)

A critical overview of safety-related and technological criteria for nuclear fuel

International Nuclear Information System (INIS)

Lahodova, M.; Valach, M.

2000-10-01

A detailed overview of the safety criteria, methods of analysis and computer codes used in OECD countries is presented. A critical analysis of the validity of criteria in the high burnup domain was performed, and recommendations for testing their validity based on available experimental data are put forth. (author)

Radiation protection aspects of design for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the Contracting Parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

The safety of radiation sources and radioactive materials in China

International Nuclear Information System (INIS)

Liu, H.

2001-01-01

The report describes the present infrastructure for the safety of radiation sources in China, where applications of radiation sources have become more and more widespread in the past years. In particular, it refers to the main functions of the National Nuclear Safety Administration of the State Environmental Protection Administration (SEPA), which is acting as the regulatory body for nuclear and radiation safety at nuclear installations, the Ministry of Public Health which issues licences for the use of radiation sources, and the Ministry of Public Security, which deals with the security of radiation sources. The report also refers to the main requirements of the existing regulatory system for radiation safety, i.e. the basic dose limits for radiation workers and the public, the licensing system for nuclear installations and for radioisotope-based and other irradiation devices, and the environmental impact assessment system. Information on the nationwide survey of radiation sources carried out by SEPA in 1991 is provided, and on some accidents that occurred in China due to loss of control of radiation sources and errors in the operation of irradiation facilities. (author)

Safety of natural radiation exposure. A meta-analysis of epidemiological studies on natural radiation

International Nuclear Information System (INIS)

Osaki, S.

2000-01-01

People have been exposed every time and everywhere to natural radiation and ''intuitively'' know the safety of this radiation exposure. On the other hand the theory of no threshold value on radiological carcinogenesis is known widely, and many people feel danger with even a smallest dose of radiation exposure. The safety of natural radiation exposure can be used for the risk communication with the public. For this communication, the safety of natural radiation exposure should be proved ''scientifically''. Safety is often discussed scientifically as the risks of the mortality from many practices, and the absolute risks of safe practices on the public are 1E-5 to 1E-6. The risks based on the difference of natural radiation exposure on carcinogenesis have been analyzed by epidemiological studies. Much of the epidemiological studies have been focused on the relationship between radiation doses and cancer mortalities, and their results have been described as relative risks or correlation factors. In respect to the safety, however, absolute risks are necessary for the discussion. Cancer mortalities depend not only on radiation exposure, but also on ethnic groups, sexes, ages, social classes, foods, smoking, environmental chemicals, medical radiation, etc. In order to control these confounding factors, the data are collected from restricted groups or/and localities, but any these ecological studies can not perfectly compensate the confounding factors. So positive or negative values of relative risks or the meaningful correlation factors can not be confirmed that their values are derived originally from the difference of their exposure doses. The absolute risks on these epidemiological studies are also affected by many factors containing radiation exposure. The absolute risk or the upper value of the confidence limit obtained from the epidemiological study which is well regulated confounding factors is possible to be a maximum risk on the difference of the exposure doses

Nuclear Safety Bureau: safety objectives and principles for the proposed ANSTO reactor

International Nuclear Information System (INIS)

Westall, D.

1993-01-01

Siting criteria and safety assessment principles were previously promulgated by the Australian Atomic Energy Commission (AAEC), and have been applied by ANSTO and the Nuclear Safety Bureau (NSB). The NSB is revising these criteria and principles to take account of evolving nuclear safety standards and practices. The NSB Safety and Siting Assessment Principles (SSAP) are presented and it is estimated that it will provide a comprehensive basis for the safety assessment of research reactors in Australia, and be applicable to all stages of a reactor project: siting: design and construction; operation; modification; and decommissioning. The SSAP are similar to the principles promulgated by the AAEC, in that probabilistic safety criteria are set for assessment of design, however these criteria are complimentary to a deterministic design basis approach. This is a similar approach to that recently published by the UK Nuclear Installations Inspectorate 4 . Siting principles are now also included, where they were previously separate, and require a consideration of the consequences of severe accidents which are an extension of accidents catered for by the design of the plant. Criteria for radiation doses due to normal operations and design basis accidents are included in the principles for safety assessment. 9 refs

Australian Radiation Protection and Nuclear Safety Act 1998. Act No 133

International Nuclear Information System (INIS)

1999-01-01

A set of legislation consisting of three Acts in the field of radiation protection and nuclear safety was passed by both Houses of Parliament on 10 December 1998 and was proclaimed on 5 February 1999. Act No. 133 - Australian Radiation Protection and Nuclear Safety Act, which is a framework Law, established the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) as the regulatory body for radiation protection and nuclear safety, in place of the Nuclear Safety Bureau. The Chief Executive Officer of ARPANSA, who is appointed by the Governor-General for a term of up to 5 years, is obliged to submit annual and quarterly reports to the Minister on the operations of the Chief Executive Officer, ARPANSA, the Council, the Radiation Health Committee and the Nuclear Safety Committee. The Council is a consultative body which examines issues relating to radiation protection and nuclear safety and advises the Chief Executive Officer on these issues as well as on the adoption of recommendations, policies and codes. The Radiation Health Committee and the Nuclear Safety Committee are to be established as advisory committees to the Chief Executive Officer or the Council. Both committees should draft national policies, codes and standards in their respective fields and review their effectiveness periodically. The second in this series of legislation, Act No. 134, Australian Radiation Protection and Nuclear Safety (License Charges) Act requires holders of both facility and source licenses to pay an annual charge, to be prescribed by the regulations. The third, Act No. 135 , Australian Radiation Protection and Nuclear Safety (Consequential Amendments) Act repeals those provisions of the 1987 Australian Nuclear Science and Technology Organisation Act which concern the Nuclear Safety Bureau, and the 1978 Environment Protection Act as a whole

Australian Radiation Protection and Nuclear Safety Act 1998. Act No 133

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-11-01

A set of legislation consisting of three Acts in the field of radiation protection and nuclear safety was passed by both Houses of Parliament on 10 December 1998 and was proclaimed on 5 February 1999. Act No. 133 - Australian Radiation Protection and Nuclear Safety Act, which is a framework Law, established the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) as the regulatory body for radiation protection and nuclear safety, in place of the Nuclear Safety Bureau. The Chief Executive Officer of ARPANSA, who is appointed by the Governor-General for a term of up to 5 years, is obliged to submit annual and quarterly reports to the Minister on the operations of the Chief Executive Officer, ARPANSA, the Council, the Radiation Health Committee and the Nuclear Safety Committee. The Council is a consultative body which examines issues relating to radiation protection and nuclear safety and advises the Chief Executive Officer on these issues as well as on the adoption of recommendations, policies and codes. The Radiation Health Committee and the Nuclear Safety Committee are to be established as advisory committees to the Chief Executive Officer or the Council. Both committees should draft national policies, codes and standards in their respective fields and review their effectiveness periodically. The second in this series of legislation, Act No. 134, Australian Radiation Protection and Nuclear Safety (License Charges) Act requires holders of both facility and source licenses to pay an annual charge, to be prescribed by the regulations. The third, Act No. 135 , Australian Radiation Protection and Nuclear Safety (Consequential Amendments) Act repeals those provisions of the 1987 Australian Nuclear Science and Technology Organisation Act which concern the Nuclear Safety Bureau, and the 1978 Environment Protection Act as a whole

Ionising radiation safety training in the Australian Defence Organisation (ADO)

International Nuclear Information System (INIS)

Jenks, G.J.; O'Donovan, E.J.B.; Wood, W.B.

1998-01-01

Training personnel in ionising radiation safety within the Australian Defence Organisation (ADO) requires addressing some unique features of an organisation employing both military and civilian personnel. Activities may include those of a civil nature (such as industrial and medical radiography), specific military requirements (for training and emergency response) and scientific research and development. Some personnel may be assigned to full-time duties associated with radiation. However, most are designated as radiation protection officers as a secondary duty. A further complication is that most military personnel are subjected to postings at regular intervals. The ADO's Directorate of Defence Occupational Health and Safety has established an Ionising Radiation Safety Subcommittee to monitor not only the adequacy of the internal Ionising Radiation Safety Manual but also the training requirements. A Training Course, responding to these requirements, has been developed to emphasize, basic radiation theory and protection, operation of radiation monitors available in the ADO, an understanding of the Ionising Radiation Safety Manual, day-to-day radiation safety in units and establishments, and appropriate responses to radiation accidents and emergencies. In addition, students are briefed on a limited number of peripheral topics and participate in some site visits. Currently, two Courses are held annually, each with about twenty students. Most of the material is presented by ADO personnel with external contractor support. The three Courses held to date have proved successful, both for the students and the ADO generally. To seek national accreditation of the course through the Australian National Training Authority, as a first step, competency standards have been proposed. (authors)

Radiation Protection, Safety and Security Issues in Ghana.

Science.gov (United States)

Boadu, Mary; Emi-Reynolds, Geoffrey; Amoako, Joseph Kwabena; Akrobortu, Emmanuel; Hasford, Francis

2016-11-01

Although the use of radioisotopes in Ghana began in 1952, the Radiation Protection Board of Ghana was established in 1993 and served as the national competent authority for authorization and inspection of practices and activities involving radiation sources until 2015. The law has been superseded by an Act of Parliament, Act 895 of 2015, mandating the Nuclear Regulatory Authority of Ghana to take charge of the regulation of radiation sources and their applications. The Radiation Protection Institute in Ghana provided technical support to the regulatory authority. Regulatory and service activities that were undertaken by the Institute include issuance of permits for handling of a radiation sources, authorization and inspection of radiation sources, radiation safety assessment, safety assessment of cellular signal towers, and calibration of radiation-emitting equipment. Practices and activities involving application of radiation are brought under regulatory control in the country through supervision by the national competent authority.

Radiation protection and safety aspects in the use of radiation in medicine, industry and research

International Nuclear Information System (INIS)

Bhatt, B.C.

1998-01-01

While ionizing radiations have significant and indispensable uses in several fields, it must be borne in mind that it may be harmful to the radiation workers and public if used indiscriminately and without due caution. Radiation doses received by these individuals should be kept well within the recommended limits through good work practices. It is therefore necessary to ensure safety of radiation workers, patients undergoing radiation diagnosis and treatment, public and environment so that maximum benefit is derived from the use of radiation with minimum and acceptable risk. General principles of radiation protection and safety in various applications of radiations are discussed

Radiation safety research information database

International Nuclear Information System (INIS)

Yukawa, Masae; Miyamoto, Kiriko; Takeda, Hiroshi; Kuroda, Noriko; Yamamoto, Kazuhiko

2004-01-01

National Institute of Radiological Sciences in Japan began to construct Radiation Safety Research Information Database' in 2001. The research information database is of great service to evaluate the effects of radiation on people by estimating exposure dose by determining radiation and radioactive matters in the environment. The above database (DB) consists of seven DB such as Nirs Air Borne Dust Survey DB, Nirs Environmental Tritium Survey DB, Nirs Environmental Carbon Survey DB, Environmental Radiation Levels, Abe, Metabolic Database for Assessment of Internal Dose, Graphs of Predicted Monitoring Data, and Nirs nuclear installation environment water tritium survey DB. Outline of DB and each DB are explained. (S.Y.)

Radiation sources safety and radioactive materials security regulation in Ukraine

International Nuclear Information System (INIS)

Smyshliaiev, A.; Holubiev, V.; Makarovska, O.

2001-01-01

Radiation sources are widely used in Ukraine. There are about 2500 users in industry, science, education and about 2800 in medicine. About 80,000 sealed radiation sources with total kerma-equivalent of 450 Gy*M 2 /sec are used in Ukraine. The exact information about the radiation sources and their users will be provided in 2001 after the expected completion of the State inventory of radiation sources in Ukraine. In order to ensure radiation source safety in Ukraine, a State System for regulation of activities dealing with radiation sources has been established. The system includes the following elements: establishment of norms, rules and standards of radiation safety; authorization activity, i.e. issuance of permits (including those in the form of licences) for activities dealing with radiation sources; supervisory activity, i.e. control over observance of norms, rules and standards of radiation safety and fulfilment of conditions of licences for activities dealing with radiation sources, and also enforcement. Comprehensive nuclear legislation was developed and implemented from 1991 to 2000. Radiation source safety is regulated by three main nuclear laws in Ukraine: On the use of nuclear energy and radiation safety (passed on 8 February 1995); On Human Protection from Impact of Ionizing Radiation (passed on 14 January 1998); On permissive activity in the area of nuclear energy utilization (passed on 11 January 2000). The regulatory authorities in Ukraine are the Ministry for Ecology and Natural Resources (Nuclear Regulatory Department) and the Ministry of Health (State sanitary-epidemiology supervision). According to the legislation, activities dealing with radiation sources are forbidden without an officially issued permit in Ukraine. Permitted activities with radiation sources are envisaged: licensing of production, storage and maintenance of radiation sources; licensing of the use of radiation sources; obligatory certification of radiation sources and transport

Regulatory Control of Radiation Sources. Safety Guide

International Nuclear Information System (INIS)

2009-01-01

This Safety Guide is intended to assist States in implementing the requirements established in Safety Standards Series No. GS-R-1, Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety, for a national regulatory infrastructure to regulate any practice involving radiation sources in medicine, industry, research, agriculture and education. The Safety Guide provides advice on the legislative basis for establishing regulatory bodies, including the effective independence of the regulatory body. It also provides guidance on implementing the functions and activities of regulatory bodies: the development of regulations and guides on radiation safety; implementation of a system for notification and authorization; carrying out regulatory inspections; taking necessary enforcement actions; and investigating accidents and circumstances potentially giving rise to accidents. The various aspects relating to the regulatory control of consumer products are explained, including justification, optimization of exposure, safety assessment and authorization. Guidance is also provided on the organization and staffing of regulatory bodies. Contents: 1. Introduction; 2. Legal framework for a regulatory infrastructure; 3. Principal functions and activities of the regulatory body; 4. Regulatory control of the supply of consumer products; 5. Functions of the regulatory body shared with other governmental agencies; 6. Organization and staffing of the regulatory body; 7. Documentation of the functions and activities of the regulatory body; 8. Support services; 9. Quality management for the regulatory system.

Radiation safety program in a high dose rate brachytherapy facility

International Nuclear Information System (INIS)

Rodriguez, L.V.; Hermoso, T.M.; Solis, R.C.

2001-01-01

The use of remote afterloading equipment has been developed to improve radiation safety in the delivery of treatment in brachytherapy. Several accidents, however, have been reported involving high dose-rate brachytherapy system. These events, together with the desire to address the concerns of radiation workers, and the anticipated adoption of the International Basic Safety Standards for Protection Against Ionizing Radiation (IAEA, 1996), led to the development of the radiation safety program at the Department of Radiotherapy, Jose R. Reyes Memorial Medical Center and at the Division of Radiation Oncology, St. Luke's Medical Center. The radiation safety program covers five major aspects: quality control/quality assurance, radiation monitoring, preventive maintenance, administrative measures and quality audit. Measures for evaluation of effectiveness of the program include decreased unnecessary exposures of patients and staff, improved accuracy in treatment delivery and increased department efficiency due to the development of staff vigilance and decreased anxiety. The success in the implementation required the participation and cooperation of all the personnel involved in the procedures and strong management support. This paper will discuss the radiation safety program for a high dose rate brachytherapy facility developed at these two institutes which may serve as a guideline for other hospitals intending to install a similar facility. (author)

Sweden's Cooperation with Eastern Europe in Radiation Safety 2010

International Nuclear Information System (INIS)

Van Dassen, Lars; Andersson, Sarmite; Bejarano, Gabriela

2011-09-01

The Swedish Radiation Safety Authority implemented in 2010 cooperation projects in Russia, Ukraine, Georgia, Armenia, Lithuania and Moldova based on instructions from the Swedish Government and agreements with the European Union and the Swedish International Development Cooperation Agency, SIDA. The projects aim at achieving a net contribution to radiation safety (including nuclear safety, nuclear security and non-proliferation as well as radiation protection and emergency preparedness) for the benefit of the host country as well as Sweden. This report gives an overview of all the projects implemented in 2010

The main goals and principles of nuclear and radiation safety

International Nuclear Information System (INIS)

Huseynov, V.

