WorldWideScience

Sample records for applying radiation safety

  1. Applying radiation safety standards in radiotherapy

    International Nuclear Information System (INIS)

    The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS) cover the application of ionizing radiation for all practices and interventions and are, therefore, basic and general in nature. Users of radiation sources have to apply these basic requirements to their own particular practices. This requires a degree of 'interpretation' by the user, which can result in varying levels of regulatory compliance and inconsistencies between applications of the BSS to similar practices. In this context, the preamble of the BSS states that: The [regulatory body] may need to provide guidance on how certain regulatory requirements are to be fulfilled for various practices, for example in regulatory guideline documents. In order to guide the user to achieve a good standard of protection and to achieve a consistent national approach to licensing and inspection, some countries have developed practice specific regulatory guidance, while others have practice specific regulations. For obvious reasons, national regulatory guidance is tailored to a country's own legislation and regulations. This can lead to problems if the guidance is used in other States without appropriate modification to take local requirements into account. There would therefore appear to be scope for producing internationally harmonized guidance, while bearing in mind that the ultimate responsibility for the regulatory documents rests with the State. Some regions have taken the initiative of preparing guidance to facilitate the regional harmonization of regulatory control of certain common practices (e.g. radiotherapy). A number of draft regulatory guidance documents for the main practices involving the use of ionizing radiation have already been prepared. This initiative indicates that there is a global demand for such documents. In particular, it is felt that countries participating in the IAEA's technical cooperation model project on Upgrading

  2. Applying radiation safety standards in diagnostic radiology and interventional procedures using x rays

    International Nuclear Information System (INIS)

    The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS) cover the application of ionizing radiation for all practices and interventions and are, therefore, basic and general in nature. Users of radiation sources have to apply those basic requirements to their own particular practices. That requires a degree of 'interpretation' by the user, which can result in varying levels of regulatory compliance and inconsistencies between applications of the BSS to similar practices. In this context, the Preamble of the BSS states that: 'The [regulatory body] may need to provide guidance on how certain regulatory requirements are to be fulfilled for various practices, for example in regulatory guideline documents.' In order to guide the user to achieve a good standard of protection and to achieve a consistent national approach to licensing and inspection, some countries have developed practice specific regulatory guidance, while others have practice specific regulations. National regulatory guidance is tailored to a country's own legislation and regulations for obvious reasons. This can lead to problems if the guidance is used in other States without appropriate modification to take local requirements into account. There would appear, therefore, to be scope for producing internationally harmonized guidance, while bearing in mind that the ultimate responsibility for the regulatory documents rests with the State. Some regions have taken the initiative of preparing guidance to facilitate the regional harmonization of regulatory control of certain common practices (e.g. radiology). In particular, it is felt that States participating in the IAEA's technical cooperation Model Project on Upgrading Radiation and Waste Safety Infrastructure would benefit significantly from the availability of practice specific guidance. Member States could then more readily develop their own guidance tailored to their own

  3. Radiation and waste safety

    International Nuclear Information System (INIS)

    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)

  4. Radiation Safety Compliance.

    Science.gov (United States)

    Koth, Jana; Smith, Marcia Hess

    2016-05-01

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

  5. Occupational radiation protection. Safety guide

    International Nuclear Information System (INIS)

    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

  6. Radiation safety audit

    International Nuclear Information System (INIS)

    Audit has been seen as one of the effective methods to ensure harmonization in radiation protection. A radiation safety audit is a formal safety performance examination of existing or future work activities by an independent team. Regular audit will assist the management in its mission to maintain the facilities environment that is inherently safe for its employees. The audits review the adequacy of facilities for the type of use, training, and competency of workers, supervision by authorized users, availability of survey instruments, security of radioactive materials, minimization of personnel exposure to radiation, safety equipment, and the required record keeping. All approved areas of use are included in these periodic audits. Any deficiency found in the audit shall be corrected as soon as possible after they are reported. Radiation safety audit is a proactive approach to improve radiation safety practices and identify and prevent any potential radiation accident. It is an excellent tool to identify potential problem to radiation users and to assure that safety measures to eliminate or reduce the problems are fully considered. Radiation safety audit will help to develop safety culture of the facility. It is intended to be the cornerstone of a safety program designed to aid the facility, staff and management in maintaining a safe environment in which activities are carried out. The initiative of this work is to evaluate the need of having a proper audit as one of the mechanism to manage the safety using ionizing radiation. This study is focused on the need of having a proper radiation safety audit to identify deviations and deficiencies of radiation protection programmes. It will be based on studies conducted on several institutes/radiation facilities in Malaysia in 2006. Steps will then be formulated towards strengthening radiation safety through proper audit. This will result in a better working situation and confidence in the radiation protection community

  7. RF radiation safety handbook

    International Nuclear Information System (INIS)

    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)

  8. Radiation protection and the safety of radiation sources

    International Nuclear Information System (INIS)

    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

  9. Recent trends in particle accelerator radiation safety

    International Nuclear Information System (INIS)

    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

  10. Radiation safety audit system - safety perspectives

    International Nuclear Information System (INIS)

    In 2005 Safety and Health at the University of Western Australia (UWA) implemented a system of Radiation Safety Audits. The system was implemented to ensure complete audits were carried out annually for each section of the University with radiation safety issues. The audits cover those aspects of radiation safety regulated in the Radiation Safety Act of Western Australia and include high powered lasers, UV emitting devices, radioactive materials, x-ray machines. In relation to these there are regulated considerations for equipment registration, location of use and storage registration, licensing of individual to use radiation, training, documentation, working rules, personal monitoring, calibrations and supervision. Within the University there are University systems to control materials and equipment coming onto campus, risk assessment protocols required for each new project or type of work, local permits and waste disposal. UWA Safety and Health have an active role in delivering control of radiation safety and ensuring that safety systems are appropriate relevant and used in an immediate and useful manner. Safety and Health has importantly built a network of key people on campus, made sure they are assisted, valued and that the systems are seen as a way to improve efficiency in delivering real, relevant and useful radiation safety outcomes. The systems include uniform documentation across campus, clear expectations and an ongoing interest from Safety and Health to ensure the systems remain alive. This has allowed the audits to become efficient and effective both for the sections involved but also for Safety and health in its recording systems and improvement follow up process.

  11. Radiation Safety for Sustainable Development

    International Nuclear Information System (INIS)

    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

  12. Occupational radiation safety in mining

    International Nuclear Information System (INIS)

    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

  13. Industrial irradiator radiation safety program assessments

    Science.gov (United States)

    Smith, Mark A.

    2000-03-01

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

  14. Radiation safety under extreme conditions

    International Nuclear Information System (INIS)

    A description is given of the main radiation safety provisions implemented during the erection of the encapsulation of Unit 4 of the Chernobyl nuclear power plant after the accident on 26 April 1986. The radiation situation at the site during the work was characterized by high radiation levels and radioactive contamination of the area and the buildings. The situation was highly complex and developments were difficult to forecast. In view of the extremely dangerous radiation conditions, the large volume of construction and assembly work had to be carried out within a very limited period of time. Work in the vicinity of the destroyed unit was carried out only after radiation reconnaissance had been performed, the main radiation sources determined, and safe working regulations formulated. Both traditional and specially developed methods were used to monitor the radiation situation. On the basis of radiation reconnaissance and radiation situation monitoring results, organizational and technical measures were developed and implemented to ensure the radiation safety of personnel. During the construction work, extensive use was made of remote controlled machinery and technology and various types of radiation protection cabins and screens were employed. Great emphasis was placed on the implementation of technical health precautions. A health checkpoint regime was instituted in the exclusion zone around the plant with changing areas, radiation monitoring areas, and shower rooms. Staff were equipped with special clothing, special footwear, and apparatus to protect the respiratory organs. By November 1986 the destroyed unit had been rendered safe and conditions restored for continued operation of the three remaining units. Radiation safety requirements were complied with during the work. (author). 6 refs, 5 figs, 1 tab

  15. Applying radiation health effects data to radiation protection policies

    International Nuclear Information System (INIS)

    Data from the peer-reviewed scientific literature establish a sound basis to define a low-dose, low-dose-rate, dose-response. These data include human health dose-response studies; immunologically 'whole' animal studies; and cellular and molecular biological studies of complete biological systems for the relevant immunological and physiological responses. Initiatives are required to constructively apply these data to both radiation research and radiation protection policies. First, current low level radiation health effects research must apply existing data to define research projects to integrate and confirm existing dose-response data, with specific emphasis on the biological bases that exist in definitive and reproducible cellular and biological dose-response. Second, dose-response assessment must identify and incorporate all existing substantial and confirmed data, including natural radiation sources, to establish the bases for radiation protection policy for interventions to protect public health and safety. A preliminary assessment of these data is applied to: 1) Specify research that can be constructively applied to describe radiation health effects dose-response. 2) Apply health effects dose-response to radiation and radioactivity applications policies to maximize radiation health effects interventions for occupational applications, medical applications, and other radiation and radioactive materials applications controls to cost-effectively assure public health and safety. An assessment of the proposed revisions to ICRP radiation protection policies is provided that associates the basis for administrative limits with the previous proposal of the US NRC for a 'Below Regulatory Concern' (BRC) policy. This proposal ignores the context of the fact that very low levels of radiation exposure are far within the variations of natural radiation exposures, and therefore can have no gross net consequences. The equivalent failure of the BRC proposal resulted in quick

  16. Radiation safety and protection

    Energy Technology Data Exchange (ETDEWEB)

    Grzywacz, R.B.

    1988-10-01

    Often overlooked are the consequences of low-level radiation. This article increases awareness of the short- and long-term effects of x-rays on the podiatrist, his staff and patients. Protection can be achieved for all concerned by using the radiographic techniques, low-cost ways for dosage reduction, and monitoring devices discussed. A good x-ray examination should always provide the best diagnostic information while minimizing risk.7 references.