2015-01-01

The use of modern radiation technology expands in various fields of human activity. The most advanced approach, methods and technologies and also radiation technologies are of great importance in industrial, medical, agricultural, construction, science, education, and etc. areas of the fastest growing Azerbaijan Republic. Ensuring of nuclear and radiation safety, safety standards, main principles and conception of safety play a crucial role. The following ten principles are taken as a basis to ensure safety measures. 1. Responsible for ensuring safety; 2. The role of government; 3. Leadership and management of security interests; 4. Devices and justification of activity; 5. Optimization of preservation; 6. Limiting of risks for physical persons; 7. The protection of present and future generations; 8. The prevention of accidents; 9. Emergency preparedness and response; 10. Reducing of risks of existing and unregulated radiation protection measures. The safety principles are applied together

Radiation safety standards

International Nuclear Information System (INIS)

1975-01-01

This is a basic document with which all rules and regulations, etc., concerning protection from ionizing radiations of workers and the general population have to conform. Basic concepts, dimensions, units, and terms used in the area of radiation safety are defined. Radiation exposures are sorted out into three categories: A, to personnel; B, to individual members of the popul;tion; and C, to the general population. Critical organs, furthermore, comprise four groups, the first of them being applicable to the whole-body gonads and bone marrow. Category A maximum permissible dose (MPD) to first group critical organs is 5 rem/year; to second group, 15 rem/year; to thrid group, 3O rem/year; and to fourth group, 75 rem/year. These rate figures include doses from both external and internal radiation exposure. Quality factors needed in computing doses from various types of radiation are provided. Permissible planned exposure levels are specified and guidelines given for accidental exposures. A radiation accident is considered to have occurred if the relevant critical organ dose is 5 times the annual MPD for that organ. For individual members of the population (category B), annual somatic doses to first group critical organs shall not exceed 0,5 rem. Population exposure is controlled in terms of genetically significant dose, which shall not exceed 5 rem/30 years. (G.G.)

Building competence in radiation protection and the safe use of radiation sources. Safety guide (Spanish ed.)

International Nuclear Information System (INIS)

2010-01-01

This Safety Guide makes recommendations concerning the building of competence in protection and safety within a national radiation protection infrastructure and provides guidance for setting up the structure for a national strategy. It relates to the training and assessment of qualification of new personnel and the retraining of existing personnel in order to develop and maintain appropriate levels of competence. It provides the necessary guidance to meet the requirements laid down in Safety Series No. 115, International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. Contents: 1. Introduction; 2. Responsibilities for building competence in protection and safety; 3. Education, training and work experience; 4. A national strategy for building competence in protection and safety.

Building competence in radiation protection and the safe use of radiation sources. Safety guide (Arabic ed.)

International Nuclear Information System (INIS)

2006-01-01

This Safety Guide makes recommendations concerning the building of competence in protection and safety within a national radiation protection infrastructure and provides guidance for setting up the structure for a national strategy. It relates to the training and assessment of qualification of new personnel and the retraining of existing personnel in order to develop and maintain appropriate levels of competence. It provides the necessary guidance to meet the requirements laid down in Safety Series No. 115, International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. Contents: 1. Introduction; 2. Responsibilities for building competence in protection and safety; 3. Education, training and work experience; 4. A national strategy for building competence in protection and safety.

Safety practices, perceptions, and behaviors in radiation oncology: A national survey of radiation therapists.

Science.gov (United States)

Woodhouse, Kristina Demas; Hashemi, David; Betcher, Kathryn; Doucette, Abigail; Weaver, Allison; Monzon, Brian; Rosenthal, Seth A; Vapiwala, Neha

Radiation therapy is complex and demands high vigilance and precise coordination. Radiation therapists (RTTs) directly deliver radiation and are often the first to discover an error. Yet, few studies have examined the practices of RTTs regarding patient safety. We conducted a national survey to explore the perspectives of RTTs related to quality and safety. In 2016, an electronic survey was sent to a random sample of 1500 RTTs in the United States. The survey assessed department safety, error reporting, safety knowledge, and culture. Questions were multiple choice or recorded on a Likert scale. Results were summarized using descriptive statistics and analyzed using multivariate logistic regression. A total of 702 RTTs from 49 states (47% response rate) completed the survey. Respondents represented a broad distribution across practice settings. Most RTTs rated department patient safety as excellent (61%) or very good (32%), especially if they had an incident learning system (ILS) (odds ratio, 2.0). Only 21% reported using an ILS despite 58% reporting an accessible ILS in their department. RTTs felt errors were most likely to occur with longer shifts and poor multidisciplinary communication; 40% reported that burnout and anxiety negatively affected their ability to deliver care. Workplace bullying was also reported among 17%. Overall, there was interest (62%) in improving knowledge in patient safety. Although most RTTs reported excellent safety cultures within their facilities, overall, there was limited access to and utilization of ILSs by RTTs. Workplace issues identified may also represent barriers to delivering quality care. RTTs were also interested in additional resources regarding quality and safety. These results will further enhance safety initiatives and inform future innovative educational efforts in radiation oncology. Copyright © 2017 American Society for Radiation Oncology. Published by Elsevier Inc. All rights reserved.

Review of radiation safety in the cardiac catheterization laboratory

International Nuclear Information System (INIS)

Johnson, L.W.; Moore, R.J.; Balter, S.

1992-01-01

With the increasing use of coronary arteriography and interventional procedures, radiation exposure to patients and personnel working in cardiac catheterization laboratories has increased. Proper technique to minimize both patient and operator exposure is necessary. A practical approach to radiation safety in the cardiac catheterization laboratory is presented. This discussion should be useful to facilities with well-established radiation safety programs as well as facilities that require restructuring to cope with the radiation environment in a modern cardiac catheterization laboratory

Study on the Safety Classification Criteria of Mechanical Systems and Components for Open Pool-Type Research Reactors

International Nuclear Information System (INIS)

Belal, Al Momani; Jo, Jong Chull

2013-01-01

This paper describes a new compromised safety classification approach based on the comparative study of the different practices in safety classification of mechanical systems and components of open pool-type RRs, which have been adopted by several developed countries in the nuclear power area. It is hoped that the proposed safety classification criteria will be used to develop a harmonized consensus international standard. Different safety classification criteria for systems, structures, and components (SSCs) of nuclear reactors are used among the countries that export or import nuclear reactor technology, which may make the nuclear technology trade and exchange difficult. Thus, such various different approaches of safety classification need to be compromised to establish a global standard. This article proposes practicable optimized criteria for safety classification of SSCs for open pool-type research reactors (RRs)

Study on the Safety Classification Criteria of Mechanical Systems and Components for Open Pool-Type Research Reactors

Energy Technology Data Exchange (ETDEWEB)

Belal, Al Momani [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Jo, Jong Chull [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2013-10-15

This paper describes a new compromised safety classification approach based on the comparative study of the different practices in safety classification of mechanical systems and components of open pool-type RRs, which have been adopted by several developed countries in the nuclear power area. It is hoped that the proposed safety classification criteria will be used to develop a harmonized consensus international standard. Different safety classification criteria for systems, structures, and components (SSCs) of nuclear reactors are used among the countries that export or import nuclear reactor technology, which may make the nuclear technology trade and exchange difficult. Thus, such various different approaches of safety classification need to be compromised to establish a global standard. This article proposes practicable optimized criteria for safety classification of SSCs for open pool-type research reactors (RRs)

Ukraine International cooperation in nuclear and radiation safety: public-administrative aspect

Directory of Open Access Journals (Sweden)

I. P. Krynychnay

2017-03-01

Full Text Available The article examines international cooperation of Ukraine with other States in the sphere of ensuring nuclear and radiation safety and highlights the main directions of development and improvement of nuclear and radiation safety in Ukraine based on international experience, with the aim of preventing the risks of accidents and contamination areas radiological substances. Illuminated that for more than half a century of experience in the use of nuclear energy by the international community under the auspices of the UN, IAEA and other international organizations initiated and monitored the implementation of key national and international programs on nuclear and radiation safety. Of the Convention in the field of nuclear safety and the related independent peer review, effective national regulatory infrastructures, current nuclear safety standards and policy documents, as well as mechanisms of evaluation in the framework of the IAEA constitute important prerequisites for the creation of a world community, the global regime of nuclear and radiation safety. For analysis of the state of international cooperation of Ukraine with other States in the sphere of nuclear and radiation safety, highlighted the legal substance of nuclear and radiation safety of Ukraine, which is enshrined in the domestic Law of Ukraine «On nuclear energy use and radiation safety». Considered the most relevant legal relations. It is established that, despite the current complex international instruments, existing domestic legislation on nuclear and radiation safety, partly there is a threat of emergency nuclear radiation nature, in connection with the failure of fixed rules and programs, lack of funding from the state is not always on time and in full allows you to perform fixed strategy for overcoming the consequences of radiation accidents, the prevention of the threat of environmental pollution. Found that to improve and further ensuring nuclear and radiation safety of

Analysis of differences in fuel safety criteria for WWER and western PWR nuclear power plants

International Nuclear Information System (INIS)

2003-11-01

In 2001 the OECD issued a report of the NEA/CSNI (Committee on the Safety of Nuclear Installations) Task Force on the existing safety criteria for reactor fuel for western LWR nuclear power plants (both for PWRs and BWRs) under new design elements. Likewise in 2001, the IAEA released a report by a Working Group on the existing safety criteria for reactor fuel for WWER nuclear power plants under new design requirements. However, it was found that it was not possible to compare the two sets of criteria on the basis upon which they had been established. Therefore, the IAEA initiated an assessment of the common features and differences in fuel safety criteria between plants of eastern and western design, focusing on western PWRs and eastern WWER reactors. Between October 2000 and November 2001, the IAEA organized several workshops with representatives from eastern and western European countries in which the current fuel safety related criteria for PWR and WWER reactors were reviewed and compared. The workshops brought together expert representatives from the Russian Federation, from the Ukraine and from western countries that operate PWRs. The first workshop focused on a general overview of the fuel safety criteria in order for all representatives to appreciate the various criteria and their respective bases. The second workshop (which involved one western and one eastern expert) concentrated on addressing and explaining the differences observed, and documenting all these results in preparation for a panel discussion. This panel discussion took place during the third workshop, where the previously obtained results were reviewed in detail and final recommendations were made. This report documents the findings of the workshops. It highlights the common features and differences between PWR and WWER fuel, and may serve as a general basis for the safety evaluation of these fuels. Therefore, it will be very beneficial for licensing activities for PWR and WWER plants, as it

Radiation protection databases of nuclear safety regulatory authority

International Nuclear Information System (INIS)

Janzekovic, H.; Vokal, B.; Krizman, M.

2003-01-01

Radiation protection and nuclear safety of nuclear installations have a common objective, protection against ionising radiation. The operational safety of a nuclear power plant is evaluated using performance indicators as for instance collective radiation exposure, unit capability factor, unplanned capability loss factor, etc. As stated by WANO (World Association of Nuclear Operators) the performance indicators are 'a management tool so each operator can monitor its own performance and progress, set challenging goals for improvement and consistently compare performance with that of other plants or industry'. In order to make the analysis of the performance indicators feasible to an operator as well as to regulatory authorities a suitable database should be created based on the data related to a facility or facilities. Moreover, the international bodies found out that the comparison of radiation protection in nuclear facilities in different countries could be feasible only if the databases with well defined parameters are established. The article will briefly describe the development of international databases regarding radiation protection related to nuclear facilities. The issues related to the possible development of the efficient radiation protection control of a nuclear facility based on experience of the Slovenian Nuclear Safety Administration will be presented. (author)

MO-AB-201-00: Radiation Safety Officer Update

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-06-15

The role of the Radiation Safety Officer at a medical facility can be complicated. The complexity of the position is based on the breadth of services provided at the institution and the nature of the radioactive materials license. Medical practices are constantly changing and the use of ionizing radiation continues to rise in this area. Some of the newer medical applications involving radiation have unique regulatory and safety issues that must be addressed. Oversight of the uses of radiation start at the local level (radiation safety officer, radiation safety committee) and are heavily impacted by outside agencies (i.e. Nuclear Regulatory Commission, State Radiologic Health, The Joint Commission (TJC), etc). This session will provide both an overview of regulatory oversight and essential compliance practices as well as practical ways to assess and introduce some of the new applications utilizing radioactive materials into your medical facility. Learning Objectives: Regulatory Compliance and Safety with New Radiotherapies: Spheres and Ra-223 (Lance Phillips) Understand the radioactive materials license amendment process to add new radiotherapies (i.e., SIR-Spheres, Therasphere, Xofigo). Understand the AU approval process for microspheres and Xofigo. Examine the training and handling requirements for new procedures. Understand the process involved with protocol development, SOP in order to define roles and responsibilities. The RSO and The RSC: Challenges and Opportunities (Colin Dimock) Understand how to form an effective Committee. Examine what the Committee does for the Program and the RSO. Understand the importance of Committee engagement. Discuss the balance of the complimentary roles of the RSO and the Committee. The Alphabet Soup of Regulatory Compliance: Being Prepared for Inspections (Linda Kroger) Recognize the various regulatory bodies and organizations with oversight or impact in Nuclear Medicine, Radiology and Radiation Oncology. Examine 10CFR35

MO-AB-201-00: Radiation Safety Officer Update

International Nuclear Information System (INIS)

2015-01-01

The role of the Radiation Safety Officer at a medical facility can be complicated. The complexity of the position is based on the breadth of services provided at the institution and the nature of the radioactive materials license. Medical practices are constantly changing and the use of ionizing radiation continues to rise in this area. Some of the newer medical applications involving radiation have unique regulatory and safety issues that must be addressed. Oversight of the uses of radiation start at the local level (radiation safety officer, radiation safety committee) and are heavily impacted by outside agencies (i.e. Nuclear Regulatory Commission, State Radiologic Health, The Joint Commission (TJC), etc). This session will provide both an overview of regulatory oversight and essential compliance practices as well as practical ways to assess and introduce some of the new applications utilizing radioactive materials into your medical facility. Learning Objectives: Regulatory Compliance and Safety with New Radiotherapies: Spheres and Ra-223 (Lance Phillips) Understand the radioactive materials license amendment process to add new radiotherapies (i.e., SIR-Spheres, Therasphere, Xofigo). Understand the AU approval process for microspheres and Xofigo. Examine the training and handling requirements for new procedures. Understand the process involved with protocol development, SOP in order to define roles and responsibilities. The RSO and The RSC: Challenges and Opportunities (Colin Dimock) Understand how to form an effective Committee. Examine what the Committee does for the Program and the RSO. Understand the importance of Committee engagement. Discuss the balance of the complimentary roles of the RSO and the Committee. The Alphabet Soup of Regulatory Compliance: Being Prepared for Inspections (Linda Kroger) Recognize the various regulatory bodies and organizations with oversight or impact in Nuclear Medicine, Radiology and Radiation Oncology. Examine 10CFR35

Operational and environmental safety

International Nuclear Information System (INIS)

Anon.

1978-01-01

The responsibility of the DOE Office of Operational and Environmental Safety is to assure that DOE-controlled activities are conducted in a manner that will minimize risks to the public and employees and will provide protection for property and the environment. The program supports the various energy technologies by identifying and resolving safety problems; developing and issuing safety policies, standards, and criteria; assuring compliance with DOE, Federal, and state safety regulations; and establishing procedures for reporting and investigating accidents in DOE operations. Guidelines for the radiation protection of personnel; radiation monitoring at nuclear facilities; an assessment of criticality accidents by fault tree analysis; and the preparation of environmental, safety, and health standards applicable to geothermal energy development are discussed

Ionising radiation safety training in the Australian defence organisation (ADO)

International Nuclear Information System (INIS)

Jenks, G.J.; O'Donovan, E.J.B.; Wood, W.B.

1996-01-01

Full text: Training personnel in ionising radiation safety within the Australian Defence Organisation (ADO) requires addressing some unique features of an organisation employing both military and civilian personnel. Activities may include those of a civil nature (such as industrial and medical radiography), specific military requirements (for training and emergency response) and scientific research and development. Some personnel may be assigned to full-time duties associated with radiation, while others may be designated as radiation protection officers in remote units with few duties to perform in this role. A further complication is that most military personnel are subjected to postings at regular intervals. The ADO's Directorate of Defence Occupational Health and Safety has established an Ionising Radiation Safety Subcommittee to monitor not only the adequacy of the internal Ionising Radiation Safety Manual but also the training requirements. A training course, responding to these requirements, has been developed to emphasise: basic radiation theory and protection; operation of radiation monitors available in the ADO; an understanding of the Safety Manual; day-to-day radiation safety in units and establishments; and appropriate responses to radiation accidents and emergencies. In addition, students are briefed on a limited number of peripheral topics and participate in some site visits. Currently, two Courses are held annually, each with about twenty students. Most of the material is presented by ADO personnel with external contractor support. The three Courses held to date have proved sufficiently successful, both for the students and the ADO generally, to seek national accreditation through the Australian National Training Authority and, as a first step, competency standards have been identified

Radiation safety of soil moisture neutron probes

International Nuclear Information System (INIS)

Oresegun, M.O.

2000-01-01

The neutron probe measures sub-surface moisture in soil and other materials by means of high energy neutrons and a slow (thermal) neutron detector. Exposure to radiation, including neutrons, especially at high doses, can cause detrimental health effects. In order to achieve operational radiation safety, there must be compliance with protection and safety standards. The design and manufacture of commercially available neutron moisture gauges are such that risks to the health of the user have been greatly reduced. The major concern is radiation escape from the soil during measurement, especially under dry conditions and when the radius of influence is large. With appropriate work practices as well as good design and manufacture of gauges, recorded occupational doses have been well below recommended annual limits. It can be concluded that the use of neutron gauges poses not only acceptable health and safety risks but, in fact, the risks are negligible. Neutron gauges should not be classified as posing high potential health hazards. (author)

''Low dose'' and/or ''high dose'' in radiation protection: A need to setting criteria for dose classification

International Nuclear Information System (INIS)

Sohrabi, M.

1997-01-01

The ''low dose'' and/or ''high dose'' of ionizing radiation are common terms widely used in radiation applications, radiation protection and radiobiology, and natural radiation environment. Reading the title, the papers of this interesting and highly important conference and the related literature, one can simply raise the question; ''What are the levels and/or criteria for defining a low dose or a high dose of ionizing radiation?''. This is due to the fact that the criteria for these terms and for dose levels between these two extreme quantities have not yet been set, so that the terms relatively lower doses or higher doses are usually applied. Therefore, setting criteria for classification of radiation doses in the above mentioned areas seems a vital need. The author while realizing the existing problems to achieve this important task, has made efforts in this paper to justify this need and has proposed some criteria, in particular for the classification of natural radiation areas, based on a system of dose limitation. (author)

Radiation safety and vascular access: attitudes among cardiologists worldwide

Energy Technology Data Exchange (ETDEWEB)

Vidovich, Mladen I., E-mail: miv@uic.edu [Department of Medicine, Division of Cardiology, University of Illinois at Chicago, Chicago, Illinois (United States); Khan, Asrar A. [Department of Medicine, Division of Cardiology, University of Illinois at Chicago, Chicago, Illinois (United States); Xie, Hui [Division of Epidemiology and Biostatistics and Cancer Center, University of Illinois at Chicago, Chicago, Illinois (United States); Shroff, Adhir R. [Department of Medicine, Division of Cardiology, University of Illinois at Chicago, Chicago, Illinois (United States)

2015-03-15

Objectives: To determine opinions and perceptions of interventional cardiologists on the topic of radiation and vascular access choice. Background: Transradial approach for cardiac catheterization has been increasing in popularity worldwide. There is evidence that transradial access (TRA) may be associated with increasing radiation doses compared to transfemoral access (TFA). Methods: We distributed a questionnaire to collect opinions of interventional cardiologists around the world. Results: Interventional cardiologists (n = 5332) were contacted by email to complete an on-line survey from September to October 2013. The response rate was 20% (n = 1084). TRA was used in 54% of percutaneous coronary interventions (PCIs). Most TRAs (80%) were performed with right radial access (RRA). Interventionalists perceived that TRA was associated with higher radiation exposure compared to TFA and that RRA was associated with higher radiation exposure that left radial access (LRA). Older interventionalists were more likely to use radiation protection equipment and those who underwent radiation safety training gave more importance to ALARA (as low as reasonably achievable). Nearly half the respondents stated they would perform more TRA if the radiation exposure was similar to TFA. While interventionalists in the United States placed less importance to certain radiation protective equipment, European operators were more concerned with physician and patient radiation. Conclusions: Interventionalists worldwide reported higher perceived radiation doses with TRA compared to TFA and RRA compared to LRA. Efforts should be directed toward encouraging consistent radiation safety training. Major investment and application of novel radiation protection tools and radiation dose reduction strategies should be pursued. - Highlights: • We examined radiation safety and arterial access practices among 1000 cardiologists. • Radial access is perceived as having higher radiation dose compared to

Conception and activity directions of journal ''Nuclear and radiation safety''

International Nuclear Information System (INIS)

Olena, M.; Volodymyr, S.

2000-01-01

In connection with the State Scientific and Technical Centre onr Nuclear and Radiation Safety (SSTC NRA) and Odessa State Polytechnic University the journal 'Nuclear and Radiation Safety' was established in 1998. In Ukraine many people are interested in nuclear energy problems. The accident in Chernobyl NPP unit 4 touches all Ukrainians and brings about strong and regular attention to nuclear and radiation safety of nuclear installations and nuclear technology, on the other side more than 50 per cent of electric power is produced in 5 NPPs and as following national power supply depends on stability of NPPs work. Main goals of the journal are: Support to Nuclear Regulatory Administration (NRA) of MEPNS of Ukraine, creation of information space for effective exchange of results of scientific, scientific and technical, scientific and analytical work in the field of Nuclear and Radiation Safety, assistance in integrated development of research for Nuclear and Radiation Safety by publication in a single issue of scientific articles, involvement of state scientific potential in resolving actual problems, participation in international collaboration in the framework of agreements, programs and plans. (orig.)

Alternative risk-based criteria for transportation of radioactive materials on the United States Department of Energy Hanford Site

International Nuclear Information System (INIS)

Mercado, J.E.; Field, J.G.; Smith, R.J.; Wang, O.S.

1993-01-01

This paper presents the development of an alternative method to evaluate packaging safety for radioactive material transported solely within the boundaries of a restricted site; the method uses risk-based criteria to assess and document packaging safety. These criteria offer a standard against which the results of a risk assessment are compared to evaluate the safety of a transportation operation. Numerous payloads are transported entirely within the U.S. Department of Energy's Hanford Site boundaries. The U.S. Department of Energy requires that the safety of onsite transportation be equivalent to the safety provided for transporting radioactive materials in commerce as regulated by the U.S. Department of Transportation and the U.S. Nuclear Regulatory Commission. Some onsite packaging configurations do not meet the performance criteria that form the basis of these regulations, necessitating the establishment of alternative criteria to evaluate safety. Quantitatively defined criteria have been derived from the U.S. Department of Transportation limits for package radiation levels, curie content, activity release, and external contamination levels. Recommendations of the International Committee on Radiation Protection may further restrict the criteria. The proposed method documents packaging safety in a transportation risk assessment. The assessment estimates accident frequencies, conservatively evaluates the dose consequences of these accidents, and compares the results to the established risk acceptance criteria. Specific Hanford Site onsite packaging and transportation issues illustrate the alternative method. The paper compares the solutions resulting from the application of risk-based criteria to those resulting from strict compliance with commercial transportation regulations. (author)

Nuclear safety requirements for upgrading the National Repository for Radioactive Wastes-Baita Bihor

International Nuclear Information System (INIS)

Vladescu, Gabriela; Necula, Daniela

2000-01-01

The upgrading project of National Repository for Radioactive Wastes-Baita Bihor is based on the integrated concept of nuclear safety. Its ingredients are the following: A. The principles of nuclear safety regarding the management of radioactive wastes and radioprotection; B. Safety objectives for final disposal of low- and intermediate-level radioactive wastes; C. Safety criteria for final disposal of low- and intermediate-level radioactive wastes; D. Assessment of safety criteria fulfillment for final disposal of low- and intermediate-level radioactive wastes. Concerning the nuclear safety in radioactive waste management the following issues are considered: population health protection, preventing transfrontier contamination, future generation radiation protection, national legislation, control of radioactive waste production, interplay between radioactive waste production and management, radioactive waste repository safety. The safety criteria of final disposal of low- and intermediate-level radioactive wastes are discussed by taking into account the geological and hydrogeological configuration, the physico-chemical and geochemical characteristics, the tectonics and seismicity conditions, extreme climatic potential events at the mine location. Concerning the requirements upon the repository, the following aspects are analyzed: the impact on environment, the safety system reliability, the criticality control, the filling composition to prevent radioactive leakage, the repository final sealing, the surveillance. Concerning the radioactive waste, specific criteria taken into account are the radionuclide content, the chemical composition and stability, waste material endurance to heat and radiation. The waste packaging criteria discussed are the mechanical endurance, materials toughness and types as related to deterioration caused by handling, transportation, storing or accidents. Fulfillment of safety criteria is assessed by scenarios analyses and analyses of

Radiation Protection, Nuclear Safety and Security

International Nuclear Information System (INIS)

Faye, Ndeye Arame Boye; Ndao, Ababacar Sadikhe; Tall, Moustapha Sadibou

2014-01-01

Senegal has put in place a regulatory framework which allows to frame legally the use of radioactive sources. A regulatory authority has been established to ensure its application. It is in the process of carrying out its regulatory functions. It cooperates with appropriate national or international institutions operating in fields related to radiation protection, safety and nuclear safety.

Australian Radiation Protection and Nuclear Safety Act 1998. Guide to the Australian radiation protection and nuclear safety licensing framework. 1. ed.

International Nuclear Information System (INIS)

1999-03-01

The purpose of this guide is to provide information to Commonwealth entities who may require a license under the Australian Radiation Protection and Nuclear Safety (ARPANS) Act 1998 to enable them to posses, have control of, use, operate or dispose of radiation sources. The guide describes to which agencies and what activities require licensing. It also addresses general administrative and legal matters such as appeal procedures, ongoing licensing requirements, monitoring and compliance. Applicants are advised to consult the Australian Radiation Protection and Nuclear Safety Act 1998 and accompanying Regulations when submitting applications

Australian Radiation Protection and Nuclear Safety Act 1998. Guide to the Australian radiation protection and nuclear safety licensing framework; 1. ed

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

The purpose of this guide is to provide information to Commonwealth entities who may require a license under the Australian Radiation Protection and Nuclear Safety (ARPANS) Act 1998 to enable them to posses, have control of, use, operate or dispose of radiation sources. The guide describes to which agencies and what activities require licensing. It also addresses general administrative and legal matters such as appeal procedures, ongoing licensing requirements, monitoring and compliance. Applicants are advised to consult the Australian Radiation Protection and Nuclear Safety Act 1998 and accompanying Regulations when submitting applications

Radiation protection aspects in the design of nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2008-01-01

The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the Contracting Parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

Expanding the scope of practice for radiology managers: radiation safety duties.

Science.gov (United States)

Orders, Amy B; Wright, Donna

2003-01-01

In addition to financial responsibilities and patient care duties, many medical facilities also expect radiology department managers to wear "safety" hats and complete fundamental quality control/quality assurance, conduct routine safety surveillance in the department, and to meet regulatory demands in the workplace. All managers influence continuous quality improvement initiatives, from effective utilization of resource and staffing allocations, to efficacy of patient scheduling tactics. It is critically important to understand continuous quality improvement (CQI) and its relationship with the radiology manager, specifically quality assurance/quality control in routine work, as these are the fundamentals of institutional safety, including radiation safety. When an institution applies for a registration for radiation-producing devices or a license for the use of radioactive materials, the permit granting body has specific requirements, policies and procedures that must be satisfied in order to be granted a permit and to maintain it continuously. In the 32 U.S. Agreement states, which are states that have radiation safety programs equivalent to the Nuclear Regulatory Commission programs, individual facilities apply for permits through the local governing body of radiation protection. Other states are directly licensed by the Nuclear Regulatory Commission and associated regulatory entities. These regulatory agencies grant permits, set conditions for use in accordance with state and federal laws, monitor and enforce radiation safety activities, and audit facilities for compliance with their regulations. Every radiology department and associated areas of radiation use are subject to inspection and enforcement policies in order to ensure safety of equipment and personnel. In today's business practice, department managers or chief technologists may actively participate in the duties associated with institutional radiation safety, especially in smaller institutions, while

Release criteria for patients having undergone radionuclide therapy and criteria for their crossing the state border of the Russian Federation

International Nuclear Information System (INIS)

Zvonova, I.; Balonov, M.; Golikov, V.

2011-01-01

By means of a conservative dosimetry model, the values of operational radiological criteria for patients released from hospital-residual activity in a body and dose rate near the patient's body-are substantiated based on the effective dose limit of 5 mSv for persons helping the patient or living with him and 1 mSv for other adults and children. Two sets of operative criteria for radionuclides 125 I, 131 I, 153 Sm and 188 Re used in Russia for radionuclide therapy were derived. Release criteria for 125 I well differ from such values in other countries because in this work absorption of 125 I low-energy photon radiation in the patient was taken into account. When a patient having undergone radionuclide therapy crosses the frontier of Russia, high-sensitivity devices for radiation control at the custom can detect the patient. A simplified radiological assessment of the patient was suggested aimed at provision of radiation safety for patient companions in transport. (authors)

Some aspects of RF radiation safety guidelines on urgent protective measures in case of radiation emergency at NPP

International Nuclear Information System (INIS)

Bulgakov, V.G.; Klepikova, N.V.; Shershakov, V.M.; Ivanov, E.A.

2003-01-01

Full text: The work is aimed at developing a decision making strategy and tools for putting into practice the principles of reasonableness and optimization when applying countermeasures in case of a radiation related accident at a nuclear power plant in RF. The presentation discusses results of the study of the legal framework in the RF for decision making to protect the personnel and public in case of a radiation-related accident Consideration is given to issues of methodological support for emergency response systems at NPPs, as required by the RF radiation safety norms to protect personnel and the public. This work was performed as part of methodological support to the national emergency center of Rosenergoatom comprising several technical support centers on the base of leading institutes with large scientific potential in the fields of nuclear power use, environmental and public protection, radioecology etc. Such centers were set up for scientific and technical support to decision making in case of emergency at NPPs. Specialists of die centers are able to quickly assess the emerging situation and propose a set of measures to minimize damage, drawing on expert judgements. The radiation safety guidelines (NRB-99) lays down requirements and criteria for decision making to protect the public in different phases of a radiation accident which should be used when implementing countermeasures and developing emergency response plans with allowance for specific situation and local conditions. These criteria provide a basis for designating areas of emergency response that would be optimum for specific population points, intervention measures etc. Dealing with these tasks requires development of normative and methodological documentation taking into account both the NRB-99 requirements and international recommendations. In accordance with NRB-99: expected and averted radiation doses are the key criteria to be used in application of any protection measures in radiation

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

Science.gov (United States)

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.

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

Science.gov (United States)

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.

Communications on nuclear, radiation, transport and waste safety: a practical handbook

International Nuclear Information System (INIS)

1999-04-01

Basic requirements to be met by national infrastructures for radiation protection and safety are stated in the International basic safety Standards for Protection against Ionizing radiation and for safety of radiation Sources. These include a requirement 'to set up appropriate means of informing the public, its representatives and the information media about the health and safety aspects of activities involving exposure to radiation and about regulatory processes.' This publication is intended for national regulatory authorities, to provide them with guidance on the principles and methods that can be applied in communicating nuclear safety to different audiences under different circumstances. This report presumes the existence of adequate national infrastructure including an independent regulatory authority with sufficient powers and resources to meet its responsibilities

Squale: evaluation criteria of functioning safety; Squale: criteres d`evaluation de la surete de fonctionnement

Energy Technology Data Exchange (ETDEWEB)

Deswarte, Y; Kaaniche, M [Centre National de la Recherche Scientifique (CNRS), 31 - Toulouse (France). Laboratoire d` Analyse et d` Architecture des Systemes; Corneillie, P [CE2A-DI, 92 - Courbevoie (France); Benoit, P [Matra Transport International, 92 - Montrouge (France)

1998-05-01

The SQUALE (security, safety and quality evaluation for dependable systems) project is part of the ACTS (advanced communications, technologies and services) European program. Its aim is to develop confidence evaluation criteria to test the functioning safety of systems. All industrial sectors that use critical applications (nuclear, railway, aerospace..) are concerned. SQUALE evaluation criteria differ from the classical evaluation methods: they are independent of the application domains and industrial sectors, they take into account the overall functioning safety attributes, and they can progressively change according to the level of severity required. In order to validate the approach and to refine the criteria, a first experiment is in progress with the METEOR automatic underground railway and another will be carried out on a telecommunication system developed by Bouygues company. (J.S.) 15 refs.

Safety analysis, risk assessment, and risk acceptance criteria

International Nuclear Information System (INIS)

Jamali, K.

1997-01-01

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

Investigation of status of safety management in radiation handle works

International Nuclear Information System (INIS)

Amauchi, Hiroshi; Nishimura, Kenji; Izumi, Kokichi

2007-01-01

This report describes the investigation in the title concerning the system for safety management and for accident prevention, which was done by a questionnaire in a period of 1.5 months in 2005. The questionnaire including 55 questions for safety management system, 33 for instruments and safety utilization of radiation and 57 for present status of safety management in high-risk radiation works, was performed in 780 hospitals, of which 313 answered. The first 55 questions concerned with the facility, patient identification, information exchange, management of private information, safety management activities, measures to prevent accident, manual preparation, personnel education and safety awareness; the second, with management of instruments, package insert, system for reporting the safety information, management of implants, re-imaging and radiation protection; and the third, with the systems for patients' emergency, in departments of CT/MR, of IVR, of nuclear diagnosis and of radiation therapy. Based on the results obtained, many problems, tasks and advices are presented to various items and further continuation of efforts to improve the present status is mentioned to be necessary. Details are given in the homepage of the Japanese Society of Radiological Technology. (T.I.)

The Argentine Approach to Radiation Safety: Its Ethical Basis

International Nuclear Information System (INIS)

Gonzalez, A.J.

2011-01-01

The ethical bases of Argentina's radiation safety approach are reviewed. The applied principles are those recommended and established internationally, namely: the principle of justification of decisions that alters the radiation exposure situation; the principle of optimization of protection and safety; the principle of individual protection for restricting possible inequitable outcomes of optimized safety; and the implicit principle of inter generational prudence for protection future generations and the habitat. The principles are compared vis-a-vis the prevalent ethical doctrines: justification vis-a-vis teleology; optimization vis-a-vis utilitarianism; individual protection vis-a-vis de ontology; and, inter generational prudence vis-a-vis aretaicism (or virtuosity). The application of the principles and their ethics in Argentina is analysed. These principles are applied to All exposure to radiation harm; namely, to exposures to actual doses and to exposures to actual risk and potential doses, including those related to the safety of nuclear installations, and they are harmonized and applied in conjunction. It is concluded that building a bridge among all available ethical doctrines and applying it to radiation safety against actual doses and actual risk and potential doses is at the roots of the successful nuclear regulatory experience in Argentina.