  17. Radiation Safety Considerations for LHD Experiments

    Science.gov (United States)

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

    1997-06-01

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

  18. Safety Culture on radiation protection

    International Nuclear Information System (INIS)

    It can be defined radiation protection culture as the set of technical and social standards applied to the management of the operation of a nuclear facility concerning the reduction of the exposure to radiation of workers and members of the public, together with the behaviour and attitudes of the individuals from the organization towards that objective. Because the basic principles of radiation protection are self-evident and are totally justified, and the thesis drawn from the article is that no effective radiation protection culture yet exists within the organization, it must be concluded that what is wrong from the system are the attitudes and behavior of the individuals. In this article some factors and elements needed to motivate all persons within the organization towards the creation of a radiation protection culture are delineated and presented. (Author)

  19. Requirements of radiation protection and safety for nuclear medicine services

    International Nuclear Information System (INIS)

    The requirements of radiation protection and safety for nuclear medicine services are established. The norms is applied to activities related to the radiopharmaceuticals for therapeutics and 'in vivo' diagnostics purposes. (M.C.K.)

  20. Basic Safety Standards for Radiation Protection

    International Nuclear Information System (INIS)

    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.

  1. Industrial safety and applied health physics. Annual report for 1977

    International Nuclear Information System (INIS)

    Progress is reported on the following: radiation monitoring with regard to personnel monitoring and health physics instrumentation; environs surveillance with regard to atmospheric monitoring, water monitoring, radiation background measurements, and soil and grass samples; radiation and safety surveys with regard to laboratory operations monitoring, radiation incidents, and laundry monitoring; industrial safety and special projects with regard to accident analysis, disabling injuries, and safety awards

  2. Proceeding of Radiation Safety and Environment

    International Nuclear Information System (INIS)

    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

  3. Promoting safety culture in radiation industry through radiation audit

    International Nuclear Information System (INIS)

    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)

  4. NTS Offsite Radiation Safety Program

    International Nuclear Information System (INIS)

    The United States began conducting nuclear tests at what was then called the Nevade Proving Grounds on January 27, 1951. In those days of the cold war, the testing of nuclear weapons was done in the atmosphere, where the explosive devices were located on the surface, set at the top of towers, suspended from balloons, dropped from aircraft, or even fired from a cannon. Some were placed in tunnels or in uncased and unstemmed holes. Altogether, between 1951 and 1958, when the President declared a moratorium on nuclear testing, the Atomic Energy Commission conducted 119 tests on the Nevada Test Site. The Site was operated for this purpose a few months during each year except for 1954 and 1956, when all U.S. nuclear tests were conducted in the Pacific Islands. In 1954, the Atomic Energy Commission and the U.S. Public Health Service signed an agreement making the Public Health Service (PHS) responsible for carrying out a continuing program of offsite radiological safety for U.S. nuclear weapons testing. In 1955, the PHS began to conduct the Offsite Radiation Safety Program with the test series called Operation Teapot. When the U.S. Environmental Protection Agency (EPA) was established in 1970, the PHS Laboratory in Las Vegas responsible for the offsite Program became a part of the new Agency, and EPA has continued the Program since that time

  5. Safety of radiation sources in Slovenia

    International Nuclear Information System (INIS)

    The Republic of Slovenia, a central European country which has been independent since 1991, has about 2 million inhabitants and an area of 20,256 km2 . The Constitutional Law on Enforcement of the Basic Constitutional Charter on the Autonomy and Independence of the Republic of Slovenia, adopted on 23 June 1991 (Off. Gaz. of the R of Slovenia No. 1/91), provided that all the laws adopted by the Socialist Federal Republic (SFR) of Yugoslavia should remain in force in the Republic of Slovenia pending the adoption of appropriate legislation by the Slovene Parliament. Under the Slovene Constitution, all international treaties ratified by Slovenia constitute an integral part of Slovenia's legislation and can be applied directly. In Slovenia, all regular types of ionizing radiation source are being used for peaceful purposes and are covered by a system for their safe use and control. All radiation sources and radioactive materials are registered and under regulatory control. Inspections are carried out periodically by the Health Inspectorate of the Republic of Slovenia (HIRS) and, in the case of nuclear installations, the Slovene Nuclear Safety Administration (SNSA). Technical checks on radiation sources are carried out periodically by technical support organizations: the Jozef Stefan Institute and the Institute for Occupational Safety (IOS). (author)

  6. Assessment of radiation safety in well logging

    International Nuclear Information System (INIS)

    Radiation safety assessments required by current regulations are a means to verify compliance with the requirements. Different methods have been used for this purpose. In the paper the results of applying the method of risk matrices, applied for the first time in the practice of well logging are exposed. For each initiating event frequency of occurrence, the severity of its consequences and the probability of failure of the barriers identified were evaluated. Starting from these assumptions, the risk associated is determined for each of the identified accident sequences, using for this the SEVRRA code 'Risk Assessment System', originally designed for use in radiotherapy. As an result sequences increased risk associated with the practice of well logging were identified, which is the starting point for the further implementation of a coherent program of dose optimization in practice.

  7. Effective education in radiation safety for nurses

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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

  9. Applied health physics and safety annual report for 1976

    Energy Technology Data Exchange (ETDEWEB)

    Auxier, J.A.; Davis, D.M.

    1977-08-01

    Progress is reported in the following areas of research: personnel monitoring; health physics instrumentation; atmospheric monitoring; water monitoring; radiation background measurements; soil samples; laboratory operations monitoring; radiation incidents; laundry monitoring; accident analysis; and industrial safety. (HLW)

  10. Radiation Safety (General) Regulations 1983 (Western Australia)

    International Nuclear Information System (INIS)

    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)

  11. Radiation protection and safety in industrial radiography

    International Nuclear Information System (INIS)

    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

  12. Radiation imaging for basic and applied research

    International Nuclear Information System (INIS)

    To peer into the interiors of a microscopic and macroscopic objects has been the dream of scientist and engineers for centuries. New frontiers in research and development in many branches of science and engineering such as biology, chemistry, engineering, geology, medical or physics have evolved around visual representation of the measurable property of an object, or phenomenon. Visualization using optical radiations provide limited information and often to look into the interiors of microscopic and macroscopic objects, probing with radiations such as x-ray or neutron is required. Such radiations are not directly visible and in order to unravel the data and images unfolded by such radiations, use of luminescent materials which convert these radiations into visible spectrum is required. Radiation imaging techniques have evolved in last few years and with this, new applications in the field of basic and applied sciences have developed. This has put greater demand on the development of new phosphors and scintillators suited for specific applications. This paper reviews new developments in radiation imaging techniques and applications and highlight the use of various phosphors and scintillators for such applications. As the subject is vast, only a few selected topics will be discussed on which work is being carried out at BARC. (author)

  13. Optical fiber-applied radiation detection system

    International Nuclear Information System (INIS)

    A technique to measure radiation by using plastic scintillation fibers doped radiation fluorescent (scintillator) to plastic optical fiber for a radiation sensor, was developed. The technique contains some superiority such as high flexibility due to using fibers, relatively easy large area due to detecting portion of whole of fibers, and no electromagnetic noise effect due to optical radiation detection and signal transmission. Measurable to wide range of and continuous radiation distribution along optical fiber cable at a testing portion using scintillation fiber and flight time method, the optical fiber-applied radiation sensing system can effectively monitor space radiation dose or apparatus operation condition monitoring. And, a portable type scintillation optical fiber body surface pollution monitor can measure pollution concentration of radioactive materials attached onto body surface by arranging scintillation fiber processed to a plate with small size and flexibility around a man to be tested. Here were described on outline and fundamental properties of various application products using these plastic scintillation fiber. (G.K.)

  14. Radiation safety aspects at Indus accelerator complex

    International Nuclear Information System (INIS)

    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

  15. Moon manned missions radiation safety analysis

    Science.gov (United States)

    Tripathi, R. K.; Wilson, J. W.; de Anlelis, G.; Badavi, F. F.

    An analysis is performed on the radiation environment found on the surface of the Moon, and applied to different possible lunar base mission scenarios. An optimization technique has been used to obtain mission scenarios minimizing the astronaut radiation exposure and at the same time controlling the effect of shielding, in terms of mass addition and material choice, as a mission cost driver. The optimization process has been realized through minimization of mass along all phases of a mission scenario, in terms of time frame (dates, transfer time length and trajectory, radiation environment), equipment (vehicles, in terms of shape, volume, onboard material choice, size and structure), location (if in space, on the surface, inside or outside a certain habitats), crew characteristics (number, gender, age, tasks) and performance required (spacecraft and habitat volumes), radiation exposure annual and career limit constraint (from NCRP 132), and implementation of the ALARA principle (shelter from the occurrence of Solar Particle Events). On the lunar surface the most important contribution to radiation exposure is given by background Galactic Cosmic Rays (GCR) particles, mostly protons, alpha particles, and some heavy ions, and by locally induced particles, mostly neutrons, created by the interaction between GCR and surface material and emerging from below the surface due to backscattering processes. In this environment manned habitats are to host future crews involved in the construction and/or in the utilization of moon based infrastructure. Three different kinds of lunar missions are considered in the analysis, Moon Base Construction Phase, during which astronauts are on the surface just to build an outpost for future resident crews, Moon Base Outpost Phase, during which astronaut crews are resident but continuing exploration and installation activities, and Moon Base Routine Phase, with long-term shifting resident crews. In each scenario various kinds of habitats

  16. Management information system applied to radiation protection services

    Energy Technology Data Exchange (ETDEWEB)

    Grossi, Pablo Andrade; Souza, Leonardo Soares de; Figueiredo, Geraldo Magela; Figueiredo, Arthur, E-mail: pabloag@cdtn.br, E-mail: lss@cdtn.br, E-mail: gmf@cdtn.br, E-mail: arthurqof@gmail.com [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2013-07-01

    An effective management information system based on technology, information and people is necessary to improve the safety on all processes and operations subjected to radiation risks. The complex and multisource information flux from all radiation protection activities on nuclear organizations requires a robust tool/system to highlight the strengths and weaknesses and identify behaviors and trends on the activities requiring radiation protection programs. Those organized and processed data are useful to reach a successful management and to support the human decision-making on nuclear organization. This paper presents recent improvements on a management information system based on the radiation protection directives and regulations from Brazilian regulatory body. This radiation protection control system is applied to any radiation protection services and research institutes subjected to Brazilian nuclear regulation and is a powerful tool for continuous management, not only indicating how the health and safety activities are going, but why they are not going as well as planned showing up the critical points. (author)

  17. New adventures in biomedical engineering: Radiation safety program management

    Energy Technology Data Exchange (ETDEWEB)

    Dickey, D.M. (Washington Hospital Center, DC (United States))

    1991-09-01

    As biomedical/clinical engineers expand their managerial expertise into nontraditional areas, it makes sense that they pursue areas where their formal training in physics and mathematics can be applied. Radiation safety requires having the educational background to understand atomic structure, the nature of radioactivity, mathematics, biology, chemistry, and instrumentation. Program management requires having the administrative experience to manage people, data, files, documentation, and budgets. Radiation safety program management also requires an understanding of how best to prepare for a surprise inspection, similar to but technically more specific than other inspections and surveys previously experienced by the BME/CE professional.

  18. The IAEA safety standards for radiation, waste and nuclear safety

    International Nuclear Information System (INIS)

    This paper presents a brief description of the standards for radiation, waste and nuclear safety established by the International Atomic Energy Agency (IAEA). It provides a historical overview of their development and also summarizes the standards' current preparation and review process. The final paragraphs offer an outlook on future developments. (author)

  19. Radiation safety for site radiography

    International Nuclear Information System (INIS)

    This guidance is an update of the 1975 Code of Practice for Site Radiography and is for the use of employers and their radiographers who carry out site work. The subject is discussed under the following headings: Administrative organization, Personnel requirements, Equipment (x-ray and gamma-ray equipment, security, pipeline crawler equipment and safety equipment) Work methods and monitoring, Carriage of sources, Contingency plans, Legal considerations. (U.K.)

  20. OBTAINING FOOD SAFETY BY APPLYING HACCP SYSTEM

    Directory of Open Access Journals (Sweden)

    ION CRIVEANU

    2012-01-01

    Full Text Available In order to increase the confidence of the trading partners and consumers in the products which are sold on the market, enterprises producing food are required to implement the food safety system HACCP,a particularly useful system because the manufacturer is not able to fully control finished products . SR EN ISO 22000:2005 establishes requirements for a food safety management system where an organization in the food chain needs to proove its ability to control food safety hazards in order to ensure that food is safe at the time of human consumption. This paper presents the main steps which ensure food safety using the HACCP system, and SR EN ISO 20000:2005 requirements for food safety.

  1. Establishment of radiation protection and safety programme in Nuclear Medicine

    International Nuclear Information System (INIS)

    Radiation is useful because of its ability to penetrate tissue, allowing imaging of internal structures. However radiation may produce harmful biological effects. Observations of exposed human populations and animal experimentation indicate that exposure to low levels of radiation over a period of time may lead to stochastic radiation effects. Exposures to high levels of radiation above threshold also leads to deterministic effects. Establishment of radiation protection and safety programme and implement it without fail may help prevent deterministic effect and limit chances of stochastic effects. This is achieved by assigning responsibilities to the proposed organizational structure, management commitment to safety culture by providing continuous education and training to employees, regular reviewing and auditing of radiation safety policies. Occupational, public and environmental radiation exposure is further achieved by implementation of set local rules and operational procedures, proper management of radioactive waste and safe transport of radioactive material. Medical radiation exposure is achieved by justified procedures, optimization of doses, guidance levels, quality assurance and quality control programme through image quality, radiopharmaceutical quality and records keeping of radiation doses, calibration certificates of equipment used, equipment service and test certificates. Diagnostic radiopharmaceuticals must deliver the minimum possible radiation dose to the patient while therapeutic radiopharmaceuticals must deliver the maximum dose to the target organ or tissue, while minimizing the dose to non-target tissues such as the bone marrow. Special considerations shall be given to pregnant and breast-feeding patients. The proper facility design and shielding of a nuclear medicine facility shall further provide for the radiation protection to the worker, the patient, public and the environment. Precautions should be given to radioactive patients as there

  2. B190 computer controlled radiation monitoring and safety interlock system

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa, D L; Fields, W F; Gittins, D E; Roberts, M L

    1998-08-01

    The Center for Accelerator Mass Spectrometry (CAMS) in the Earth and Environmental Sciences Directorate at Lawrence Livermore National Laboratory (LLNL) operates two accelerators and is in the process of installing two new additional accelerators in support of a variety of basic and applied measurement programs. To monitor the radiation environment in the facility in which these accelerators are located and to terminate accelerator operations if predetermined radiation levels are exceeded, an updated computer controlled radiation monitoring system has been installed. This new system also monitors various machine safety interlocks and again terminates accelerator operations if machine interlocks are broken. This new system replaces an older system that was originally installed in 1988. This paper describes the updated B190 computer controlled radiation monitoring and safety interlock system.

  3. Safety requirements applied to research reactors in France

    International Nuclear Information System (INIS)

    Full text: In France, there are currently some twenty research reactors in operation with a thermal powers up to a hundred megawatts. General safety requirements such as the redundancy and separation of protection system channels, continuous monitoring of confinement barriers and containment building leak tightness with respect to underlying soils and the underground water have been gradually established and applied. Regarding the seismic risk and those risks relating to the industrial environment and transportation of hazardous materials, the rules applying to research reactor design are the same as those applying to power reactors, albeit with some adaptations due to the specific features of certain reactors (short operating time or low radioactive product inventory). The following safety requirements applying specifically to the confinement barriers of pool-type research reactors should be noted: there must be no fuel cladding dryout under the various operating conditions; in the case of plate type fuels, this requirement implies checking the absence of flow redistribution in the hottest cooling channel; reactors must not be operated with a fuel element affected by clad failure; in such situations, the reactor must be automatically shut down and the fuel element in question removed and stored in a leaktight container; the core must not be uncovered in the event of a pipe break in the reactor coolant system or a window failure in neutron beam channels; this requirement is met through the integrated design of the reactor primary coolant system, which is installed in a 'water block', and through the implementation of automatic isolation valves on the neutron beam channels. The most significant specific approach adopted in France for the design of pool-type reactors using uranium and aluminum metal fuels is to take into account a BORAX-type explosive reactivity accident. For this type of accident, which is supposed to lead to total meltdown of the core under water

  4. Deriving and applying generally applicable safety principles

    Energy Technology Data Exchange (ETDEWEB)

    Spray, S.D.

    1998-08-01

    The nuclear detonation safety of modern nuclear weapons depends on a coordinated safety theme incorporating three general safety principles: isolation, inoperability, and incompatibility. The success of this approach has encouraged them to study whether these and/or other principles might be useful in other applications. Not surprisingly, no additional first-principles (based on physical laws) have been identified. However, a more widely applicable definition and application of the principle-based approach has been developed, resulting in a selection of strategies that are basically subsets and varied combinations of the more general principles above. However, identification of principles to be relied on is only one step in providing a safe design. As one other important example, coordinating overall architecture and strategy is essential: the authors term this a safety theme.

  5. Radiation safety and inventory of sealed radiation sources in Pakistan

    International Nuclear Information System (INIS)

    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)

  6. 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...

  7. Radiation safety research at Indus accelerator complex

    International Nuclear Information System (INIS)

    A brief description of the radiation safety research being carried out at the electron synchrotron radiation sources, Indus-1 (450 MeV) and Indus-2 (2.5 GeV) is presented. As these sources being operated at high energy, the radiation environment is primarily due to the interaction of these electrons with accelerating structure, when beam loss takes place, and subsequent development of electromagnetic cascade. Radiation in the cascade mainly consists of the Bremsstrahlung component which initiates photo-neutron production. Characteristics of these radiations are that the energy can be as high up to the energy of the accelerated electron. This gives rise to problems in detection and personnel dosimetry due to dose buildup effects. The angular dependency and pulsed nature of these radiations complicate the issue of detection. Besides, accidental loss of beam in the vacuum envelope of the accelerator, in addition to normal loss calls for appropriate evaluation of these contributions for personnel radiation safety. Attempts made to understand these problems and the research and development work carried out at Indus Accelerator Complex in order to address them will be discussed. (author)

  8. Radiation safety in veterinary practice

    International Nuclear Information System (INIS)

    It is stated that the Code is based on the recommendations of the International Commission on Radiological Protection and is in harmony with related national codes and legislation. The Code is in chapters, entitled: need for the Code; scope of the Code (establishments, persons, hazards); administrative measures for radiological protection; medical measures for radiological protection; operational measures for radiological protection; premises and equipment for radiography; procedures for radiography (general, large animal radiography, radiography undertaken outside the Designated Area); fluoroscopy; other uses of ionizing radiations (therapeutic use of x-rays, use of sealed radioactive sources, use of unsealed radioactive substances). Appendices include the following topics: maximum permissible doses and dose limits; advisory services; definitions, records, symbols and specimen local rules. (U.K.)

  9. 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 ...

  10. 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.

  11. Applying the behaviour grid for improving safety in industrial environments

    NARCIS (Netherlands)

    Boer, de J. (Johannes); Heylen, D. (Dirk); Teeuw, W.B. (Wouter)

    2013-01-01

    The Saxion University of Applied Sciences recently started its “Safety at Work” project. Its objective is to increase safety in the workplace by combining and applying state-of-the-art factors from Ambient Intelligence, Industrial & Product Design and Smart Materials [1].The human fa

  12. Progress report: 1996 Radiation Safety Systems Division

    International Nuclear Information System (INIS)

    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)

  13. Application of radiation safety principles and criteria in safety reassessment of radioactive waste disposed in near-surface facilities of the radon state corporation

    International Nuclear Information System (INIS)

    The paper analyses regulatory requirements applied in the design and construction of radioactive waste disposal facilities at sites of the Radon State Corporation and considers approaches on use of radiation safety principles and criteria in their safety reassessment

  14. Applying a realistic evaluation model to occupational safety interventions

    DEFF Research Database (Denmark)

    Pedersen, Louise Møller

    2016-01-01

    Background: Recent literature characterizes occupational safety interventions as complex social activities, applied in complex and dynamic social systems. Hence, the actual outcomes of an intervention will vary, depending on the intervention, the implementation process, context, personal...... and qualitative methods. This revised model has, however, not been applied in a real life context. Method: The model is applied in a controlled, four-component, integrated behaviour-based and safety culture-based safety intervention study (2008-2010) in a medium-sized wood manufacturing company. The interventions...... involve the company’s safety committee, safety manager, safety groups and 130 workers. Results: The model provides a framework for more valid evidence of what works within injury prevention. Affective commitment and role behaviour among key actors are identified as crucial for the implementation...