Supervisor's experiments on radiation safety trainings in school of engineering

International Nuclear Information System (INIS)

Nomura, Kiyoshi

2005-01-01

Radiation safety training courses in School of Engineering, The University of Tokyo, were introduced. The number of radiation workers and the usage of radiation and radioisotopes have been surveyed for past 14 years. The number of radiation workers in School of Engineering has increased due to the treatment of X-ray analysis of materials, recently. It is important for workers to understand the present situation of School of Engineering before the treatment of radiation and radioisotopes. What the supervisor should tell to radiation workers were presented herewith. The basic questionnaires after the lecture are effective for radiation safety trainings. (author)

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

International Nuclear Information System (INIS)

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

1987-01-01

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

Safety criteria related to microheterogeneities in LWR mixed oxide fuels

International Nuclear Information System (INIS)

Renard, A.; Mostin, N.

1978-01-01

The main safety aspets of PuO 2 microheterogeneities in the pellets of LWR mixed oxide fuels are reviewed. Points of interest are studied, especially the transient behaviour in accidental conditions and criteria are deduced for use in the specification and quality control of the fabricated product. (author)

Radiation protection safety in Uganda -- Experience and prospects of the National Radiation Protection Service

International Nuclear Information System (INIS)

Kisolo, A.

2001-01-01

The Uganda National Radiation Protection Service (NRPS) is a technical body under the Atomic Energy Control Board, established by Law - the Atomic Energy Decree of 1972, Decree No. 12, to oversee and enforce safety of radiation sources, practices and workers; and to protect the patients, members of the public and the environment from the dangers of ionizing radiation and radioactive wastes. The Ionizing Radiation Regulations (Standards) - Statutory Instruments Supplement No. 21 of 1996 -- back up the Law. The Law requires all users, importers and operators of radiation sources and radioactive materials to notify the NRPS for registration and licensing. The NRPS is responsible for licensing and for the regulatory enforcement of compliance to the requirements for the safety of radiation sources and practices. There are about 200 diagnostic X-ray units, two radiotherapy centres, one nuclear medicine unit, several neutron probes, about three level gauges and two non-destructive testing sources and a number of small sealed sources in teaching and research institutions. About 50% of these sources have been entered in our inventory using the RAIS software provided by the IAEA. There are about 500 radiation workers and 250 underground miners. The NRPS covers about 50% of the radiation workers. It is planned that by June 2001, all occupational workers will be monitored, bringing coverage to 100%. The Government of Uganda is making the necessary legal, administrative and technical arrangements aimed at establishing the National Radiation Protection Commission as an autonomous regulatory authority. The Atomic Energy Decree of 1972 and Regulations of 1996 are being revised to provide for the National Radiation Protection Commission and to make it comply with the requirements of the International Basic Safety Standards Safety Series No. 115. (author)

Analysis of existing work-zone devices with MASH safety performance criteria.

Science.gov (United States)

2009-02-01

Crashworthy, work-zone, portable sign support systems accepted under NCHRP Report No. 350 were analyzed to : predict their safety peformance according to the TL-3 MASH evaluation criteria. An analysis was conducted to determine : which hardware param...

Health physics limitations for radiation protection of patients and medical staff

International Nuclear Information System (INIS)

Golikov, V.Ya.; Ermolina, E.P.

1997-01-01

Norm-setting documents regulating the requirements to radiation safety during medical x-ray and radiological procedures are reviewed. Besides the Federal Law On Radiation Safety of the Population and Radiation Safety Norms-96, the authors comment on the norm-setting documents issued later and supplementing the above documents. The authors emphasize the obligatory licensing during medical use of ionizing radiation sources. Effective dose is introduced as the criterion of radiation safety of the patients and staff during prophylactic x-ray examinations. Principles of normsetting, validation, and optimization of medical exposures and criteria of radiation safety of patients are discussed

What do implementers need in terms of regulatory safety criteria for the post-closure phase?

International Nuclear Information System (INIS)

Cahen, B.

2010-01-01

Bruno Cahen, Director Safety Division (ANDRA) presented the point of view of the NEA Integration Group for the Safety Case (IGSC) on 'What do implementers need in terms of regulatory safety criteria for the post-closure phase?' B. Cahen acknowledged that the national experience in siting and developing conceptual designs of geological disposal is growing rapidly. It implies increasing opportunities for interactions between implementers and regulators. There has been large development of international guidance in the recent years. Many regulators have already developed a regulatory framework. The implementers need practical, transparent and deliverable regulations. These regulations should draw on experiences gained from development of geological disposal projects. The IGSC has identified five key questions that the RF may focus on: 1. Over what time frame are the waste deemed to present a hazard? 2. Over what time frames are regulatory criteria applied and do they change over time? 3. Over what time frame(s) are safety assessments required to be conducted? 4. How do implementers have to address uncertainties in the long time frames? 5. What happens after cut-offs: are additional analyses needed? What types of arguments are to be used? Stable, understandable and practical criteria mean, namely, that they need to be developed on a strong scientific and societal basis, that there is consistency of safety options and requirements for different types of waste, that, in the longer time frames, the emphasis is given to robust systems, passive safety and multiple safety functions and that the criteria should fit the various phases of the project (siting, designing, operating, closure and post-closure). Experience feedback from safety cases shows that safety priorities depend very much on time frames. The derived safety criteria for the individual components should lead to measurable, verifiable specifications. The assessment of geological repository post-closure safety

Radiation safety assessment and development of environmental radiation monitoring technology

CERN Document Server

Choi, B H; Kim, S G

2002-01-01

The Periodic Safety Review(PSR) of the existing nuclear power plants is required every ten years according to the recently revised atomic energy acts. The PSR of Kori unit 1 and Wolsong unit 1 that have been operating more than ten years is ongoing to comply the regulations. This research project started to develop the techniques necessary for the PSR. The project developed the following four techniques at the first stage for the environmental assessment of the existing plants. 1) Establishment of the assessment technology for contamination and accumulation trends of radionuclides, 2) alarm point setting of environmental radiation monitoring system, 3) Development of Radiation Safety Evaluation Factor for Korean NPP, and 4) the evaluation of radiation monitoring system performance and set-up of alarm/warn set point. A dynamic compartment model to derive a relationship between the release rates of gas phase radionuclides and the concentrations in the environmental samples. The model was validated by comparing ...

New radiation protection concept as important safety factor of industrial radiography

International Nuclear Information System (INIS)

Pavlovic, R.; Pavlovic, S.

1998-01-01

Industrial radiography is a method for non destructive testing of homogeneity of various materials based on different absorption of radiation in different material. X and γ radiation are the most often used. Detrimental effects of radiation are observed since its discovery. In order to prevent harmful effects of radiation without unduly limitations of its use, International Commission on Radiological Protection in collaboration with International Atomic Energy Agency have developed International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources, Safety Series No 115, adopted in 1996. based on ICRP recommendations from 1991. Besides a lot of changes in radiation protection concept and philosophy, decrement of annual dose limits for occupational exposure from 50 to 20 mSv. (author)

Report on administrative work for radiation safety from April 2006 to March 2007

Energy Technology Data Exchange (ETDEWEB)

Komori, Akio; Kaneko, Osamu; Nishimura, Kiyohiko; Uda, Tatsuhiko; Asakura, Yamato; Kawano, Takao; Yamanishi, Hirokuni; Miyake, Hitoshi

2007-10-15

The National Institute for Fusion Science (NIFS) is proceeding with the research on magnetic confining nuclear fusion both experimentally and theoretically. During the experiment with deals with very hot plasma, X ray is generated. Therefore the experimental devices with their surroundings are administrated in conformity with the Industrial Safety and Health Law to keep workplace safety. The Radiation Control Safety Office of Safety Hygiene Protection Bureau carries out measuring the radiation dose level regularly, registering the employees who are engaged in plasma experiments, and training them. Non-regulated small sealed sources are used in some detectors. The treating of these sources is controlled by the Safety and Environmental Research Center. This report is on administrative works for radiation safety in the last fiscal year 2006. It includes (1) report on the establishment of radiation safety management system, (2) report on the establishment of training and registration system for radiation workers, and (3) results of radiation dose measurement and monitoring in the radiation controlled area and on the site by using Radiation Monitoring System Applicable to Fusion Experiment (RMSAFE). The report has been published annually. We hope that these reports would be helpful for future safety management in NIFS. (author)

Report on administrative work for radiation safety from April 2006 to March 2007

International Nuclear Information System (INIS)

Komori, Akio; Kaneko, Osamu; Nishimura, Kiyohiko; Uda, Tatsuhiko; Asakura, Yamato; Kawano, Takao; Yamanishi, Hirokuni; Miyake, Hitoshi

2007-10-01

The National Institute for Fusion Science (NIFS) is proceeding with the research on magnetic confining nuclear fusion both experimentally and theoretically. During the experiment with deals with very hot plasma, X ray is generated. Therefore the experimental devices with their surroundings are administrated in conformity with the Industrial Safety and Health Law to keep workplace safety. The Radiation Control Safety Office of Safety Hygiene Protection Bureau carries out measuring the radiation dose level regularly, registering the employees who are engaged in plasma experiments, and training them. Non-regulated small sealed sources are used in some detectors. The treating of these sources is controlled by the Safety and Environmental Research Center. This report is on administrative works for radiation safety in the last fiscal year 2006. It includes (1) report on the establishment of radiation safety management system, (2) report on the establishment of training and registration system for radiation workers, and (3) results of radiation dose measurement and monitoring in the radiation controlled area and on the site by using Radiation Monitoring System Applicable to Fusion Experiment (RMSAFE). The report has been published annually. We hope that these reports would be helpful for future safety management in NIFS. (author)

Legislation for radiation protection and nuclear safety in the Republic of Croatia

International Nuclear Information System (INIS)

Novosel, N.

1994-01-01

The main prerequisite of radiation protection and nuclear safety development and improvement in the Republic of Croatia are: national legislation for radiation protection and nuclear safety in accordance with international recommendations; and development of state infrastructure for organization and management of radiation protection and nuclear safety measures. In this paper I the following topics are present: inherited legislation for radiation protection and nuclear safety; modern trends in world nowadays; and what is done and has to be done in the Republic of Croatia to improve this situation

Systematic approach to training for competence building in radiation safety

International Nuclear Information System (INIS)

Asiamah, S.D.; Schandorf, C.; Darko, E.O.

2003-01-01

Competence building involves four main attributes, namely, knowledge, skills, operating experience and attitude to radiation safety. These multi-attribute requirements demand a systematic approach to education and training of regulatory staff, licensees/registrants and service providers to ensure commensurate competence in performance of responsibilities and duties to specified standards. In order to address issues of competencies required in radiation safety a national programme for qualification and certification has been initiated for regulatory staff, operators, radiation safety officers and qualified experts. Since the inception of this programme in 1993, 40 training events have been organized involving 423 individuals. This programme is at various levels of implementation due to financial and human resource constraints. A department for Human Resource Development and Research was established in 2000 to enhance and ensure the sustainability of the effectiveness of capacity building in radiation safety. (author)

Technical regulations on the general design and safety criteria for design and construction of nuclear reactors of May 1975

International Nuclear Information System (INIS)

1975-05-01

These Technical Regulations published on 5th September 1975 were made in implementation of Section 33 of Decree No 7/9141 on the procedure for the licensing of nuclear installations. They serve as a guide to licensing authorities, project designers and operators in the nuclear field and therefore provide general criteria for safety standards, engineering codes, siting considerations, design bases for overall environmental radiation protection, and also deal with reactor core design, instrumentation, control, alarm systems, including an emergency core cooling system. Finally, the safe design of fuel elements must be ensured and fuel storage and handling techniques complied with. (NEA) [fr

Radiation protection and safety guide no. GRPB-G-4: inspection

International Nuclear Information System (INIS)

Schandorf, C.; Darko, O.; Yeboah, J.; Osei, E.K.; Asiamah, S.D.

1995-01-01

The use of ionizing radiation and radiation sources in Ghana is on the increase due to national developmental efforts in Health Care, Food and Agriculture, Industry, Science and Technology. This regulatory Guide has been developed to assist both the Regulatory Body (Radiation Protection Board) and operating organizations to perform systematic inspections commensurate with the level of hazard associated with the application of radiation sources and radioactive materials. The present Guide applies to the Radiation Protection and Safety inspection and/or audit conducted by the Radiation Protection Board or Radiation Safety Officer. The present Guide is applicable in Ghana and to foreign suppliers of radiation sources. The present Guide applies to notifying person, licensee, or registrant and unauthorized practice

Building competence in radiation protection and the safe use of radiation sources. Safety guide

International Nuclear Information System (INIS)

2005-01-01

An essential element of a national infrastructure for radiation protection and safety is the maintenance of an adequate number of competent personnel. This Safety Guide makes recommendations concerning the building of competence in protection and safety, which relate to the training and assessment of qualification of new personnel and retraining of existing personnel in order to develop and maintain appropriate levels of competence. This Safety Guide addresses training in protection and safety aspects in relation to all practices and intervention situations in nuclear and radiation related technologies. This document covers the following aspects: the categories of persons to be trained. The requirements for education, training and experience for each category. The processes of qualification and authorization of persons. A national strategy for building competence

Methods of checking general safety criteria in UML statechart specifications

International Nuclear Information System (INIS)

Pap, Zsigmond; Majzik, Istvan; Pataricza, Andras; Szegi, Andras

2005-01-01

This paper describes methods and tools for safety analysis of UML statechart specifications. A comprehensive set of general safety criteria including completeness and consistency is applied in automated analysis. Analysis techniques are based on OCL expressions, graph transformations and reachability analysis. Two canonical intermediate representations of the statechart specification are introduced. They are suitable for straightforward implementation of checker methods and for the support of the proof of the correctness and soundness of the applied analysis. One of them also serves as a basis of the metamodel of a variant of UML statecharts proposed for the specification of safety-critical control systems. The analysis is extended to object-oriented specifications. Examples illustrate the application of the checker methods implemented by an automated tool-set

Promoting radiation protection and safety for X-ray inspection systems

International Nuclear Information System (INIS)

Maharaj, Harri P.

2008-01-01

This paper aims to present a regulatory perspective on radiation protection and safety relevant to facilities utilizing baggage X-ray inspection systems. Over the past several years there has been rapid growth in the acquisition and utilization of X-ray tube based inspection systems for security screening purposes worldwide. In addition to ensuring compliance with prescribed standards applicable to such X-ray systems, facilities subject to federal jurisdiction in Canada are required to comply with established codes of practice, which, not only are in accordance with occupational health and safety legislation but also are consistent with international guidance. Overall, these measures are aimed at reducing radiation risks and adverse health effects. Data, acquired in the past several years in a number of facilities through various instruments, namely, monitoring and surveillance, radiation safety audits, onsite evaluations, device registration processes and information developed, were considered in conjunction with detrimental traits. Changes are necessary to reduce radiation and safety risks from both an ALARA point of view and an accountability perspective. Establishing, developing, implementing and following a radiation protection program is warranted and advocated. Minimally, such a program shall be managed by a radiation safety officer. It shall promote and sustain a radiation safety culture in the workplace; shall ensure properly qualified individuals operate and service the X-ray systems in accordance with established and authorized procedures; and shall incorporate data recording and life cycle management principles. Such a program should be the norm for a facility that utilizes baggage X-ray inspection systems for security purposes, and it shall be subject to continuous regulatory oversight. (author)

Review of design criteria and safety analysis of safety class electric building for fuel test loop

Energy Technology Data Exchange (ETDEWEB)

Kim, J. Y.

1998-02-01

Steady state fuel test loop will be equipped in HANARO to obtain the development and betterment of advanced fuel and materials through the irradiation tests. HANARO fuel test loop was designed for CANDU and PWR fuel testing. Safety related system of Fuel Test Loop such as emergency cooling water system, component cooling water system, safety ventilation system, high energy line break mitigation system and remote control room was required 1E class electric supply to meet the safety operation in accordance with related code. Therefore, FTL electric building was designed to construction and install the related equipment based on seismic category I. The objective of this study is to review the design criteria and analysis the safety function of safety class electric building for fuel test loop, and this results will become guidance for the irradiation testing in future. (author). 10 refs., 6 tabs., 30 figs.

New ICRP recommendations and radiation safety of an NPP

International Nuclear Information System (INIS)

Janzekovic, H.

2007-01-01

In March 2007 the fundamental radiation protection recommendations used world-widely in nuclear facilities were approved by the ICRP. Implementation of radiation safety standards in an NPP is a challenging issue related to all NPP phases from planning a site and its design to its decommissioning also because if neglected it could be very difficult if not impossible to implement improvement of radiation safety later during operation or decommissioning without a substantial cost. The standards are changing with a period of 15 years which is small regarding a prolonged lifetime of many NPPs and also foreseen lifetime of new NPPs, i.e. 60 years. The new recommendations are actually an upgrading of the ICRP 60. Among other changes new sets of wR and wT are given, as well as an update of around 50 different values related to doses. Two new concepts are also tackled i.e. terrorist attacks and protection of the environment. The influence of the new recommendations on the radiation safety of NPPs can be analysed by a selection of four renewed or new concepts: types of exposure situation, dose constraints, source-related approach and safety and security. Their implementation could lead to upgrading the radiation safety of future or existing NPPs as well as of decommissioning processes. Some of the concepts were already extensively and successfully used by designers of modifications or of new NPPs, as well as by operators. (author)

Standards for radiation protection instrumentation: design of safety standards and testing procedures

International Nuclear Information System (INIS)

Meissner, Frank

2008-01-01

This paper describes by means of examples the role of safety standards for radiation protection and the testing and qualification procedures. The development and qualification of radiation protection instrumentation is a significant part of the work of TUV NORD SysTec, an independent expert organisation in Germany. The German Nuclear Safety Standards Commission (KTA) establishes regulations in the field of nuclear safety. The examples presented may be of importance for governments and nuclear safety authorities, for nuclear operators and for manufacturers worldwide. They demonstrate the advantage of standards in the design of radiation protection instrumentation for new power plants, in the upgrade of existing instrumentation to nuclear safety standards or in the application of safety standards to newly developed equipment. Furthermore, they show how authorities may proceed when safety standards for radiation protection instrumentation are not yet established or require actualization. (author)

The Advanced Light Source (ALS) Radiation Safety System

International Nuclear Information System (INIS)

Ritchie, A.L.; Oldfather, D.E.; Lindner, A.F.

1993-08-01

The Advanced Light Source (ALS) at the Lawrence Berkeley Laboratory (LBL) is a 1.5 Gev synchrotron light source facility consisting of a 120 kev electron gun, 50 Mev linear accelerator, 1.5 Gev booster synchrotron, 200 meter circumference electron storage ring, and many photon beamline transport systems for research. Figure 1. ALS floor plan. Pairs of neutron and gamma radiation monitors are shown as dots numbered from 1 to 12. The Radiation Safety System for the ALS has been designed and built with a primary goal of providing protection against inadvertent personnel exposure to gamma and neutron radiation and, secondarily, to enhance the electrical safety of select magnet power supplies

A prediction model for the radiation safety management behavior of medical cyclotrons

International Nuclear Information System (INIS)

Jung, Ji Hye; Han, Eun Ok; Kim, Ssang Tae

2008-01-01

This study attempted to provide reference materials for improving the behavior level in radiation safety managements by drawing a prediction model that affects the radiation safety management behavior because the radiation safety management of medical Cyclotrons, which can be used to produce radioisotopes, is an important factor that protects radiation caused diseases not only for radiological operators but average users. In addition, this study obtained follows results through the investigation applied from January 2 to January 30, 2008 for the radiation safety managers employed in 24 authorized organizations, which have already installed Cyclotrons, through applying a specific form of questionnaire in which the validity was guaranteed by reference study, site investigation, and focus discussion by related experts. The radiation safety management were configured as seven steps: step 1 is a production preparation step, step 2 is an RI production step, step 3 is a synthesis step, step 4 is a distribution step, step 5 is a quality control step, step 6 is a carriage container packing step, and step 7 is a transportation step. It was recognized that the distribution step was the most exposed as 15 subjects (62.5%), the items of 'the sanction and permission related works' and 'the guarantee of installation facilities and production equipment' were the most difficult as 9 subjects (37.5%), and in the trouble steps in such exposure, the item of 'the synthesis and distribution' steps were 4 times, respectively (30.8%). In the score of the behavior level in radiation safety managements, the minimum and maximum scores were 2.42 and 4.00, respectively, and the average score was 3.46 ± 0.47 out of 4. Prosperity and well-being programs in the behavior and job in radiation safety managements (r=0.529) represented a significant correlation statistically. In the drawing of a prediction model based on the factors that affected the behavior in radiation safety managements, general

Exemption of the use of radiation from the safety licence and reporting obligation

International Nuclear Information System (INIS)

1999-07-01

The primary means of controlling the use of radiation is the safety licence procedure. The safety licence, and the granting of the licence, are regulated in the section 16 of the Finnish Radiation Act (592/1991). In section 17 of the act, certain practices are exempted from the safety licence. In addition to these practices, the Radiation and Nuclear Safety (STUK) may (on the basis of the same legal clause) exempt other types of radiation use from the safety licence, if it is possible to ascertain with sufficient reliability that the use of the radiation will not cause damage or danger to health. This guide presents the conditions applying to exemption from the safety licence for the use of radiation and reporting obligation, and also the exemption values for radioactive substances which, if exceeded, will entail the application of the safety licence and notification procedure for the use of radiation in question. The guide also presents exemptions in the use of exemption values, and requirements associated with the exemption of radiation appliances. However, the guide does not apply to the use of nuclear energy

Exemption of the use of radiation from the safety licence and reporting obligation

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

The primary means of controlling the use of radiation is the safety licence procedure. The safety licence, and the granting of the licence, are regulated in the section 16 of the Finnish Radiation Act (592/1991). In section 17 of the act, certain practices are exempted from the safety licence. In addition to these practices, the Radiation and Nuclear Safety (STUK) may (on the basis of the same legal clause) exempt other types of radiation use from the safety licence, if it is possible to ascertain with sufficient reliability that the use of the radiation will not cause damage or danger to health. This guide presents the conditions applying to exemption from the safety licence for the use of radiation and reporting obligation, and also the exemption values for radioactive substances which, if exceeded, will entail the application of the safety licence and notification procedure for the use of radiation in question. The guide also presents exemptions in the use of exemption values, and requirements associated with the exemption of radiation appliances. However, the guide does not apply to the use of nuclear energy.

Radiation safety handbook for ionizing and nonionizing radiation

International Nuclear Information System (INIS)

Kincaid, C.B.

1976-10-01

The Handbook is directed primarily to users of radiation sources throughout the Food and Drug Administration. Specific precautions regarding the possession and use of radiation sources in meeting the Agency's objectives are an inherent responsibility of all employees. In addition, the increased emphasis on occupational safety and health and the responsibilities placed on the Department by Public Law and Executive Order make it mandatory that all organizational levels and activities conform to the intent of this Handbook. The policies and procedures described in this document apply to all Agency operators and activities and are intended to protect employees and the general public

Radiation safety. Handbook for laboratory workers in the USA

International Nuclear Information System (INIS)

Hotte, E.D.; Krueger, D.J.; Connor, K.

2000-01-01

The aim of the Handbook is to provide a source of information on radiation safety for those who are involved in the use of ionizing radiation in the laboratory. The potential reader may be a laboratory worker in the university or biomedical setting or the safety professional who desires a basic understanding of radiation protection within the research environment. The Handbook may be used as a reference by the radiation protection specialist or Radiation Safety Officer. To this end, liberal use is made of Appendices to make the Handbook a source of reference for a wide spectrum of readership while avoiding complicating the main body of the text. Each chapter or appendix is designed to stand alone. A complete reading of the Handbook will show that topics may be covered more than once. For example, one may read about the hazards and protective measures on handling radioiodine in Chapter 5 on Practical Radiation Protection as well as in Appendix 19 on Safe Handling of 125 I. Extensive use of figures, rather than tables has been made to present data, in the belief that these produce a good visual representation to a level of precision which is sufficient for most purposes of radiation protection in laboratories. The reader must remember that this Handbook should be taken as a guide only to the applicable regulations. You must consult the appropriate state or federal regulation directly or receive advice of a qualified radiation safety professional. Also, some information in the Appendices, such as commercially available training institutions or radioactive waste brokers, may change with time. Telephone numbers are given for the reader to call directly and check the services provided

Overview criteria for the environmental, safety and health evaluation of remedial action project planning

International Nuclear Information System (INIS)

Stenner, R.D.; Denham, D.H.

1984-10-01

Overview criteria (i.e., subject areas requiring review) for evaluating remedial action project plans with respect to environmental, safety and health issues were developed as part of a Department of Energy, Office of Operational Safety, technical support project. Nineteen elements were identified as criteria that should be addressed during the planning process of a remedial action (decontamination and decommissioning) project. The scope was interpreted broadly enough to include such environmental, safety and health issues as public image, legal obligation and quality assurance, as well as more obvious concerns such as those involving the direct protection of public and worker health. The nineteen elements are discussed along with suggested ways to use a data management software system to organize and report results

Radiation protection - Performance criteria for radiobioassay. Part 1: General principles

International Nuclear Information System (INIS)

2001-01-01

International Standard ISO 12790-1 was prepared by Technical Committee ISO/TC 85, Nuclear energy, Subcommittee SC 2, Radiation protection. ISO 12790 consists of the following parts, under the general title Radiation protection - Performance criteria for radiobioassay: Part 1: General principles; and Part 2: Rationale and specific applications This part of ISO 12790 provides criteria for quality assurance and control, evaluation of performance and the accreditation of radiobioassay service laboratories. Criteria and guidance for direct radiobioassay ( in vivo) and indirect radiobioassay ( in vitro) are given in separate clauses of this part of ISO 12790. This part of ISO 12790 addresses: a) the accuracy of direct ( in vivo) measurements of activity and quantities of selected important radionuclides in test phantoms and indirect ( in vitro) measurements of activity and quantities of selected important radionuclides in test samples; b) methods for determining the minimum detectable amount; c) minimum testing levels and testing ranges; d) requirements for reporting radiobioassay results by service laboratories; e) quality assurance in service laboratories; f) quality control in service laboratories; g) protocol for reporting test evaluations by service laboratories to the testing laboratory; h) default procedures when the service laboratory customer does not specify the performance criteria. The scope of this part of ISO 12790 does not include: a) detailed radiochemical methods for separating radionuclides from biological samples; b) detailed procedures for in vivo and in vitro radioactivity measurements; c) metabolic data and mathematical models for converting radiobioassay results into absorbed dose and dose equivalent; d) procedures for the preparation and distribution of test samples and phantoms by the testing laboratories. Analytical methods for radiobioassay are not currently standardized, but are available in the literature. Guidance for converting

Food safety assurance systems: Microbiological testing, sampling plans, and microbiological criteria

NARCIS (Netherlands)

Zwietering, M.H.; Ross, T.; Gorris, L.G.M.

2014-01-01

Microbiological criteria give information about the quality or safety of foods. A key component of a microbiological criterion is the sampling plan. Considering: (1) the generally low level of pathogens that are deemed tolerable in foods, (2) large batch sizes, and (3) potentially substantial

Dose and temperature criteria for radiation chlorination of ethane

International Nuclear Information System (INIS)

Prasil, Z.

1979-01-01

General criteria determining the region of dose rates and temperatures at which a radiation-induced chain reaction proceeds are applied to a series of subsequent and competitive chain reactions of the chlorination of ethane and its derivatives. The calculations presume that the reactions proceed in an ideal through-flow chemical reactor with a piston flow. (M.S.)

Delivering a radiation protection dividend: systemic capacity-building for the radiation safety profession in Africa

Directory of Open Access Journals (Sweden)

Julian Hilton

2014-12-01

Full Text Available Many African countries planning to enter the nuclear energy “family” have little or no experience of meeting associated radiation safety demands, whether operational or regulatory. Uses of radiation in medicine in the continent, whether for diagnostic or clinical purposes, are rapidly growing while the costs of equipment, and hence of access to services, are falling fast. In consequence, many patients and healthcare workers are facing a wide array of unfamiliar challenges, both operational and ethical, without any formal regulatory or professional framework for managing them safely. This, combined with heighted awareness of safety issues post Fukushima, means the already intense pressure on radiation safety professionals in such domains as NORM industries and security threatens to reach breaking point. A systematic competency-based capacity-building programme for RP professionals in Africa is required (Resolution of the Third AFRIRPA13 Regional Conference, Nairobi, September 2010. The goal is to meet recruitment and HR needs in the rapidly emerging radiation safety sector, while also addressing stakeholder concerns in respect of promoting and meeting professional and ethical standards. The desired outcome is an RP “dividend” to society as a whole. A curriculum model is presented, aligned to safety procedures and best practices such as Safety Integrity Level and Layer of Protection analysis; it emphasizes proactive risk communication both with direct and indirect stakeholders; and it outlines disciplinary options and procedures for managers and responsible persons for dealing with unsafe or dangerous behavior at work. This paper reports on progress to date. It presents a five-tier development pathway starting from a generic foundation course, suitable for all RP professionals, accompanied by specialist courses by domain, activity or industry. Delivery options are discussed. Part of the content has already been developed and delivered as

Growth of the Female Professional in the Radiation Safety Department

International Nuclear Information System (INIS)

Yoon, J.

2015-01-01

Currently in Korea’s Nuclear Power Plants (KHNP), the number of the female staffs has been increased as planned construction of new NPPs. However the role of the female staffs in NPPs is still limited as before. Because there is the prejudice which the operating and the maintenance work is unsuitable for female owing to the risk of the radiation exposure and the physical weakness. So female staffs mostly belong to the supporting departments. In particular, the proportion of the female staffs is significantly higher in the radiation safety department among those. The ratio is 15% and is twice higher, whereas the total percentage of the female workers in KHNP is 8%. In the past, the women staffs in the radiation safety department were usually charge of the non-technical duties like the radiation exposure dose management and the education for radiation workers. Although the ratio of the women about that is still higher, nowadays, the role of the female workers tends to diversify to technical supports like the radiation protection and the radioactive waste management while increased the proportion of female employees. This trend is expected to continue for many years to come. Thus, in Korea’s NPPs, it is expected that many women will demonstrate their professionalism especially in the radiation safety department than any other departments. This presentation contains the detailed duty and trend about female staffs in the radiation safety department in Korea’s NPPs. (author)

Radiation safety and care of patients

International Nuclear Information System (INIS)

Das, B.K.; Noreen Norfaraheen Lee Abdullah

2012-01-01

The objective of this chapter is to acquaint the reader with radiation safety measures which can be pursued to minimize radiation load to the patient and staff. The basic principle is that all unnecessary administration should be avoided and a number of simple techniques be used to reduce radiation dose. For example, the kidney excretes many radionuclides. Drinking plenty of fluid and frequent bladder emptying can minimize absorbed dose to the bladder. Thyroid blocking agents must be used if radioactive iodine is being administered to avoid unnecessary radiation exposure to the thyroid gland. When it is necessary to administer radioactive substances to a female of childbearing age, the radiation exposure should be minimum and information whether the patient is pregnant or not must be obtained. Alternatives techniques, which do not involve ionizing radiation, should also be considered. (author)

Radiation Safety of Accelerator Facility with Regard to Regulation

International Nuclear Information System (INIS)

Dedi Sunaryadi; Gloria Doloresa

2003-01-01

The radiation safety of accelerator facility and the status of the facilities according to licensee in Indonesia as well as lesson learned from the accidents are described. The atomic energy Act No. 10 of 1997 enacted by the Government of Indonesia which is implemented in Radiation Safety Government Regulation No. 63 and 64 as well as practice-specific model regulation for licensing request are discussed. (author)

Monitoring System For Improving Radiation Safety Management

International Nuclear Information System (INIS)

Osovizky, A.; Paran, J.; Tal, N.; Ankry, N.; Ashkenazi, B.; Tirosh, D.; Marziano, R.; Chisin, R.

1999-01-01

Medi SMARTS (Medical Survey Mapping Automatic Radiation Tracing System), a gamma radiation monitoring system, was installed in a nuclear medicine department. In this paper the evaluation of the system's ability to improve radiation safety management is presented. The system is based on a state of the art software that continuously collects on line radiation measurements for display, analysis and logging. Radiation is measured by GM tubes; the signal is transferred to a data processing unit and then via an RS-485 communication line to a computer. The system automatically identifies the detector type and its calibration factor, thus providing compatibility, maintainability and versatility when changing detectors. Radiation levels are displayed on the nuclear medicine department map at six locations. The system has been operating continuously for more than one year, documenting abnormal events caused by routine operation or failure incidents. In cases where abnormal working conditions were encountered, an alarm message was sent automatically to the supervisor via his tele-pager. An interesting issue observed during the system evaluation, was the inability to distinguish between high radiation levels caused by proper routine operation and those caused by safety failure incidents. The solution included examination of two parameters, radiation levels as well as their duration period. A careful analysis of the historical data, applying the appropriated combined parameters determined for each location, verified that such a system can identify abnormal events, provide alarms to warn in case of incidents and improve standard operating procedures

Nuclear and radiation safety in Mongolia

International Nuclear Information System (INIS)

Batjargala, Erdev

2010-01-01

The main purpose of the paper is to assess legal environment of Mongolia for development of nuclear and radiation safety and security. The Nuclear Energy Agency, regulatory agency of the Government of Mongolia, was founded in the beginning of 2009. Since then, it has formulated the State Policy for Utilization of Radioactive Minerals and Nuclear Energy and the Nuclear Energy Law, regulatory law of the field. The State Great Khural of Mongolia has enacted these acts. By adopting the State Policy and Nuclear Energy Law, which together imported the international standards for nuclear and radiation safety and security, it is possible to conclude that legal environment has formed in Mongolia to explore and process radioactive minerals and utilize nuclear energy and introduce technologies friendly to human health and environment. (author)

A prediction model for the radiation safety management behavior of medical cyclotrons

Energy Technology Data Exchange (ETDEWEB)

Jung, Ji Hye; Han, Eun Ok [Daegu Health College, Daegu (Korea, Republic of); Kim, Ssang Tae [CareCamp Inc., Seoul (Korea, Republic of)

2008-06-15

This study attempted to provide reference materials for improving the behavior level in radiation safety managements by drawing a prediction model that affects the radiation safety management behavior because the radiation safety management of medical Cyclotrons, which can be used to produce radioisotopes, is an important factor that protects radiation caused diseases not only for radiological operators but average users. In addition, this study obtained follows results through the investigation applied from January 2 to January 30, 2008 for the radiation safety managers employed in 24 authorized organizations, which have already installed Cyclotrons, through applying a specific form of questionnaire in which the validity was guaranteed by reference study, site investigation, and focus discussion by related experts. The radiation safety management were configured as seven steps: step 1 is a production preparation step, step 2 is an RI production step, step 3 is a synthesis step, step 4 is a distribution step, step 5 is a quality control step, step 6 is a carriage container packing step, and step 7 is a transportation step. It was recognized that the distribution step was the most exposed as 15 subjects (62.5%), the items of 'the sanction and permission related works' and 'the guarantee of installation facilities and production equipment' were the most difficult as 9 subjects (37.5%), and in the trouble steps in such exposure, the item of 'the synthesis and distribution' steps were 4 times, respectively (30.8%). In the score of the behavior level in radiation safety managements, the minimum and maximum scores were 2.42 and 4.00, respectively, and the average score was 3.46 {+-} 0.47 out of 4. Prosperity and well-being programs in the behavior and job in radiation safety managements (r=0.529) represented a significant correlation statistically. In the drawing of a prediction model based on the factors that affected the behavior in

Law on protection against ionising radiation and nuclear safety in Slovenia

International Nuclear Information System (INIS)

Breznik, B.; Krizman, M.; Skrk, D.; Tavzes, R.