  15. Radiation Safety Awareness Among Medical Staff

    International Nuclear Information System (INIS)

    The common access to imaging methods based on ionizing radiation requires also radiation protection. The knowledge of ionizing radiation exposure risks among the medical staff is essential for planning diagnostic procedures and therapy. Evaluation of the knowledge of radiation safety during diagnostic procedures among the medical staff. The study consisted of a questionnaire survey. The questionnaire consisted of seven closed-ended questions concerning the knowledge of the effects of exposure to ionizing radiation as well as questions related to responder’s profession and work experience. The study group included a total of 150 individuals from four professional groups: nurses, doctors, medical technicians, support staff. The study was carried out in the three largest hospitals in Gdańsk between July and October 2013. The highest rates of correct answers to questions related to the issue of radiation protection were provided by the staff of radiology facilities and emergency departments with 1–5 years of professional experience. The most vulnerable group in terms of the knowledge of these issues consisted of individuals working at surgical wards with 11–15 years of professional experience. Education in the field of radiological protection should be a subject of periodic training of medical personnel regardless of position and length of service

  16. Nuclear and radiation safety in Kazakhstan

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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

  18. Radiation safety shield for a syringe

    International Nuclear Information System (INIS)

    Safety apparatus for use in administering radioactive serums by a syringe, without endangering the health and safety of the medical operators is described. The apparatus consists of a sheath and a shield which can be retracted into the sheath to assay the radioactive serum in an assay well. The shield can be moved from the retracted position into an extended position when the serum is to be injected into the patient. To protect the operator, the shield can be constructed of tantalum or any like high density substance to attenuate the radiation, emanating from the radioactive serums contained in the syringe, from passing to the atmosphere. A lead glass window is provided so that the operator can determine the exact quantity of the radioactive serum which is contained in the syringe

  19. Communication on radiation safety: ability and sensibility

    International Nuclear Information System (INIS)

    Nuclear Communication Issues today, combine aspects of nuclear science, public approach and psychological subjects. The principal objectives are to systematize nuclear public information and to prepare researchers or communicators in a position to comment on the nuclear issues of our stage. The programme should focused on progress of nuclear energy, public perception of risk, conflicts among scientists, as the radiation effect at low doses, and how nuclear industry and scientists may better communicate information concerning the potential for hazard to property, health and the environment. There will be occasions where the competent authority should have formal link with other organizations, as in case of abnormal situation or emergency. Particular attention should be paid to the exchange of distinct parts in order to avoid misinterpretation or mistakes when divulging information to the public.Communication is emphasized in the IAEA Basic Safety Standards, [1] as well as, the current approach created to enlarge the relationship between man, practices and protection by the encouragement of a better understanding and implementation of the Safety Culture concept. The application of this concept involves better protection on Radiation Safety to workers, public and environment not only reducing accidents, but also avoiding unnecessary stresses and strains due to intensified operations. This means an advance towards the humanization of practices, equally observed by industrialized and developing countries. Finally, this paper also comment about two very important lessons that there were not yet learned as in reality necessary, considering the goals for a competent Nuclear Communication: the psychological effects of Chernobyl accident in April 1986 resulted from the lack of public information; the psychological effects of the Radiological Accident in Goiania resulted from the misunderstanding of the basic concept of ionizing radiation, which was translated into fear and

  20. Basic safety standards for radiation protection. 1982 ed

    International Nuclear Information System (INIS)

    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.

  1. Maintenance of radiation safety information system

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Ho Sun [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Park, Moon Il; Chung, Chong Kyu; Lim, Bock Soo; Kim, Hyung Uk; Chang, Kwang Il; Nam, Kwan Hyun; Cho, Hye Ryan [AD center incubation LAB, Taejon (Korea, Republic of)

    2001-12-15

    The objectives of radiation safety information system maintenance are to maintain the requirement of users, change of job process and upgrade of the system performance stably and effectively while system maintenance. We conduct the code of conduct recommended by IAEA, management of radioisotope inventory database systematically using analysis for the state of inventory database integrated in this system. This system and database will be support the regulatory guidance, rule making and information to the MOST, KINS, other regulatory related organization and general public optimizationally.

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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

  4. Education and Training in Radiation, Transport and Waste Safety Newsletter, No. 2b, May 2013

    International Nuclear Information System (INIS)

    The IAEA Strategic Approach to Education and Training in Radiation, Transport and Waste Safety (2011-2020) provides a framework for establishing a sustainable education and training infrastructure in Member States that addresses national needs for building and maintaining competence in radiation, transport and waste safety that is consistent with IAEA Safety Standards. For this purpose, IAEA's General Conference has encouraged Member States to develop a national strategy for education and training, underlining the fundamental importance of sustainable programmes for building competence in radiation, transport and waste safety, as a key component of safety infrastructure. Furthermore Member States that receive assistance from IAEA are obliged to apply IAEA Safety Standards which require, inter alia, governments to establish a national policy and strategy for safety, including provisions for acquiring and maintaining the necessary competence nationally for ensuring safety. IAEA's Division of Radiation, Transport and Waste Safety is assisting Member States to develop their own national strategies in Asia and the Pacific via the Regional project RAS/9/066 on ''Strengthening Education and training Infrastructure, and Building Competence in Radiation Safety'', which includes, inter alia, Regional Workshops on National Strategies for education and training in radiation transport and waste safety. IAEA's Regional Training Centres (RTCs) in Malaysia and Syrian Arabic Republic are key partners in the Asian and the Pacific region.

  5. Education and Training in Radiation, Transport and Waste Safety Newsletter, No. 2d, June 2013

    International Nuclear Information System (INIS)

    The IAEA Strategic Approach to Education and Training in Radiation, Transport and Waste Safety (2011-2020) provides a framework for establishing a sustainable education and training infrastructure in Member States that addresses national needs for building and maintaining competence in radiation, transport and waste safety that is consistent with IAEA Safety Standards. For this purpose, IAEA's General Conference has encouraged Member States to develop a national strategy for education and training, underlining the fundamental importance of sustainable programmes for building competence in radiation, transport and waste safety, as a key component of safety infrastructure. Furthermore Member States that receive assistance from IAEA are obliged to apply IAEA Safety Standards which require, inter alia, governments to establish a national policy and strategy for safety, including provisions for acquiring and maintaining the necessary competence nationally for ensuring safety. IAEA's Division of Radiation, Transport and Waste Safety is assisting Member States to develop their own national strategies in Latin America via the Regional Project RLA/9/070 on ''Strengthening Education and training Infrastructure, and Building Competence in Radiation Safety'', which includes, inter alia, Regional Workshops on National Strategies for education and training in radiation transport and waste safety. IAEA's Regional Training Centres (RTCs) in Argentina and Brazil are key partners in the Latin-American region.

  6. Radiation safety of children in X-ray examinations

    International Nuclear Information System (INIS)

    Problem of radiation safety of children in X-ray examinations is studied on the base of review of Soviet and foreign publications. Data on frequency of X-ray investigations and radiation loadings depending on sex and age of children are presented. Devices used in children X-ray examinations are decsribed. Recommendations on improving radiation safety of patients in pediatrics are given

  7. Radiation shielding and safety analysis for SPring-8

    Energy Technology Data Exchange (ETDEWEB)

    Asano, Yoshihiro; Sasamoto, Nobuo [Japan Atomic Energy Research Inst., Kamigori, Hyogo (Japan). Kansai Research Establishment

    1998-03-01

    The methods of shielding design and safety analysis applied to SPring-8 are summarized. SPring-8, a third generation synchrotron radiation facility, is the facility with the highest stored electron energy of 8 GeV and very low beam emittance of 5.5 nm{center_dot}rad. Because of these distinguished features, a variety of radiation issues have to be taken up, requiring the latest information for analyses. In this technical report are described the calculational methods and the conditions for the following shielding matters as well as verification of the validity; a bulk shielding, synchrotron radiation beamline shielding, skyshine, streaming through ducts and mazes, induced activities in air, cooling water and targets, and incident analysis due to abnormal beam losses. (author)

  8. 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.

  9. Laser sources in dentistry and radiation safety regulations

    Science.gov (United States)

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

    2007-02-01

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

  10. Thermoluminescence Dosimetry Applied to Radiation Protection

    DEFF Research Database (Denmark)

    Christensen, Poul; Bøtter-Jensen, Lars; Majborn, Benny

    1982-01-01

    This is a general review of the present state of the development and application of thermoluminescence dosimetry (TLD) for radiation protection purposes. A description is given of commonly used thermoluminescent dosimeters and their main dosimetric properties, e.g. energy response, dose range......, fading, and LET dependence. The applications of thermoluminescence dosimetry in routine personnel monitoring, accident dosimetry, u.v. radiation dosimetry, and environmental monitoring are discussed with particular emphasis on current problems in routine personnel monitoring. Finally, the present state...

  11. Code of practice for safety in laboratory - non ionising radiation

    International Nuclear Information System (INIS)

    The code identifies the non-ionizing radiation encountered in laboratories and the associated hazards. The code is intended as a laboratory standard reference document for general information on safety requirements relating to the usage of non-ionizing radiations in laboratories. The nonionizing radiations cover in this code, namely, are ultraviolet radiation, visible light, radio-frequency radiation, lasers, sound waves and ultrasonic radiation. (author)

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

    Science.gov (United States)

    Goldin, Eric M; Pryor, Kathryn H

    2016-02-01

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

  13. NCRP Program Area Committee 2: Operational Radiation Safety

    Energy Technology Data Exchange (ETDEWEB)

    Pryor, Kathryn H.; Goldin, Eric M.

    2016-02-29

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

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

    International Nuclear Information System (INIS)

    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

  15. The knowledge, attitude and behavior on the radiation safety management for dental hygiene major students

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, Yeo Reong; Cho, Pyong Kon; Kim, Yong Min [Dept. of Radiological Science, Daegu Catholic University, Daegu (Korea, Republic of); Han, Eun Ok [Korea Academy of Nuclear Safety, Seoul (Korea, Republic of); Jang, Hyon Chul [Dept. of Radiological Technology, Suseong College, Daegu (Korea, Republic of); Ko, Jong Kyung [Radiation Safety Management Commission, Daegu Health College, (Korea, Republic of)

    2015-12-15

    This study tries to find the educational basis based on the radiation safety knowledge, attitudes and behaviors to check the level of radiation safety behavior in domestic students who study dental hygiene. The students of 3rd and 4th grades in 83 universities which have registered on the Korean University Education Council were involved, and they were given a questionnaire for this study. The questionnaire was provided via visit with 20 copies to each university (total 1660 copies), mail by post and e-mail. Among them, we analyzed only 723 copies that we can trust. The data were analyzed with frequency, percentage, mean, standard deviation and Pearson’s correlation using the SPSS/WIN 15.0. As a result, there are correlations in the students’ knowledge, attitudes and behaviors regarding the radiation safety management. It means that the education which can improve the knowledge and attitudes should be applied to increase the action level of the radiation safety. In addition, the physical environment is the most closely correlated with the individual behavior, so it will be limited to improve the behavioral levels of the radiation safety if the physical environment is not prepared. Therefore, the physical environment should be supported to enhance the level of the radiation safety activity, and to increase the individual attitude level of radiation safety. The knowledge level of the radiation safety management is relatively lower than the attitudes level, and the behavior level is the lowest. Therefore, the education policy of the safety behavior must be enhanced. For domestic students, the educational intervention is necessary to improve their behavioral level of radiation safety management because they will be able to reduce the amount of radiation exposure of their patients in dental care after getting a job.

  16. Environmental and source monitoring for purposes of radiation protection. Safety guide

    International Nuclear Information System (INIS)

    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

  17. The 7 basic tools of quality applied to radiological safety

    International Nuclear Information System (INIS)

    This work seeks to establish a series of correspondences among the search of the quality and the optimization of the doses received by the occupationally exposed personnel. There are treated about the seven basic statistic tools of the quality: the Pareto technique, Cause effect diagrams, Stratification, Verification sheet, Histograms, Dispersion diagrams and Graphics and control frames applied to the Radiological Safety

  18. Radiation safety for baggage x-ray inspection systems

    International Nuclear Information System (INIS)

    This book is an outgrowth of a course on radiation safety aimed at technicians responsible for conducting maintenance on baggage x-ray inspection systems used in federally operated facilities. The need for a single reference book became apparent to the instructor in 1984. In an effort to provide a cohesive development of the subject, a set of lecture notes was prepared and revised annually since 1984, from which this book has evolved. This book is intended to present concepts necessary for an elementary but comprehensive knowledge of radiation safety. While some material coverage may appear somewhat detailed, it is a deliberate attempt to strengthen areas of demonstrated weaknesses observed in course attenders and to provide guidance on the numerous questions about man-made radiation asked by course attenders over the years. Numerical examples are included in most chapters for clarity and ease of understanding. The problems given at the end of most chapters provide the reader with the opportunity of applying the material presented in the chapters to situations of practical interest. It is important that these problems be considered an integral part of the course and students attempt to solve them. 36 refs., 9 tabs., 17 figs

  19. Optical fiber applied to radiation detection

    Energy Technology Data Exchange (ETDEWEB)

    Junior, Francisco A.B.; Costa, Antonella L.; Oliveira, Arno H. de; Vasconcelos, Danilo C., E-mail: fanbra@yahoo.com.br, E-mail: antonella@nuclear.ufmg.br, E-mail: heeren@nuclear.ufmg.br, E-mail: danilochagas@yahoo.com.br [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Escola de Engenharia. Departamento de Engenharia Nuclear

    2015-07-01

    In the last years, the production of optical fibers cables has make possible the development of a range of spectroscopic probes for in situ analysis performing beyond nondestructive tests, environmental monitoring, security investigation, application in radiotherapy for dose monitoring, verification and validation. In this work, a system using an optical fiber cable to light signal transmission from a NaI(Tl) radiation detector is presented. The innovative device takes advantage mainly of the optical fibers small signal attenuation and immunity to electromagnetic interference to application for radiation detection systems. The main aim was to simplify the detection system making it to reach areas where the conventional device cannot access due to its lack of mobility and external dimensions. Some tests with this innovative system are presented and the results stimulate the continuity of the researches. (author)

  20. Integration of radiation protection in safety management: sharing best practices between radiation protection and other safety areas

    International Nuclear Information System (INIS)

    Full text: The Institute for Reference Materials and Measurements (IRMM) located in Geel is one of the seven institutes of the Joint Research Centre of the European Commission (EC, DG JRC). The institute was founded in 1960 as a nuclear research centre, but has gradually shifted its activities to also include 'non-nuclear' domains, mainly in the areas of food safety and environmental surveillance. As the activities on the IRMM site are currently quite diversified, they necessitate the operation of nuclear controlled areas, accelerators, as well as bio safety restricted areas and chemical laboratories. Therefore, the care for occupational health and safety and for environmental protection has to take into consideration various types of hazards and threats. Recently an integrated management system according to ISO-9001, ISO-14001 and OHSAS-18001 was implemented. The integrated system combines 'vertically' quality, occupational health and safety and environmental issues and covers 'horizontally' the nuclear, biological and chemical fields. The paper outlines how the radiation protection can be included in an overall health, safety and environmental management system. It will give various practical examples where synergies can be applied: 1-) the overall policy; 2-) The assessment and ranking of all risks and the identification, in a combined way, of the appropriate prevention measures; 3-) The planning and review of related actions; 4-) The monitoring, auditing and registration of anomalies and incidents and the definition of corrective actions; 5-) The training of personnel based on lessons learned from past experiences; 6-) The organisation of an internal emergency plan dealing with nuclear and non-nuclear hazards. Based on these examples, the benefits of having an integrated approach are commented. In addition, the paper will illustrate how the recent ICRP fundamental recommendations and more particularly some of the principles of radiation protection such as

  1. 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

  2. Safety and Radiation Protection at Swedish Nuclear Power Plants 2005

    International Nuclear Information System (INIS)

    -to-date and documented safety analyses must be prepared and actively be included in both the preventive safety work and in connection with plant modifications. The licensees have implemented design analysis projects for a long period of time and clarified and stringent regulations for safety analyses have entered into force in 2005. As a result, updated safety reports exist for many of the facilities and schedules exist for the supplementary work that remains to be done. SKI's reinforced supervision of Barsebaeck 2 continued until the closure of the reactor on May 31, 2005. In SKI's opinion, BKAB mainly handled the lengthy facility closure in a satisfactory manner. The handling of nuclear waste at the nuclear facilities has mainly functioned well. The same applies to the operation of the Repository for Low and Intermediate-level Operational Waste (SFR-1) and the Central Interim Storage Facility for Spent Nuclear Fuel (CLAB). The overall evaluation of the Swedish Radiation Protection Authority (SSI) is that radiation protection at Swedish nuclear power plants has functioned well in 2005. The total radiation dose to the personnel at Swedish nuclear power plants was 9.2 manSv, which agrees with the average value of the total radiation doses over the last five years (9 manSv). No-one received a radiation dose in excess of the established dose limits and the radiation levels in the facilities are largely unchanged compared with previous years. The radiation doses to the public from the Swedish nuclear power plants continue to be low. SSI considers that continuous work is also needed in the future at the facilities to further reduce radioactive releases by applying the best available technique (BAT) and other measures. The control measurements that SSI is conducting on environmental samples from around the nuclear power facilities as well as on radioactive releases to water show a good agreement with the licensees' own measurements

  3. Safety and Radiation Protection at Swedish Nuclear Power Plants 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-05-15

    other things. Up-to-date and documented safety analyses must be prepared and actively be included in both the preventive safety work and in connection with plant modifications. The licensees have implemented design analysis projects for a long period of time and clarified and stringent regulations for safety analyses have entered into force in 2005. As a result, updated safety reports exist for many of the facilities and schedules exist for the supplementary work that remains to be done. SKI's reinforced supervision of Barsebaeck 2 continued until the closure of the reactor on May 31, 2005. In SKI's opinion, BKAB mainly handled the lengthy facility closure in a satisfactory manner. The handling of nuclear waste at the nuclear facilities has mainly functioned well. The same applies to the operation of the Repository for Low and Intermediate-level Operational Waste (SFR-1) and the Central Interim Storage Facility for Spent Nuclear Fuel (CLAB). The overall evaluation of the Swedish Radiation Protection Authority (SSI) is that radiation protection at Swedish nuclear power plants has functioned well in 2005. The total radiation dose to the personnel at Swedish nuclear power plants was 9.2 manSv, which agrees with the average value of the total radiation doses over the last five years (9 manSv). No-one received a radiation dose in excess of the established dose limits and the radiation levels in the facilities are largely unchanged compared with previous years. The radiation doses to the public from the Swedish nuclear power plants continue to be low. SSI considers that continuous work is also needed in the future at the facilities to further reduce radioactive releases by applying the best available technique (BAT) and other measures. The control measurements that SSI is conducting on environmental samples from around the nuclear power facilities as well as on radioactive releases to water show a good agreement with the licensees' own measurements.