2003-01-01

The existing legislation related to nuclear and radiation safety in Slovenia was introduced in 80's. The necessity for the new law is based on the new radiation safety standards (ICRP 60) and the intention of Slovenia to harmonize the legislation with the European Union. The harmonization means adoption of the basic safety standards and other relevant directives and regulations of Euratom. The nuclear safety section of this law is based on the legally binding international conventions ratified by Slovenia. The general approach is similar to that of some members of Nuclear Energy Agency (OECD). The guidelines of the law were set by the Ministry of the Environment and Spatial Planning, Nuclear Safety Administration, and Ministry of Health. The expert group of the Ministry of Environment and Spatial Planning and the Ministry of Health together with the representatives of the users of the ionising sources and representatives of the nuclear sector, prepared the draft of the subject law. The emphasis in this paper is given to main topics and solutions related to the control of the occupationally exposed workers, radiation safety, licensing, nuclear and waste safety, and radiation protection of people and patients. (authors)

The personnel protection system for a Synchrotron Radiation Accelerator Facility: Radiation safety perspective

International Nuclear Information System (INIS)

Liu, J.C.

1993-05-01

The Personnel Protection System (PPS) at the Stanford Synchrotron Radiation Laboratory is summarized and reviewed from the radiation safety point of view. The PPS, which is designed to protect people from radiation exposure to beam operation, consists of the Access Control System (ACS) and the Beam Containment System (BCS), The ACS prevents people from being exposed to the very high radiation level inside the shielding housing (also called a PPS area). The ACS for a PPS area consists of the shielding housing and a standard entry module at every entrance. The BCS prevents people from being exposed to the radiation outside a PPS area due to normal and abnormal beam losses. The BCS consists of the shielding (shielding housing and metal shielding in local areas), beam stoppers, active current limiting devices, and an active radiation monitor system. The system elements for the ACS and BCS and the associated interlock network are described. The policies and practices in setting up the PPS are compared with some requirements in the US Department of Energy draft Order of Safety of Accelerator Facilities

Evolution of Radiation Safety Culture in Africa: Impact of the Chernobyl Accident

International Nuclear Information System (INIS)

Elegba, S.

2016-01-01

The use of ionizing radiation in Africa is more than a century old but the awareness for radiation safety regulation is still a work in progress. The nuclear weapon tests carried out in the Sahara Desert during the early 1960’s and the resultant radiation fallout that drifted into West Africa with the northeasterly winds provided the first organized response to the hazards of ionizing radiation in Nigeria. The Nigerian Government in 1964 established the Federal Radiation Protection Service (FRPS) at the Physics Department of the University of Ibadan but without the force of law. In 1971, draft legislation on Nuclear Safety and Radiation Protection was submitted to Government for consideration and promulgation. It never went beyond a draft until June 1995 only after IAEA intervention! The April 1986 Chernobyl nuclear accident unfortunately did not provoke as much reaction from African countries, probably because of geography and climate: Africa is far from Ukraine and in April the winds blow from SW-NE, unlike if it had happened in December when the wind direction would have been NE-SW and Africa would have been greatly impacted with little or no radiation safety infrastructure to detect the radiation fallout or to respond to it; and weak economic infrastructure to mitigate the economic impact of such radioactive deposits on agriculture and human health. Africa was shielded by both geography and climate; but not for long. By 1988, some unscrupulous businessmen exported to Nigeria and to several African countries radiation contaminated beef and dairy products which were meant for destruction in Europe. This led to the establishment of laboratories in several African countries for the monitoring of radiation contamination of imported foods. Fortunately, the international response to the Chernobyl accident was swift and beneficial to Africa and largely spurred the establishment of radiation safety infrastructure in most if not all African Member States. Notably

Radiation safety aspects of high energy particle accelerators

International Nuclear Information System (INIS)

Subbaiah, K.V.

2007-01-01

High-energy accelerators are widely used for various applications in industry, medicine and research. These accelerators are capable of accelerating both ions and electrons over a wide range of energy and subsequently are made to impinge on the target materials. Apart from generating intended reactions in the target, these projectiles can also generate highly penetrating radiations such as gamma rays and neutrons. Over exposure to these radiations will cause deleterious effects on the living beings. Various steps taken to protect workers and general public from these harmful radiations is called radiation safety. The primary objective in establishing permissible values for occupational workers is to keep the radiation worker well below a level at which adverse effects are likely to be observed during one's life time. Another objective is to minimize the incidence of genetic effects for the population as a whole. Today's presentation on radiation safety of accelerators will touch up on the following sub-topics: Types of particle accelerators and their applications; AERB directives on dose limits; Radiation Source term of accelerators; Shielding Design-Use of Transmission curves and Tenth Value layers; Challenges for accelerator health physicists

Radiation safety standards : an environmentalist's approach

International Nuclear Information System (INIS)

Murthy, M.S.S.S.

1977-01-01

An integrated approach to the problem of environmental mutagenic hazards leads to the recommendation of a single dose-limit to the exposure of human beings to all man-made mutagenic agents including chemicals and radiation. However, because of lack of : (1) adequate information on chemical mutagens, (2) sufficient data on their risk estimates and (3) universally accepted dose-limites, control of chemical mutagens in the environment has not reached that advanced stage as that of radiation. In this situation, the radiation safety standards currently in use should be retained at their present levels. (M.G.B.)

Basic Safety Standards for Radiation Protection

International Nuclear Information System (INIS)

1962-01-01

Pursuant to the provisions of its Statute relevant to the adoption and application of safety standards for protection against radiation, the Agency convened a panel of experts which formulated the Basic Safety Standards set forth in this publication. The panel met under the chairmanship of Professor L. Bugnard, Director of the French Institut National d'Hygiene, and representatives of the United Nations and of several of its specialized agencies participated in its work. The Basic Safety Standards thus represent the result of a most careful assessment of the variety of complex scientific and administrative problems involved. Nevertheless, of course, they will need to be revised from time to time in the light of advances in scientific knowledge, of comments received from Member States and of the work of other competent international organizations. The Agency's Board of Governors in June 1962 approved the Standards as a first edition, subject to later revision as mentioned above, and authorized Director General Sigvard Eklund to apply the Standards in Agency and Agency-assisted operations and to invite Governments of Member States to take them as a basis in formulating national regulations or recommendations on protection against the dangers arising from ionizing radiations. It is mainly for this last purpose that the Basic Safety Standards are now being published in the Safety Series; but it is hoped that this publication will also interest a much wider circle of readers.

Radiation Safety in Industrial Radiography. Specific Safety Guide (French Edition); Surete radiologique en radiographie industrielle

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-05-15

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in Horizontal-Ellipsis shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography.

Assessment of occupational exposure due to external sources of radiation. Safety guide

International Nuclear Information System (INIS)

2000-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. The three Safety Guides on occupational radiation protection are jointly sponsored by the IAEA and the International Labour Office. The Agency gratefully acknowledges the contribution of the European Commission to the development of the present Safety Guide. The present Safety Guide addresses the assessment of exposure due to external sources of radiation in the workplace. Such exposure can result from a number of sources within a workplace, and the monitoring of workers and the workplace in such situations is an integral part of any occupational radiation protection programme. The assessment of exposure due to external radiation sources depends critically upon knowledge of the radiation type and energy and the conditions of exposure. The present Safety Guide reflects the major changes over the past decade in international practice in external dose assessment

Radiation safety program in high dose rate brachytherapy facility at INHS Asvini

Directory of Open Access Journals (Sweden)

Kirti Tyagi

2014-01-01

Full Text Available Brachytherapy concerns primarily the use of radioactive sealed sources which are inserted into catheters or applicators and placed directly into tissue either inside or very close to the target volume. The use of radiation in treatment of patients involves both benefits and risks. It has been reported that early radiation workers had developed radiation induced cancers. These incidents lead to continuous work for the improvement of radiation safety of patients and personnel The use of remote afterloading equipment has been developed to improve radiation safety in the delivery of treatment in brachytherapy. The widespread adoption of high dose rate brachytherapy needs appropriate quality assurance measures to minimize the risks to both patients and medical staff. The radiation safety program covers five major aspects: quality control, quality assurance, radiation monitoring, preventive maintenance, administrative measures and quality audit. This paper will discuss the radiation safety program developedfor a high dose rate brachytherapy facility at our centre which may serve as a guideline for other centres intending to install a similar facility.

Assessment of occupational exposure due to external sources of radiation. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. The three Safety Guides on occupational radiation protection are jointly sponsored by the IAEA and the International Labour Office. The Agency gratefully acknowledges the contribution of the European Commission to the development of the present Safety Guide. The present Safety Guide addresses the assessment of exposure due to external sources of radiation in the workplace. Such exposure can result from a number of sources within a workplace, and the monitoring of workers and the workplace in such situations is an integral part of any occupational radiation protection programme. The assessment of exposure due to external radiation sources depends critically upon knowledge of the radiation type and energy and the conditions of exposure. The present Safety Guide reflects the major changes over the past decade in international practice in external dose assessment

Assessment of occupational exposure due to external sources of radiation. Safety guide

International Nuclear Information System (INIS)

1999-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. The three Safety Guides on occupational radiation protection are jointly sponsored by the IAEA and the International Labour Office. The Agency gratefully acknowledges the contribution of the European Commission to the development of the present Safety Guide. The present Safety Guide addresses the assessment of exposure due to external sources of radiation in the workplace. Such exposure can result from a number of sources within a workplace, and the monitoring of workers and the workplace in such situations is an integral part of any occupational radiation protection programme. The assessment of exposure due to external radiation sources depends critically upon knowledge of the radiation type and energy and the conditions of exposure. The present Safety Guide reflects the major changes over the past decade in international practice in external dose assessment

Basic safety standards for radiation protection. 1982 ed

International Nuclear Information System (INIS)

1982-01-01

The International Atomic Energy Agency, the World Health Organization, the International Labour Organisation and the Nuclear Energy Agency of the OECD have undertaken to provide jointly a world-wide basis for harmonized and up-to-date radiation protection standards. The new Basic Safety Standards for Radiation Protection are based upon the latest recommendations by the International Commission on Radiological Protection (ICRP) which are essentially contained in its Publication No.26. These new Basic Safety Standards have been elaborated by an Advisory Group of Experts which met in Vienna from 10-14 October 1977, from 23-27 October 1978 and from 1-12 December 1980 under the joint auspices of the IAEA, ILO, WHO and the Nuclear Energy Agency of the OECD. Comments on the draft Basic Safety Standards received from Member States and relevant organizations were taken into account by the Advisory Group in the process of preparation of the revised Basic Safety Standards for Radiation Protection, which are published by the IAEA on behalf of the four sponsoring organizations. One of the main features of this revision is an increased emphasis on the recommendation to keep all exposures to ionizing radiation as low as reasonably achievable, economic and social factors being taken into account; consequently, radiation protection should not only apply the basic dose limits but also comply with this recommendation. Detailed guidance is given to assist those who have to decide on the implementation of this recommendation in particular cases. Another important feature is the recommendation of a more coherent method for achieving consistency in limiting risks to health, irrespective of whether the risk is of uniform or non-uniform exposure of the body.

Radiation in the human environment: health effects, safety and acceptability

International Nuclear Information System (INIS)

Gonzalez, A.J.; Anderer, J.

1990-01-01

This paper reports selectively on three other aspects of radiation (used throughout to mean ionizing radiation) in the human environment: the human health effects of radiation, radiation safety policy and practices, and the acceptability of scientifically justified practices involving radiation exposures. Our argument is that the science of radiation biology, the judgemental techniques of radiation safety, and the social domain of radiation acceptability express different types of expertise that should complement - and not conflict with or substitute for - one another. Unfortunately, communication problems have arisen among these three communities and even between the various disciplines represented within a community. These problems have contributed greatly to the misperceptions many people have about radiation and which are frustrating a constructive dialogue on how radiation can be harnessed to benefit mankind. Our analysis seeks to assist those looking for a strategic perspective from which to reflect on their interaction with practices involving radiation exposures. (author)

Preliminary report of radiological safety to hydrology 1993 campaign

International Nuclear Information System (INIS)

Badano, A.; Suarez Antola, R.; Dellepere, A.; Barreiro, M.

1993-01-01

This report has been prepared based on the interaction between project managers and division radiological Protection and Nuclear Safety. In seeking to establish a basis for approval from the point of view of radiation safety practices . The idea for the audit has been provided at all times because the interest was the exchange of ideas and the use of common sense to improve the safety of radioactive substances, security of operators and public safety and environment.The above shows that in the planned radiation safety condition described in this report,the practice can be carried out according to the criteria of safety accepted .

Radiation Safety (General) Regulations 1983 (Western Australia)

International Nuclear Information System (INIS)

1983-01-01

The provisions of the Regulations cover, inter alia, the general precautions and requirements relating to radiation safety of the public and radiation workers and registration of irradiating apparatus or premises on which such apparatus is operated. In addition, the Regulations set forth requirements for the operation of such apparatus and for the premises involved. (NEA) [fr

The Advanced Light Source (ALS) Radiation Safety System

International Nuclear Information System (INIS)

Ritchie, A.; Oldfather, D.; Lindner, A.

1993-05-01

The Advanced Light Source (ALS) at the Lawrence Berkeley Laboratory (LBL) is a 1.5 GeV synchrotron light source facility consisting of a 120 keV electron gun, 50 MeV linear accelerator, 1.5 Gev booster synchrotron, 200 meter circumference electron storage ring, and many photon beamline transport systems for research. The Radiation Safety System for the ALS has been designed and built with a primary goal of providing protection against inadvertent personnel exposure to gamma and neutron radiation and, secondarily, to enhance the electrical safety of select magnet power supplies

Radiation protection and radiation safety: CERN and its host states to sign a tripartite agreement.

CERN Multimedia

2010-01-01

On 15 November CERN and its Host States will sign a tripartite agreement that replaces the existing bilateral agreements in matters of radiation protection and radiation safety at CERN. It will provide, for the first time, a single forum where the three parties will discuss how maximum overall safety can best be achieved in the specific CERN context.   CERN has always maintained close collaboration with its Host States in matters of safety. “The aim of this collaboration is especially to ensure best practice in the field of radiation protection and the safe operation of CERN’s facilities”, explains Ralf Trant, Head of the Occupational Health & Safety and Environmental Protection (HSE) Unit. Until today, CERN’s collaboration with its Host States was carried out under two sets of bilateral agreements: depending on which side of the French-Swiss border they were being carried out on, a different framework applied to the same activities. This approach has b...

Construction of data base for radiation safety assessment of low dose ionizing radiation

International Nuclear Information System (INIS)

Saigusa, Shin

2001-01-01

Data base with an electronic text on the safety assessment of low dose ionizing radiation have been constructed. The contents and the data base system were designed to provide useful information to Japanese citizens, radiation specialists, and decision makers for a scientific and reasonable understanding of radiation health effects, radiation risk assessment, and radiation protection. The data base consists of the following four essential parts, namely, ORIGINAL DESCRIPTION, DETAILED INFORMATION, TOPIC INFORMATION, and RELATED INFORMATION. The first two parts of the data base are further classified into following subbranches: Radiobiological effects, radiation risk assessment, and radiation exposure and protection. (author)

Radiation protection criteria for cases of probabilistic disruptive events

International Nuclear Information System (INIS)

Beninson, D.J.