  4. Radiation safety interlock system at Indus accelerator complex

    International Nuclear Information System (INIS)

    A Radiation Safety Interlock System (a part of Radiation Safety System) that ensures protection of personnel during the facility operation from radiation hazards induced by electron beam and synchrotron radiation has been in operation very effectively for over a decade at Indus Accelerator complex (IAC). Radiation Safety Interlock System (RSIS) consists of two parts - Safety Interlock Unit (SIU) and Mode Selection Unit (MSU). Separate Safety Interlock Units are provided for four machine areas of IAC, namely Microtron and Booster, Indus-1 storage ring, Indus-1 user hall and Indus-2 storage ring. The efficacy of the Safety Interlock Units of Indus-1 user hall, Indus-1 storage ring and Indus-2 storage ring is governed by the operation modes that are selected through Mode Selection Unit. RSIS has been modified during past 1 and 1/2 year by addition of new interlock features and changes in the final beam control scheme. Machine Safety Interlock System (MSIS) was also interlocked with RSIS to facilitate termination of machine operation in case of any unsafe condition of Indus-2 systems. This paper describes the design philosophy, recent modifications, implementation and future upgrade plans of the present Radiation Safety Interlock Systems at Indus accelerator complex. (author)

  5. Challenges in strengthening radiation safety and security programme in Malaysia

    International Nuclear Information System (INIS)

    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)

  6. Towards a radiation safety culture at Universidad Nacional de Colombia

    International Nuclear Information System (INIS)

    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

  7. Radiation safety and vascular access: attitudes among cardiologists worldwide

    International Nuclear Information System (INIS)

    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

  8. 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

  9. Study of fieldbus technology applied in a sterilization plant control and safety systems

    International Nuclear Information System (INIS)

    Several sterilization processes have been used in these years for treatment of countless products. Some processes use high temperatures, thermal shocks and chemical agents. With the discovery of the ionizing radiation and its posterior technological developments turned possible application of that process, in 1960, also in the the sterilization, denominated radiation sterilization. This process became also applied in another areas of health and industrial as food conservation, gemstones enhancement and others. The radiation sterilization requests an effective control and it needs a high level of safety. The commercial use of the computers applied in industrial automation provides and the domain of new technologies in this field provides new applications then new designs now is possible. The Fieldbus technology, a new digital communication protocol, like a Local Area Network, can be an alternative in the cobalt-60 irradiation plant. The present work suggests, evaluates, qualifies and quantifies this possibility. (author)

  10. Sweden's Cooperation with Eastern Europe in Radiation Safety 2010

    International Nuclear Information System (INIS)

    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

  11. Nuclear safety and radiation protection in France in 2011

    International Nuclear Information System (INIS)

    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

  12. 10. Latin American Regional Congress IRPA Protection and Radiation Safety

    International Nuclear Information System (INIS)

    The 10.Latin American Regional Congress IRPA Protection and Radiation Safety was organized by the Radioprotection Argentine Society, in Buenos Aires, between the april 12 and 17, 2015. In this event, were presented almost 400 papers about these subjects: radiation protection in medicine and industry; radiological and nuclear emergencies; NORM (Natural Occurring Radioactive Materials); reactors; radiation dosimetry; radiotherapy; non-ionizing radiations; policies and communications; etc.

  13. Characteristics of radiation safety for synchrotron radiation and X-ray free electron laser facilities.

    Science.gov (United States)

    Asano, Yoshihiro

    2011-07-01

    Radiation safety problems are discussed for typical electron accelerators, synchrotron radiation (SR) facilities and X-ray free electron laser (XFEL) facilities. The radiation sources at the beamline of the facilities are SR, including XFEL, gas bremsstrahlung and high-energy gamma ray and photo-neutrons due to electron beam loss. The radiation safety problems for each source are compared by using 8 GeV class SR and XFEL facilities as an example.

  14. Radiation safety in Indonesia: An overview of infrastructures

    International Nuclear Information System (INIS)

    Basic Safety Standards state that essential of a national infrastructure are: legislation and regulation; a Regulatory Authority empowered to authorize and inspect regulated activities and to enforce the legislation and regulations; sufficient resources; and adequate numbers of trained personnel. This paper discussed history, present and prospects future of radiation safety infrastructures in Indonesia. After The Second World War and the declaration of freedom, Indonesia initiated to realize that the potential hazard of the use of ionizing radiation should be controlled. The first highest regulation concerning control of the use of ionizing radiation was Act. No. 31 Year 1964. To execute the Act, The Government Regulation No. 33 Year 1965 has been enacted. Then to implement radiation safety, The First Regulation for Radiation Safety was The Government Regulation No. 11 Year 1975 followed the others regulations. Due to the development in nuclear science and technology, the Act. No. 31 Year 1964 was superseded by The Act No.10 Year 1997. The main different of the new act is separation the authority in executing and controlling into different institution. The regulatory body is now called Nuclear Energy Control Board (BAPETEN), and one of the executing bodies which is National Nuclear Energy Agency (BATAN). Resources (facilities and services), education and training programs to support radiation safety infrastructures are also discussed in this paper. By the competent authorities and institutions, Indonesia has the legal legislation and adequate infrastructure to ensure implementation, enforcement and compliance with the radiation safety nationally in the near future. (author)

  15. Systematic approach to training for competence building in radiation safety

    International Nuclear Information System (INIS)

    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)

  16. An evaluation of the uranium mine radiation safety course

    International Nuclear Information System (INIS)

    The report evaluates the Uranium Mine Radiation Safety Course focussing on the following areas: effectivenss of the course; course content; instructional quality; course administration. It notes strengths and weaknesses in these areas and offers preliminary recommendations for future action

  17. The IAEA's sub programme on the safety of radiation sources and the security of radioactive materials

    International Nuclear Information System (INIS)

    In compliance with its mandate to establish standards of safety and to provide for their application with respect to radiation sources, the International Atomic Energy Agency has developed a subprogramme aimed at providing Member States guidance and assistance on achieving regulatory control and the safe use of the sources. The guidance addresses the establishment of a Regulatory Programme, with focus on a system for notification and authorization (registration and licensing) and inspection of radiation sources, including check lists for review of safety. It also includes methods for assessing its effectiveness of the Regulatory Programme and is complemented with tools for the management of data by the Regulatory Authority and Services to assist Member States in assessment and implementation of the programme. In addition, technical guidance for the safety of radiation sources includes both prospective and retrospective safety assessment. Retrospective methods have been used resulting in the publication and dissemination of information and lessons from accidents, both individual accident reports and lessons from collection of accident for the practices with major sources (industrial radiography, irradiators and radiotherapy). Prospective methods will include guidance on the application of the principles of radiation protection to potential exposure, as well as methods to apply the principles, such as identification and evaluation of scenarios. Practice specific reports will address the major radiation sources. A research programme will be dedicated to apply Probabilistic Safety Assessment (PSA) to radiation sources. (author)

  18. The safety of radiation sources and radioactive materials in China

    International Nuclear Information System (INIS)

    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)

  19. Radiation Safety of Accelerator Facility with Regard to Regulation

    International Nuclear Information System (INIS)

    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)

  20. Industrial safety and applied health physics. Annual report for 1980

    International Nuclear Information System (INIS)

    Information is reported in sections entitled: radiation monitoring; Environmental Management Program; radiation and safety surveys; industrial safety and special projects; Office of Operational Safety; and training, lectures, publications, and professional activities. There were no external or internal exposures to personnel which exceeded the standards for radiation protection as defined in DOE Manual Chapter 0524. Only 35 employees received whole body dose equivalents of 10 mSv (1 rem) or greater. There were no releases of gaseous waste from the Laboratory which were of a level that required an incident report to DOE. There were no releases of liquid radioactive waste from the Laboratory which were of a level that required an incident report to DOE. The quantity of those radionuclides of primary concern in the Clinch River, based on the concentration measured at White Oak Dam and the dilution afforded by the Clinch River, averaged 0.16 percent of the concentration guide. The average background level at the Perimeter Air Monitoring (PAM) stations during 1980 was 9.0 μrad/h (0.090 μGy/h). Soil samples were collected at all perimeter and remote monitoring stations and analyzed for eleven radionuclides including plutonium and uranium. Plutonium-239 content ranged from 0.37 Bq/kg (0.01 pCi/g) to 1.5 Bq/kg (0.04 pCi/g), and the uranium-235 content ranged from 0.7 Bq/kg (0.02 pCi/g) to 16 Bq/kg (0.43 pCi/g). Grass samples were collected at all perimeter and remote monitoring stations and analyzed for twelve radionuclides including plutonium and uranium. Plutonium-239 content ranged from 0.04 Bq/kg (0.001 pCi/g) to 0.07 Bq/kg (0.002 pCi/g), and the uranium-235 content ranged from 0.37 Bq/kg (0.01 pCi/g) to 12 Bq/kg

  1. Developments of radiation safety requirements for the management of radiation devices

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hee Seock [Pohang Accelerator Lab, Pohang (Korea, Republic of); Choi, Jin Ho [Gachun University of Medicine and science, Incheon (Korea, Republic of); Cheong, Yuon Young [Asan Medical Center, Seoul (Korea, Republic of)] (and others)

    2002-03-15

    The approach of the risk-informed regulatory options was studied to develop the radiation safety requirements for the managements for radiation devices. The task analysis, exposure, accident scenario development, risk analysis, and systematic approach for regulatory options was considered in full, based on the NRC report, 'NUREG/CR-6642', and the translation of its core part was conducted for ongoing research. In this methodology, the diamond tree that includes human factors, etc, additionally with normal event tree, was used. According to the analysis results of this approach, the risk analysis and the development of regulatory options were applied for the electron linear accelerators and the qualitative results were obtained. Because the field user groups were participated in this study could contribute to the basis establishment of the risk-informed regulation policy through securing consensus and inducing particle interests. It will make an important role of establishing the detail plan of ongoing research.

  2. SAFETY

    CERN Multimedia

    Niels Dupont

    2013-01-01

    CERN Safety rules and Radiation Protection at CMS The CERN Safety rules are defined by the Occupational Health & Safety and Environmental Protection Unit (HSE Unit), CERN’s institutional authority and central Safety organ attached to the Director General. In particular the Radiation Protection group (DGS-RP1) ensures that personnel on the CERN sites and the public are protected from potentially harmful effects of ionising radiation linked to CERN activities. The RP Group fulfils its mandate in collaboration with the CERN departments owning or operating sources of ionising radiation and having the responsibility for Radiation Safety of these sources. The specific responsibilities concerning "Radiation Safety" and "Radiation Protection" are delegated as follows: Radiation Safety is the responsibility of every CERN Department owning radiation sources or using radiation sources put at its disposition. These Departments are in charge of implementing the requi...