1985-01-01

The individual risk limitation for the case of probabilistic disruptive events is studied, when the radiation effects cease to be only stochastic; the proposed criterion is applied for the case of high level waste repositories. The protection's optimization results from the differential cost-benefit. More general procedures of decision theory that use probabilistically defined utility functions are considered for its calculation. These more general procedures can be applied also in cases where radiation exposures are only potential, to optimize the required level of safety features. It is shown that for disruptive events of low probability and large resulting consequences, the concept of 'expectation' of consequence can not be used in decision making, but that the use of probabilistically based utility functions can conceptually assure a consistent approach in deciding the required level of safety. The use of utility functions of logaritmic form to assign weights to consequences involving different loss of life is explored (M.E.L.) [es

Generalized Safety and Efficacy of Simplified Intravenous Thrombolysis Treatment (SMART) Criteria in Acute Ischemic Stroke

DEFF Research Database (Denmark)

Sørensen, Sigrid B; Barazangi, Nobl; Chen, Charlene

2016-01-01

BACKGROUND: Common intravenous recombinant tissue plasminogen activator (IV rt-PA) exclusion criteria may substantially limit the use of thrombolysis. Preliminary data have shown that the SMART (Simplified Management of Acute stroke using Revised Treatment) criteria greatly expand patient...... eligibility by reducing thrombolysis exclusions, but they have not been assessed on a large scale. We evaluated the safety and efficacy of general adoption of SMART thrombolysis criteria to a large regional stroke network. METHODS: Retrospective analysis of consecutive patients who received IV thrombolysis...... within a regional stroke network was performed. Patients were divided into those receiving thrombolysis locally versus at an outside hospital. The primary outcome was modified Rankin Scale score (≤1) at discharge and the main safety outcome was symptomatic intracranial hemorrhage (sICH) rate. RESULTS...

Selection of tolerable risk criteria for dam safety decision making

International Nuclear Information System (INIS)

Nielsen, N.M.; Hartford, D.N.D.; MacDonald, T.F.

1994-01-01

Risk assessment has received increasing attention in recent years as a means of aiding decision making on dams by providing systematic and rational methods for dealing with risk and uncertainty. Risk assessment is controversial and decisions affecting risk to life are the most controversial. Tolerable criteria, based on the risks that society is prepared to accept in order to avoid excessive costs, set bounds within which risk-based decisions may be made. The components of risk associated with dam safety are addressed on an individual basis and criteria established for each component, thereby permitting flexibility in the balance between component risk and avoiding the problems of placing a monetary value on life. The guiding principle of individual risk is that dams do not impose intolerable risks on any individual. A risk to life of 1 in 10 4 per annum is generally considered the maximum tolerable risk. When considering societal risk, the safety of a dam should be proportional to the consequences of its failure. Risks of financial losses beyond the corporation's ability to finance should be so low as to be considered negligible. 17 refs., 3 figs

X-ray and nuclear radiation facilities: personnel safety features

International Nuclear Information System (INIS)

Mason, W.J.; Pipes, E.W.; Rucker, T.R.; Smith, D.N.; West, C.M.

1976-10-01

The Oak Ridge Y-12 Plant is a research and production installation. The nature and versatility of this work require the use of a large number and variety of x-ray and radiographic sources for nondestructive testing and material analyses. Presently, there are over 80 x-ray generators in the plant, which range in size from small, portable units which operate at a less than 50 kilovolts potential and 0.1 milliampere current to an electron linear accelerator which operates at 12-million electron volts and produces a radiation beam of such intensity that it could deliver a lethal dose to man in a fraction of a minute. There are also almost 50 gamma and neutron sources in use in the plant. These units range in size from a few millicuries to several hundred curies. Although the radiation safety at each of these facilities was considered adequate, the administrative and maintenance procedures became unduly complicated. Accordingly, engineering standards and uniform operating procedures were considered necessary to alleviate these complications and, in so doing, provide an improved measure of radiation safety. Development and implementation of these standards are described and the general philosophy and approach to these standards are outlined. Use of a matrix (type of installation versus radiation safety feature) to facilitate equipment classification and personnel safety feature requirements is presented. Included is a set of the standards showing formats, matrices, etc., and the detailed standards for each safety feature

The Radiation Safety Interlock System for Top-Up Mode Operation at NSRRC

CERN Document Server

Chen Chien Rong; Kao, Sheau-Ping; Liu, Joseph; Sheu, Rong-Jiun; Wang, Jau-Ping

2005-01-01

The radiation safety interlock systems of NSRRC have been operated for more than a decade. Some modification actions have been implemented in the past to perfect the safe operation. The machine and its interlock system were originally designed to operate at the decay mode. Recently some improvement programs to make the machine injection from original decay mode to top-up mode at NSRRC has initiated. For users at experimental area the radiation dose resulted from top-up re-fill injections where safety shutters of beam-lines are opened will dominate. In addition to radiation safety action plans such as upgrading the shielding, enlarging the exclusion zones and improving the injection efficiency, the interlock system for top-up operation is the most important to make sure that injection efficiency is acceptable. To ensure the personnel radiation safety during the top-up mode, the safety interlock upgrade and action plans will be implemented. This paper will summarize the original design logic of the safety inter...

Winning public confidence in radiation safety standards

International Nuclear Information System (INIS)

Skelcher, B.W.

1982-01-01

Evaluations using cost/benefit analysis and the ALARA principle should take account of psychological as well as material considerations. Safety is a basic human need which has to be met. It is also subjective and therefore has to be understood by the individual. The professional health physicist has a duty to see that radiation safety is understood by the general public. (author)

Nuclear safety and radiation protection consideration in the design of research and development facility

International Nuclear Information System (INIS)

Akbar, M.R.

2010-01-01

Nuclear safety is a critically important aspect that must be considered in the design of a nuclear facility in order to ensure the protection of the workers, public and environment. This paper looks at the methodology, approach and incorporation of this aspect, specifically into the design of a research and development facility. The Health, Safety and Environmental Basis of Design is an initial analysis of nuclear safety and radiation protection considerations that is performed during the conceptual design phase and sets the baseline for what the design of the facility must conform to. It consists of general nuclear safety design principles, such as defence in depth and optimisation considerations, and a hazard management strategy. Following the Health, Safety and Environmental Basis of Design, a Preliminary Safety Assessment Report is generated during the basic design phase in conjunction with various analyses in order to assess the impact of hazards on the workers and members of the public. This assessment follows a hazard graded approach where the depth of the analysis will be determined by the impact of the worst case accident scenario in the facility. The assessment also includes a waste management strategy which is an essential aspect to be considered in the design in order to minimize the generation of waste. The safety assessment also demonstrates compliance to dose limits and risk criteria for the workers and members of the public set by the regulatory body and supported by a legal framework. Measures are taken to keep risk as low as reasonably achievable and prevent transgression of the risk and dose limits. However, a balance needs to be maintained between 5 reducing these doses further and the cost of such a reduction, which is known as optimization. It is therefore imperative to have nuclear safety specialists analyse the design in order to protect the worker and member of the public from unwarranted exposure to nuclear radiation. (author)

Explanation of diagnosis criteria for radiation sickness from internal exposure

International Nuclear Information System (INIS)

Xing Zhiwei; Jiang Enhai; Du Jianying; Bai Guang

2012-01-01

A revised edition of the Diagnostic Criteria for Radiation Sickness from Internal Exposure has been approved and issued by the Ministry of Health. It is necessary to research the internal radiation sickness to adapt to the current serious anti-terrorism situation. This standard was enacted based on the extensive research of related literature, from which 12 cases with internal radiation sickness and screened out were involving 7 types of radionuclide. The Development of Emergency Response Standard Extension Framework: Midterm Evaluation Report is the main reference which approved by the International Atomic Energy Agency and World Health Organization. This amendment contains many new provisions such as internal radiation sickness effects models and threshold dose, and the appendix added threshold dose of serious deterministic effects induced by radionuclide intake and radiotoxicology parameters of some radionuclides. In order to understand and implement this standard, and to diagnose and treat the internal radiation sickness correctly, the contents of this standard were interpreted in this article. (authors)

Criteria for Radionuclide Activity Concentrations for Food and Drinking Water

International Nuclear Information System (INIS)

2016-04-01

Requirements for the protection of people from the harmful consequences of exposure to ionizing radiation, for the safety of radiation sources and for the protection of the environment are established in IAEA Safety Standards Series No. GSR Part 3, Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. GSR Part 3 requires that the regulatory body or other relevant authority establish specific reference levels for exposure due to radionuclides in commodities, including food and drinking water. The reference level is based on an annual effective dose to the representative person that generally does not exceed a value of about 1 mSv. International standards have been developed by the Food and Agriculture Organization of the United Nations/World Health Organization (FAO/WHO) Codex Alimentarius Commission for levels of radionuclides contained in food traded internationally that contains, or could potentially contain, radioactive substances as a consequence of a nuclear or radiological emergency. International standards have also been developed by the WHO for radionuclides contained in drinking water, other than in a nuclear or radiological emergency. These international standards provide guidance and criteria in terms of levels of individual radiation dose, levels of activity concentration of specific radionuclides, or both. The criteria derived in terms of levels of activity concentration in the various international standards differ owing to a number of factors and assumptions underlying the common objective of protecting public health in different circumstances. This publication considers the various international standards to be applied at the national level for the assessment of levels of radionuclides in food and in drinking water in different circumstances for the purposes of control, other than in a nuclear or radiological emergency. It collates and provides an overview of the different criteria used in assessing and

Radiation safety considerations and compliance within equine veterinary clinics: Results of an Australian survey

International Nuclear Information System (INIS)

Surjan, Y.; Ostwald, P.; Milross, C.; Warren-Forward, H.

2015-01-01

Objective: To examine current knowledge and the level of compliance of radiation safety principles in equine veterinary clinics within Australia. Method: Surveys were sent to equine veterinary surgeons working in Australia. The survey was delivered both online and in hardcopy format; it comprised 49 questions, 15 of these directly related to radiation safety. The participants were asked about their current and previous use of radiation-producing equipment. Information regarding their level of knowledge and application of radiation safety principles and practice standards was collected and analysed. Results: The use of radiation-producing equipment was evident in 94% of responding clinics (a combination of X-ray, CT and/or Nuclear Medicine Cameras). Of those with radiation-producing equipment, 94% indicated that they hold a radiation licence, 78% had never completed a certified radiation safety course and 19% of participants did not use a personal radiation monitor. In 14% of cases, radiation safety manuals or protocols were not available within clinics. Conclusions: The study has shown that knowledge and application of guidelines as provided by the Code of Practice for Radiation Protection in Veterinary Medicine (2009) is poorly adhered to. The importance of compliance with regulatory requirements is pivotal in minimising occupational exposure to ionising radiation in veterinary medicine, thus there is a need for increased education and training in the area. - Highlights: • Application of the Code of Practice for Veterinary Medicine is poorly adhered to. • Majority of veterinary clinics had not completed certified radiation safety course. • One-fifth of participants did not use personal radiation monitoring. • Increased education and training in area of radiation safety and protection required to generate compliance in clinics

Topical issues in nuclear, radiation and radioactive waste safety. Contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-08-01

The IAEA International Conference on Topical Issues in Nuclear, Radiation and Radioactive Waste Safety was held in Vienna, Austria, 30 August - 4 September 1998 with the objective to foster the exchange of information on topical issues in nuclear, radiation and radioactive waste safety, with the aim of consolidating an international consensus on: the present status of these issues; priorities for future work; and needs for strengthening international co-operation, including recommendations for the IAEA`s future activities. The document includes 43 papers presented at the Conference dealing with the following topical issues: Safety Management; Backfitting, Upgrading and Modernization of NPPs; Regulatory Strategies; Occupational Radiation Protection: Trends and Developments; Situations of Chronic Exposure to Residual Radioactive Materials: Decommissioning and Rehabilitation and Reclamation of Land; Radiation Safety in the Far Future: The Issue of Long Term Waste Disposal. A separate abstract and indexing were provided for each paper. Refs, figs, tabs

Topical issues in nuclear, radiation and radioactive waste safety. Contributed papers

International Nuclear Information System (INIS)

1998-08-01

The IAEA International Conference on Topical Issues in Nuclear, Radiation and Radioactive Waste Safety was held in Vienna, Austria, 30 August - 4 September 1998 with the objective to foster the exchange of information on topical issues in nuclear, radiation and radioactive waste safety, with the aim of consolidating an international consensus on: the present status of these issues; priorities for future work; and needs for strengthening international co-operation, including recommendations for the IAEA's future activities. The document includes 43 papers presented at the Conference dealing with the following topical issues: Safety Management; Backfitting, Upgrading and Modernization of NPPs; Regulatory Strategies; Occupational Radiation Protection: Trends and Developments; Situations of Chronic Exposure to Residual Radioactive Materials: Decommissioning and Rehabilitation and Reclamation of Land; Radiation Safety in the Far Future: The Issue of Long Term Waste Disposal. A separate abstract and indexing were provided for each paper

Safety design criteria for the next generation Sodium-cooled fast reactors based on lessons learned from the Fukushima NPS accident

International Nuclear Information System (INIS)

Sakai, Takaaki

2012-01-01

In this presentation, architecture of the safety design criteria as requirements for SFR system and the activities on safety research works to establish safety evaluation methods for the next generation SFRs are summarized with the basis on lessons learned from the Fukushima NPS accident. Nuclear safety is a grovel issue which should be achieved by the international cooperation. In respect of the development for the next generation reactor, it is necessary to build the harmonized safety criteria and evaluation methods to establish the next level of safety

Radiation protection and safety in the Australian Defence Organisation (ADO)

International Nuclear Information System (INIS)

Jenks, G.J.; O'Donovan, E.J.B.

1995-01-01

Very few organisations have to address such a diverse and complex range of radiation safety matters as the Australian Defence Organisation. The Australian Defence Force and the Department of Defence (its military and civilian branches) have to comply with strict regulations in normal peace time activities. The Surgeon-General, to whom responsibility for policy in radiation protection and safety falls, has established a Defence Radiation Safety Committee, which in turn oversees four specialist subcommittees. Their tasks include recommending policy and doctrine in relation to radiation safety, overseeing the implementation of appropriate regulations, monitoring their compliance. generating the relevant documentation (particularly on procedures to be followed), developing and improving any necessary training courses, and providing sound technical advice whenever and to whomever required. The internal Defence regulations do not permit radiation doses to exceed those limits recommended by the Australian National Health and Medical Research Council and precautions are taken to ensure during normal peace time duties that these levels are not exceeded. At times of national emergency, the Surgeon-General provides guidance and advice to military commanders on the consequences of receiving dose levels that would not be permitted during normal peace time activities. The paper describes the methods adopted to implement such arrangements

NEW CRITERIA FOR ASSIGNING WASTE CONTAINING TECH-NOGENIC RADIONUCLIDES TO THE RADIOACTIVE WASTE

Directory of Open Access Journals (Sweden)

I. K. Romanovich

2010-01-01

Full Text Available The article contains detailed description of criteria for assigning of liquid and gaseous industrial waste containing technogenicradionuclides to the radioactive waste, presented in the new Basic Sanitary Rulesof Radiation Safety (OSPORB-99/2010. The analysisof shortcomings and discrepancies of the previously used in Russia system of criteria for assigning waste to the radioactive waste is given.

Regulatory Control of Radiation Sources. Safety Guide (Arabic Edition)

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide is intended to assist States in implementing the requirements established in Safety Standards Series No. GS-R-1, Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety, for a national regulatory infrastructure to regulate any practice involving radiation sources in medicine, industry, research, agriculture and education. The Safety Guide provides advice on the legislative basis for establishing regulatory bodies, including the effective independence of the regulatory body. It also provides guidance on implementing the functions and activities of regulatory bodies: the development of regulations and guides on radiation safety; implementation of a system for notification and authorization; carrying out regulatory inspections; taking necessary enforcement actions; and investigating accidents and circumstances potentially giving rise to accidents. The various aspects relating to the regulatory control of consumer products are explained, including justification, optimization of exposure, safety assessment and authorization. Guidance is also provided on the organization and staffing of regulatory bodies. Contents: 1. Introduction; 2. Legal framework for a regulatory infrastructure; 3. Principal functions and activities of the regulatory body; 4. Regulatory control of the supply of consumer products; 5. Functions of the regulatory body shared with other governmental agencies; 6. Organization and staffing of the regulatory body; 7. Documentation of the functions and activities of the regulatory body; 8. Support services; 9. Quality management for the regulatory system.

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

International Nuclear Information System (INIS)

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

2014-01-01

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

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

Science.gov (United States)

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.

Radiation safety training for industrial irradiators: What are we trying to accomplish?

International Nuclear Information System (INIS)

Smith, M.A.

1998-01-01

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 training to an audience of varied educational and technical background where little to no commercially available training material specific to this type of operation exists

Internet applications in radiation safety

International Nuclear Information System (INIS)

Hill, P.; Geisse, C.; Wuest, E.