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

    International Nuclear Information System (INIS)

    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

  4. Nuclear power plant radiation: personnel safety aspects

    International Nuclear Information System (INIS)

    Reactor using water as coolant, moderator, and heat transfer can produce a sufficiently great internal and external radiation caused by contamination. The process of contamination and actions that must be taken to avoid radiation workers from receiving more than the maximum permissible dose are presented. (author)

  5. AN ADVANCED TOOL FOR APPLIED INTEGRATED SAFETY MANAGEMENT

    Energy Technology Data Exchange (ETDEWEB)

    Potts, T. Todd; Hylko, James M.; Douglas, Terence A.

    2003-02-27

    WESKEM, LLC's Environmental, Safety and Health (ES&H) Department had previously assessed that a lack of consistency, poor communication and using antiquated communication tools could result in varying operating practices, as well as a failure to capture and disseminate appropriate Integrated Safety Management (ISM) information. To address these issues, the ES&H Department established an Activity Hazard Review (AHR)/Activity Hazard Analysis (AHA) process for systematically identifying, assessing, and controlling hazards associated with project work activities during work planning and execution. Depending on the scope of a project, information from field walkdowns and table-top meetings are collected on an AHR form. The AHA then documents the potential failure and consequence scenarios for a particular hazard. Also, the AHA recommends whether the type of mitigation appears appropriate or whether additional controls should be implemented. Since the application is web based, the information is captured into a single system and organized according to the >200 work activities already recorded in the database. Using the streamlined AHA method improved cycle time from over four hours to an average of one hour, allowing more time to analyze unique hazards and develop appropriate controls. Also, the enhanced configuration control created a readily available AHA library to research and utilize along with standardizing hazard analysis and control selection across four separate work sites located in Kentucky and Tennessee. The AHR/AHA system provides an applied example of how the ISM concept evolved into a standardized field-deployed tool yielding considerable efficiency gains in project planning and resource utilization. Employee safety is preserved through detailed planning that now requires only a portion of the time previously necessary. The available resources can then be applied to implementing appropriate engineering, administrative and personal protective equipment

  6. Ordinance on the Finnish Centre of Radiation and Nuclear Safety

    International Nuclear Information System (INIS)

    This Ordinance was adopted in implementation of the 1983 Act setting up the Finnish Centre for Radiation and Nuclear Safety and the 1987 Nuclear Energy Act and entered into force on 1 November 1990. The Ordinance specifies the tasks of the Centre, as provided under both Acts, and gives it several supplementary responsibilities. In addition to its overall competence in respect of radiation safety, the Centre will carry out research into and supervise the health effects of radiation and maintain a laboratory for national measurements in that field. The Ordinance also sets out the Centre's organisation chart and the staff duties

  7. Industrial safety and applied health physics. Annual report for 1978

    International Nuclear Information System (INIS)

    There were no external or internal exposures to personnel which exceeded the standards for radiation protection as defined in DOE Manual Chapter 0524. Only 39 employees received whole body dose equivalents of one rem or greater. The highest whole body dose equivalent to an employee was 3.3 rem. The highest internal exposure was less than 25% of a maximum permissible dose for any calendar quarter. During 1978, 23 portable instruments were added to the inventory and 228 retired. The total number in service on January 1, 1979, was 1023. There were no releases of gaseous waste or liquid radioactive waste from the laboratory which were of a level that required an incident report to DOE. The average background level at the PAM stations during 1978 was 9.3 μR/hr, or 81 mR/yr. Soil samples were collected at all perimeter and remote monitoring stations and analyzed for eleven radionuclides including plutonium and uranium. Grass samples were collected and analyzed for twelve radionuclides including plutonium and uranium. During 1978, the Radiation and Safety Surveys personnel continued to assist the operating groups in keeping contamination, air concentrations, and personnel exposure levels below the established maximum permissible levels. Fourteen radiation incidents involving radioactive materials were recorded during 1978. Of the 582,000 articles of wearing apparel and 192,000 articles, such as mops, laundry bags, towels, etc., monitored during 1978 about four percent were found to be contaminated. Three lost workday cases occurred at ORNL in 1978, a frequency rate of 0.07. The Serious Injury frequency rate for 1978 was 1.40, as based on the new OSHA system for recording injuries and illness (RII). A total of 55 days were lost or charged for the three lost workday cases in 1978

  8. Probabilistic safety analysis of radiation treatments with linear accelerator (Spanish Ed.)

    International Nuclear Information System (INIS)

    This publication addresses the issue of accidental exposures of radiotherapy patients and how to avoid them. More proactive approaches are required to anticipate and thus avoid situations that could lead to accidental exposures. In this context, the International Atomic Energy Agency (IAEA) and the Ibero American Forum of Radiation and Nuclear and Safety Regulatory Agencies (the FORO) have applied proactive methods, such as probabilistic safety assessment to radiotherapy treatments with accelerators. The methodology and results of this exercise are described in this publication.

  9. Multigroup albedo method applied to gamma radiation shielding

    International Nuclear Information System (INIS)

    The Albedo method, when applied to shielding calculations, is characterized by following the radiation through the materials, determining the reflected, absorbed and transmitted fractions of the incident current, independently of flux calculations. The excellent results obtained to neutron shielding cases in which the diffusion approximation could be applied motivated this work, where the method was applied in order to develop a multigroup and multilayered algorithm. A gamma radiation shielding simulation was carried out to a system constituted by three infinite slabs of varied materials and six energy groups. The results obtained by Albedo Method were the same generated by ANISN, a consecrated deterministic nuclear code. Concludingly, this work demonstrates the validity of Albedo Method to gamma radiation shielding analysis through its agreement with the full Transport Equation. (author)

  10. Safety study on ultra-violet radiation

    International Nuclear Information System (INIS)

    Ultra-violet radiation (UVR) falls under category of non-ionising radiation (NIR). Excessive exposure to ultra-violet radiation (UVR) may cause significant health hazard to human beings. The sun is the main source of UVR which produce the radiation in the form of solar radiation. Due to its ability to cause hazard, a study of UV solar radiation exposure was conducted around Bangi, Selangor. For this preliminary study, selected measurement location were around Universiti Kebangsaan Malaysia (UKM) and MINT. The study was carried out by direct measurement of the radiation quantitatively with due consideration given on variation of time, cloud and weather condition. Research radiometer model IL 1700 with three different sensors were used for measurement of UV-A, UV-B and UV-C and they were connected to Laptop with LabView software for data analysis. The results were compared with the permissible exposure limits recommended by IRPA/ICNIRP. In addition to assessment of direct exposure to UVR the study also look into the effectiveness of absorption for some material such as tinted glass and different kind of clothing. The results showed that UV-A, UV-B and UV-C emitted directly from the sun around UKM and MINT were below the permissible limit recommended by IRPA/ICNIRP for members of public (30 J/m2 or 1mWm-2). Besides that, they study found that tinted glass was effective to protect us from excessive exposure to UVR . For clothing we found that the silk fabric with light colour is more applicable for filtering UV radiation, compare to the other type of fabric. (Author)

  11. Thermal Radiation for Structural Fire Safety Design

    DEFF Research Database (Denmark)

    Hertz, Kristian Dahl

    2006-01-01

    The lecture notes give a short introduction of the theory of thermal radiation. The most elementary concepts and methods are presented in order to give a fundamental knowledge for calculation of the load bearing capacities of fire exposed building constructions.......The lecture notes give a short introduction of the theory of thermal radiation. The most elementary concepts and methods are presented in order to give a fundamental knowledge for calculation of the load bearing capacities of fire exposed building constructions....

  12. Thermal Radiation for Structural Fire Safety Design

    DEFF Research Database (Denmark)

    Hertz, Kristian

    1999-01-01

    The lecture note gives a short introduction of the theory of thermal radiation. The most elementary concepts and methods are presented in order to give a fundamental knowledge for calculation of the load bearing capacities of fire exposed building constructions.......The lecture note gives a short introduction of the theory of thermal radiation. The most elementary concepts and methods are presented in order to give a fundamental knowledge for calculation of the load bearing capacities of fire exposed building constructions....

  13. Practice specific model regulations: Radiation safety of non-medical irradiation facilities. Interim report for comment

    International Nuclear Information System (INIS)

    The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (Standards or BSS) were published as IAEA Safety Series No. 115 in 1996. This publication is the culmination of efforts over the past decades towards harmonization of radiation protection and safety standards internationally, and is jointly sponsored by the Food and Agriculture Organisation of the United Nations (FAO), the International Atomic Energy Agency (IAEA), the International Labour Organisation (ILO), the OECD Nuclear Energy Agency (OECD/NEA), the Pan American Health Organisation (PAHO) and the World Health Organisation (WHO). The purpose of the Standards is to establish basic requirements for protection against the risks associated with exposure to ionizing radiation and for the safety of radiation sources that may deliver such exposure (hereinafter called 'radiation safety'). The requirements are based on the principles set out in the Safety Fundamentals, published as IAEA Safety Series Nos 110 and 120. The Standards can be implemented only through an effective radiation safety infrastructure that includes adequate laws and regulations, an efficient regulatory system, supporting experts and services, and a 'safety culture' shared by all those with responsibilities for protection, including both management and workers. IAEA-TECDOC-1067, Organization and Implementation of a National Regulatory Infrastructure Governing Protection against Ionizing Radiation and the Safety of Radiation Sources, provides detailed guidance on how to establish or improve national radiation safety infrastructure in order to implement the requirements of the Standards. The TECDOC covers the elements of a radiation safety infrastructure at the national level needed to apply the Standards to radiation sources such as those used in medicine, agriculture, research, industry and education. It also provides advice on approaches to the organization and operation of

  14. Study of fieldbus technology confiability when applied in a Sterilization plant control and safety systems

    International Nuclear Information System (INIS)