1998-01-01

As a means of effective communication the Internet is presently becoming more and more important in German speaking countries, too. Its possibilities to exchange and to obtain information efficiently and rapidly are excellent. Internet and email access are available now in most institutions for professional use. Internet services of importance to radiation safety professionals are described. (orig.) [de

Nuclear safety and radiation protection report of the nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the Tricastin operational hot base facility (INB no. 157, Bollene, Vaucluse (FR)), a nuclear workshop for storage and maintenance and qualification operations on some EdF equipments. Then, the nuclear safety and radiation protection measures taken regarding the facility are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if some, are reported as well as the effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility is presented and sorted by type of waste, quantities and type of conditioning. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

Nuclear and radiation safety in Kazakhstan

International Nuclear Information System (INIS)

Kim, A.A.

2001-01-01

Major factors by which the radiation situation in Kazakhstan is formed are: enterprises of nuclear fuel cycle, including uranium mining and milling activity and geological exploration of uranium; nuclear power plant and research reactors; residues of atmospheric and underground nuclear explosions, which were conducted for military and peaceful purposes at different test sites; mining and milling of commercial minerals accompanied by radioactive substances; use of radioactive sources in industry, medicine, agriculture and scientific research. Since 1991, after getting sovereignty, creation was started of an own legislative basis of the country for the field of atomic energy use. It includes laws, regulations and standards for nuclear and radiation safety of nuclear installations, personnel, involved in the activity with using of atomic energy, population and environment. An applicable system of state regulation in this area (including a central regulatory body in the field of atomic energy use) and various ministries, agencies and committees, was created. As a result of these reforms, regulatory activities were improved in the country. This paper presents the current matters of nuclear and radiation safety in Kazakhstan and some difficulties which Kazakhstan encountered during the transition to an independent state. (author)

Operations report 1985 of the Department of Safety and Radiation Protection

International Nuclear Information System (INIS)

Hille, R.; Frenkler, K.L.

1986-04-01

Under the heading 'Licensing' the report deals with licensing procedures and the handling of nuclear-fuels and radioactive materials. Operational radiation protection is concerned with operational and personnel monitoring, mathematical methods and safety analyses. Environmental protection deals with emission control, immission monitoring and meteorological measurements, and safety technology with α/β-analysis, dosimetry, equipment servicing and mechanics, nuclear material safeguards. Other subdepartments take care of industrial safety, physical protection, emergency protection and training. Subjects dealt with, too, are dispersion pollutants in atmosphere and environment, further development of radiation protection methods, and the bibliography of radiation protection in KFA. (HK) [de

Criteria adopted by the Argentine Nuclear Regulatory Authority for assessing digital systems related to safety

International Nuclear Information System (INIS)

Terrado, Carlos A.; Chiossi, Carlos E.; Felizia, Eduardo R.; Roca, Jose L.; Sajaroff, Pedro M.

2004-01-01

Following the technological evolution in Instrumentation and Control (I and C) design, analog components are replaced by digital in almost every industry. Due to growing challenges of obsolescence and increasing maintenance costs, licensees of nuclear and radioactive installations are increasingly upgrading or replacing their existing I and C analog systems and components. In existing installations, this involves analog to digital replacements. In new installations design, the use of digital I and C systems is being considered from the very beginning, becoming a good alternative, even in safety applications. Up to now, in Argentina, there is no specific rules for safety-related digital systems, every safety system, analog or digital, must comply with the same generic regulations. The Nuclear Regulatory Authority is now developing criteria to assess digital systems related to safety in nuclear and radioactive installations. In this paper some of those criteria, based on local research and the recognized state of the art, are explained. From a regulatory point of view, the use of digital technology often raises new technical and licensing issues, particularly for safety-related applications. Examples include new failure modes, the potential for common-cause failure of redundant components, electromagnetic interference (EMI), software verification and validation, configuration management and a more exhaustive quality assurance system. The mentioned criteria comprehend the design, operation, maintenance and acquisition of digital systems and components important to safety. The main topics covered are: requirements specifications for digital systems, planning and documentation for digital system development, effectiveness of a digital system, commercial off the shelf (COTS) treatment and considerations involving tools for software development. (author)

Computer-based and web-based radiation safety training

Energy Technology Data Exchange (ETDEWEB)

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.

Legal and governmental infrastructure for nuclear, radiation, radioactive waste and transport safety. Safety requirements

International Nuclear Information System (INIS)

2000-01-01

This publication establishes requirements for legal and governmental responsibilities in respect of the safety of nuclear facilities, the safe use of sources of ionizing radiation, radiation protection, the safe management of radioactive waste and the safe transport of radioactive material. Thus, it covers development of the legal framework for establishing a regulatory body and other actions to achieve effective regulatory control of facilities and activities. Other responsibilities are also covered, such as those for developing the necessary support for safety, involvement in securing third party liability and emergency preparedness

Legal and governmental infrastructure for nuclear, radiation, radioactive waste and transport safety. Safety requirements

International Nuclear Information System (INIS)

2004-01-01

This publication establishes requirements for legal and governmental responsibilities in respect of the safety of nuclear facilities, the safe use of sources of ionizing radiation, radiation protection, the safe management of radioactive waste and the safe transport of radioactive material. Thus, it covers development of the legal framework for establishing a regulatory body and other actions to achieve effective regulatory control of facilities and activities. Other responsibilities are also covered, such as those for developing the necessary support for safety, involvement in securing third party liability and emergency preparedness

The decision making criteria on radiation protection of population in the cases of an accidental plutonium dispersion into environment

International Nuclear Information System (INIS)

Savkin, M.N.; Titov, A.V.

2000-01-01

Intervention criteria for radiation protection of general public in the case of accidental plutonium release have been elaborated on the basis of experimental radiobiological studies of affects of incorporated plutonium and of long duration medical observation for nuclear workers in Russia and the requirements of the national Radiation Safety Standards. Generic and operational levels for decision-making are given for early and late phases following the accident. Criteria for decision making are established in terms of upper and lower generic and operational levels (UL/LL). Criteria for urgent evacuation in the early stage directed on preventing of serious deterministic effects are defined as projected absorbed dose rate for lung 2x10 -2 Gy/day (UL) and 3x10 -3 Gy/day (LL). The UL corresponds to intake of 300 kBq of 239 Pu and mortal consequences during the first year after the accident as a result of acute interstitial pneumonite. The LL corresponds to intake of 40 kBq of 239 Pu and the threshold of serious radiological effects (disablement as a result of pneumosclerosis) and high level of stochastic effects - cancer of lung. Other basic countermeasures are intended on to be directed mitigation of long term radiological consequences. That is why criteria for them are defined in terms of protected equivalent dose for lungs or avertable effective dose. Criteria for sheltering and individual protection of respiratory tract correspond to committed equivalent dose due to intake during two days 200 mSv (UL) and 20 mSv (LL). Temporary relocation (1-2 years) is recommended if averted monthly effective dose is 30 mSv (UL) and 10 mSv (LL). Permanent relocation is justified if averted life-time effective dose is 1000 mSv (UL) and 200 mSv (LL). Operational levels in terms of density of soil contamination by plutonium are calculated for practical application of the dose criteria. (author)

Radiation Safety in Industrial Radiography. Specific Safety Guide (Spanish Edition); Seguridad radiologica en la radiografia industrial

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-12-15

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography.

Safety and Efficacy of Stereotactic Ablative Radiation Therapy for Renal Cell Carcinoma Extracranial Metastases

International Nuclear Information System (INIS)

Wang, Chiachien Jake; Christie, Alana; Lin, Mu-Han; Jung, Matthew; Weix, Derek; Huelsmann, Lorel; Kuhn, Kristin; Meyer, Jeffrey; Desai, Neil; Kim, D. W. Nathan; Pedrosa, Ivan; Margulis, Vitaly; Cadeddu, Jeffrey; Sagalowsky, Arthur; Gahan, Jeffrey; Laine, Aaron; Xie, Xian-Jin; Choy, Hak; Brugarolas, James; Timmerman, Robert

2017-01-01

Purpose: Renal cell carcinoma is refractory to conventional radiation therapy but responds to higher doses per fraction. However, the dosimetric data and clinical factors affecting local control (LC) are largely unknown. We aimed to evaluate the safety and efficacy of stereotactic ablative radiation therapy (SAbR) for extracranial renal cell carcinoma metastases. Methods and Materials: We reviewed 175 metastatic lesions from 84 patients treated with SAbR between 2005 and 2015. LC and toxicity after SAbR were assessed with Response Evaluation Criteria in Solid Tumors (RECIST) version 1.1 and Common Terminology Criteria for Adverse Events (CTCAE) version 4.0. Predictors of local failure were analyzed with χ 2 , Kaplan-Meier, and log-rank tests. Results: In most cases (74%), SAbR was delivered with total doses of 40 to 60 Gy, 30 to 54 Gy, and 20 to 40 Gy in 5 fractions, 3 fractions, and a single fraction, respectively. The median biologically effective dose (BED) using the universal survival model was 134.5 Gy. The 1-year LC rate after SAbR was 91.2% (95% confidence interval, 84.9%-95.0%; median follow-up, 16.7 months). Local failures were associated with prior radiation therapy (hazard ratio [HR], 10.49; P<.0001), palliative-intent radiation therapy (HR, 4.63; P=.0189), spinal location (HR, 5.36; P=.0041), previous systemic therapy status (0-1 vs >1; HR, 3.52; P=.0217), and BED <115 Gy (HR, 3.45; P=.0254). Dose received by 99% of the target volume was the strongest dosimetric predictor for LC. Upon multivariate analysis, dose received by 99% of the target volume greater than BED of 98.7 Gy and systemic therapy status remained significant (HR, 0.12 and 3.64, with P=.0014 and P=.0472, respectively). Acute and late grade 3 toxicities attributed to SAbR were observed in 3 patients (1.7%) and 5 patients (2.9%), respectively. Conclusions: SAbR demonstrated excellent LC of metastatic renal cell carcinoma with a favorable safety profile when an adequate dose and

Safety and Efficacy of Stereotactic Ablative Radiation Therapy for Renal Cell Carcinoma Extracranial Metastases

Energy Technology Data Exchange (ETDEWEB)

Wang, Chiachien Jake [Kidney Cancer Program, Simmons Comprehensive Cancer Center, University of Texas Southwestern Medical Center, Dallas, Texas (United States); Department of Radiation Oncology, University of Texas Southwestern Medical Center, Dallas, Texas (United States); Christie, Alana [Kidney Cancer Program, Simmons Comprehensive Cancer Center, University of Texas Southwestern Medical Center, Dallas, Texas (United States); Lin, Mu-Han; Jung, Matthew; Weix, Derek; Huelsmann, Lorel; Kuhn, Kristin; Meyer, Jeffrey; Desai, Neil; Kim, D. W. Nathan [Department of Radiation Oncology, University of Texas Southwestern Medical Center, Dallas, Texas (United States); Pedrosa, Ivan [Department of Radiology, Advanced Imaging Research Center, University of Texas Southwestern Medical Center, Dallas, Texas (United States); Margulis, Vitaly; Cadeddu, Jeffrey; Sagalowsky, Arthur; Gahan, Jeffrey [Department of Urology, University of Texas Southwestern Medical Center, Dallas, Texas (United States); Laine, Aaron [Department of Radiation Oncology, University of Texas Southwestern Medical Center, Dallas, Texas (United States); Xie, Xian-Jin [Kidney Cancer Program, Simmons Comprehensive Cancer Center, University of Texas Southwestern Medical Center, Dallas, Texas (United States); Choy, Hak [Department of Radiation Oncology, University of Texas Southwestern Medical Center, Dallas, Texas (United States); Brugarolas, James [Kidney Cancer Program, Simmons Comprehensive Cancer Center, University of Texas Southwestern Medical Center, Dallas, Texas (United States); Division of Hematology/Oncology, Department of Internal Medicine, University of Texas Southwestern Medical Center, Dallas, Texas (United States); Timmerman, Robert [Department of Radiation Oncology, University of Texas Southwestern Medical Center, Dallas, Texas (United States); and others

2017-05-01

Purpose: Renal cell carcinoma is refractory to conventional radiation therapy but responds to higher doses per fraction. However, the dosimetric data and clinical factors affecting local control (LC) are largely unknown. We aimed to evaluate the safety and efficacy of stereotactic ablative radiation therapy (SAbR) for extracranial renal cell carcinoma metastases. Methods and Materials: We reviewed 175 metastatic lesions from 84 patients treated with SAbR between 2005 and 2015. LC and toxicity after SAbR were assessed with Response Evaluation Criteria in Solid Tumors (RECIST) version 1.1 and Common Terminology Criteria for Adverse Events (CTCAE) version 4.0. Predictors of local failure were analyzed with χ{sup 2}, Kaplan-Meier, and log-rank tests. Results: In most cases (74%), SAbR was delivered with total doses of 40 to 60 Gy, 30 to 54 Gy, and 20 to 40 Gy in 5 fractions, 3 fractions, and a single fraction, respectively. The median biologically effective dose (BED) using the universal survival model was 134.5 Gy. The 1-year LC rate after SAbR was 91.2% (95% confidence interval, 84.9%-95.0%; median follow-up, 16.7 months). Local failures were associated with prior radiation therapy (hazard ratio [HR], 10.49; P<.0001), palliative-intent radiation therapy (HR, 4.63; P=.0189), spinal location (HR, 5.36; P=.0041), previous systemic therapy status (0-1 vs >1; HR, 3.52; P=.0217), and BED <115 Gy (HR, 3.45; P=.0254). Dose received by 99% of the target volume was the strongest dosimetric predictor for LC. Upon multivariate analysis, dose received by 99% of the target volume greater than BED of 98.7 Gy and systemic therapy status remained significant (HR, 0.12 and 3.64, with P=.0014 and P=.0472, respectively). Acute and late grade 3 toxicities attributed to SAbR were observed in 3 patients (1.7%) and 5 patients (2.9%), respectively. Conclusions: SAbR demonstrated excellent LC of metastatic renal cell carcinoma with a favorable safety profile when an adequate dose

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

Science.gov (United States)

2013-05-14

... provide as a service, scenario based physiology training, which includes hypobaric chamber training. BST may offer its scenario based physiology altitude training as a service to a prospective launch and...: Notification of criteria used to evaluate the Black Sky Training, Inc. (BST) safety approval application...

IAEA safety glossary. Terminology used in nuclear safety and radiation protection. 2007 ed

International Nuclear Information System (INIS)

2007-01-01

In developing and establishing standards of safety for protecting people and the environment from harmful effects of ionizing radiation and for the safety of facilities and activities that give rise to radiation risks, clear communication on scientific and technical concepts is essential. The principles, requirements and recommendations that are established and explained in the IAEA's safety standards and elaborated upon in other publications must be clearly expressed. To this end, this Safety Glossary defines and explains technical terms used in IAEA safety standards and other safety related publications, and provides information on their usage. The primary purpose of the Safety Glossary is to harmonize terminology and usage in the IAEA safety standards for protecting people and the environment from harmful effects of ionizing radiation, and in their application. Once definitions of terms have been established, they are, in general, intended to be observed in safety standards and other safety related publications and in the work of the IAEA Department of Nuclear Safety and Security generally. The achievement of consistently high quality in its publications contributes to the authority and credibility of the IAEA, and thus to its influence and effectiveness. High quality in publications and documents is achieved not only by review to ensure that the relevant requirements are met, but also by managing their preparation so as to achieve high quality in their drafting. The Safety Glossary provides guidance primarily for the drafters and reviewers of safety standards, including IAEA technical officers and consultants and bodies for the endorsement of safety standards. The Safety Glossary is also a source of information for users of IAEA safety standards and other safety and security related IAEA publications and for other IAEA staff - notably writers, editors, translators, revisers and interpreters. Users of the Safety Glossary, in particular drafters of national

IAEA safety glossary. Terminology used in nuclear safety and radiation protection. 2007 ed

International Nuclear Information System (INIS)

2007-06-01

In developing and establishing standards of safety for protecting people and the environment from harmful effects of ionizing radiation and for the safety of facilities and activities that give rise to radiation risks, clear communication on scientific and technical concepts is essential. The principles, requirements and recommendations that are established and explained in the IAEA's safety standards and elaborated upon in other publications must be clearly expressed. To this end, this Safety Glossary defines and explains technical terms used in IAEA safety standards and other safety related publications, and provides information on their usage. The primary purpose of the Safety Glossary is to harmonize terminology and usage in the IAEA safety standards for protecting people and the environment from harmful effects of ionizing radiation, and in their application. Once definitions of terms have been established, they are, in general, intended to be observed in safety standards and other safety related publications and in the work of the IAEA Department of Nuclear Safety and Security generally. The achievement of consistently high quality in its publications contributes to the authority and credibility of the IAEA, and thus to its influence and effectiveness. High quality in publications and documents is achieved not only by review to ensure that the relevant requirements are met, but also by managing their preparation so as to achieve high quality in their drafting. The Safety Glossary provides guidance primarily for the drafters and reviewers of safety standards, including IAEA technical officers and consultants and bodies for the endorsement of safety standards. The Safety Glossary is also a source of information for users of IAEA safety standards and other safety and security related IAEA publications and for other IAEA staff - notably writers, editors, translators, revisers and interpreters. Users of the Safety Glossary, in particular drafters of national