    Several sterilization processes have been used in these years for treatment of countless products. Some processes use high temperatures, thermal shocks and chemical agents. With the discovery of the ionizing radiation and its posterior technological developments turned possible the application of that process, in 1960, also in the sterilization, denominated radiation sterilization. This process became also applied in another areas of health and industrial as food conservation, gemstones enhancement and others. The radiation sterilization requests an effective control and it needs a high level of safety. The commercial use of the computers applied in industrial automation provides and the domain of new technologies in this field provides news applications then new designs now is possible. The Fieldbus technology, a new digital communication protocol, like a Local Area Network, can be an alternative in the cobalt-60 irradiation plant. This paper show preliminary study about confiability in systems using Fieldbus technology. This technology was simulated in sterilization plant control and safety systems and the fail probability was quantified using Fail Tree Analysis Method. Fieldbus technology can be used in sterilization plants because the confiability in this systems is like PLCs and relays systems, was the conclusion

  15. Radiation safety and formation of public opinion

    International Nuclear Information System (INIS)

    Full text: Team-administrative system of long years has been a reason of environmental pollution and health consequences and still does. This includes soil pollution with pesticides, ecological condition of micro and macro flora of the Caspian Sea, soil pollution with oil, deforestation and etc. Scientists and environmental NGOs have given some information to public and public opinion has already been formed on this issue. But public opinion is not necessarily formed on radiation - the most important and invisible problem. The reason of this is that radiation danger has been hidden as a closed theme from the public. After the soviet collapse this problem is also being revealed. Number of NGOs have held the seminar on this issue and given some information to public. The researches cover the following problems:To hold the public monitoring in the fields polluted with oil and separate it from the other fields by determining the fields polluted with radiation. To take measures in order to prevent public entrance to these fields; To inform about the usage of radiation based equipment in the industrial fields and to hold the regular monitoring; To advertise the differential signs of radiation sources in the city landfill and other polluted zones; To broaden the advocacy on ultraviolet rays and their influence to human health; To disseminate the brochures and advertisement papers on high technical radiation and their influence to human health; To analyze the radio environmental condition around the Gabala Radar Station; To advocate the possible radiation danger in using the x-ray and other medical equipment; Analyze the possible radon danger in shipping materials; To create the idea on possible transition of radioactive gases and elements from neighbor countries; Creation of idea on possible danger around the high voltage. The formation of public opinion on mentioned problem will depend on combining the scientists' and NGOs activities

  16. Framework for applying probabilistic safety analysis in nuclear regulation

    International Nuclear Information System (INIS)

    The traditional regulatory framework has served well to assure the protection of public health and safety. It has been recognized, however, that in a few circumstances, this deterministic framework has lead to an extensive expenditure on matters hat have little to do with the safe and reliable operation of the plant. Developments of plant-specific PSA have offered a new and powerful analytical tool in the evaluation of the safety of the plant. Using PSA insights as an aid to decision making in the regulatory process is now known as 'risk-based' or 'risk-informed' regulation. Numerous activities in the U.S. nuclear industry are focusing on applying this new approach to modify regulatory requirements. In addition, other approaches to regulations are in the developmental phase and are being evaluated. One is based on the performance monitoring and results and it is known as performance-based regulation. The other, called the blended approach, combines traditional deterministic principles with PSA insights and performance results. (author)

  17. Albedo method applied to coupled neutron-gamma shielding radiations

    International Nuclear Information System (INIS)

    The Albedo Theory was applied in order to develop an one-group algorithm for coupled neutron-gamma shielding calculations. The configuration analyzed consists of multilayered plane systems, where a incident neutron current generates gamma radiation through neutron-gamma reactions. The results obtained by Albedo Method and ANISN code have shown excellent agreement. (author)

  18. Safety and Radiation Protection at Swedish Nuclear Power Plants 2004

    International Nuclear Information System (INIS)

    In 2004, no severe events occurred which challenged the safety at Swedish nuclear power plants. Two events were classified as Level 1 events on the 7-point International Nuclear Event Scale. The events are described in the chapter Operating Experience. During the year, relatively little new degradation and deficiencies were detected in the reactor barriers. The number of fuel defects is constantly decreasing. The same applies to the number of defects in the pressure-bearing systems. On the other hand, SKI has observed that damage is beginning to occur in the reactor containment. Applied control programmes are effective and capture most of the damage at an early stage before safety is affected. However, individual defects have been detected in material where such degradation was not anticipated and which is currently not regularly checked. SKI will follow up these observations thoroughly in order to judge whether there is a need for increased inspections. During the year, two defects found in the reactor containment were reported. The damage and degradation that occurred indicate that the causes were mainly due to defects during construction, or during subsequent plant modification. Taking into account the difficulty of inspecting the reactor containments and other vital building structures reliably, it is important for the licensees to continue to study possible ageing and degradation mechanisms that can affect the integrity and safety of the components. SKI continuously follows the progress of the degradation in the mechanical devices and building structures that form the plant barriers and defence-in-depth system. This includes both overall evaluations of the progress of degradation as a whole and the progress of degradation in each facility. Furthermore, the occurrence of different degradation mechanisms is followed. The power companies have intensified the rate of investment in nuclear power plants. Modernization work and safety reviews stipulated by the

  19. Report on nuclear and radiation safety in Slovenia in 2000

    International Nuclear Information System (INIS)

    The Slovenian Nuclear Safety Administration (SNSA), in co-operation with the Health Inspectorate of the Republic of Slovenia, the Administration for Civil Protection and Disaster Relief and the Ministry of the Interior, has prepared a Report on Nuclear and Radiation Safety in the Republic of Slovenia for 2000. This is one of the regular forms of reporting on the work of the Administration to the Government and National Assembly of the Republic of Slovenia.

  20. Nuclear and radiation safety in Slovenia. Annual report 2000

    International Nuclear Information System (INIS)

    The Slovenian Nuclear Safety Administration (SNSA), in co-operation with the Health Inspectorate of the Republic of Slovenia, the Administration for Civil Protection and Disaster Relief and the Ministry of the Interior, has prepared a Report on Nuclear and Radiation Safety in the Republic of Slovenia for 2000. This is one of the regular forms of reporting on the work of the Administration to the Government and National Assembly of the Republic of Slovenia. (author)

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

    International Nuclear Information System (INIS)

    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

  2. Report on the Uranium Mine Radiation Safety Course

    International Nuclear Information System (INIS)

    Since 1981 the Canadian Institute for Radiation Safety (CAIRS) has administered a semi-annual course on radiation safety in uranium mines under contract to and in consultation with the Atomic Energy Control Board (AECB). The course is intended primarily for representatives from mining companies, regulatory agencies, unions, and mine and mill workers. By the terms of its contract with the AECB, CAIRS is required to submit a report on each course it conducts. This is the report on the June 1987 course. It lists the course objectives and the timetable, outlines for each lecture, the lecturers' resumes, and the participants. The students' evaluations of the course are included

  3. 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.

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

    Science.gov (United States)

    Walker, J S

    1989-08-01

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

  5. Radiation safety at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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)

  7. Nuclear and radiation safety in Slovenia. Annual report 1997

    International Nuclear Information System (INIS)

    The Slovenian Nuclear Safety Administration (SNSA), in co-operation with the Health Inspectorate of the Republic of Slovenia, the Administration for Civil Protection and Disaster Relief and the Ministry of the Interior, has prepared a Report on Nuclear and Radiation Safety in the Republic of Slovenia for 1997. This is one of the regular forms of reporting on the work of the Administration to the Government and National Assembly of the Republic of Slovenia. Contributions to the report were furthermore prepared by competent authorities in the field of nuclear safety: the Agency for Radwaste Management (ARAO), the Milan Copic Nuclear Training Centre, etc. The report contains 17 chapters. (author)

  8. A bioethical perspective on radiation protection and ''safety''

    International Nuclear Information System (INIS)

    Three problems of major concern to policymakers whose task it is to protect public health by setting standards for ''safe'' radiation management are reviewed. The first problem is to decide if current conceptual tools for assessing basic harms to valued living systems are ethically adequate. The second is how to set safety standards on the basis of informed consent to scientific evidence presented by experts who disagree in interpreting that evidence. The third problem is how to resolve conflicting philosophies about radiation protection. Principles which might serve as guidance in the formulation of social policies for radiation health protection are suggested. (H.K.)

  9. Radiation safety in X-ray diagnostic installations

    International Nuclear Information System (INIS)

    Safety measures to be strictly adhered to in handling X-ray equipment and exposing patients to X-radiation are described in detail. Hazards resulting from ignorance and careless handling are mentioned. Methods of shielding are indicated. (A.K.)

  10. Australian Radiation Protection and Nuclear Safety Regulations 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-11-01

    This document contains statutory rules made under the Australian Radiation and Nuclear Safety Act 1998 defining how specified standards to be observed, practices and procedures to be followed and measures to be taken by controlled persons in relation to activities relating to controlled facilities, as well as in relation to dealings with controlled apparatus or controlled material

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

    Energy Technology Data Exchange (ETDEWEB)

    Sygitowicz, L S

    2008-03-20

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

  12. Radiation Safety Management Guidelines for PET-CT: Focus on Behavior and Environment

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Jin Wook [Cancer Imaging Center, National University Cancer Hospital, Seoul (Korea, Republic of); Han, Eun Ok [Dept. of Radiological Technology, Daegu Health College, Seoul (Korea, Republic of)

    2011-09-15

    Our purpose is to specify behavior and environmental factors aimed at reducing the exposed dosage caused by PET-CT and to develop radiation safety management guidelines adequate for domestic circumstances. We have used a multistep-multimethod as the methodological approach to design and to carry out the research both in quality and quantity, including an analysis on previous studies, professional consultations and a survey. The survey includes responses from 139 practitioners in charged of 109 PET-CTs installed throughout Korea(reported by the Korean Society of Nuclear Medicine, 2010). The research use 156 questions using Cronbach's {alpha} (alpha) coefficients which were: 0.818 for 'the necessity of setting and installing the radiation protective environment'; 0.916 for 'the necessity of radiation protection', 'setting and installing the radiation protective environment'; and 0.885 for 'radiation protection'. The check list, derived from the radiation safety management guidelines focused on behavior and environment, was composed of 20 items for the radiation protective environment: including 5 items for the patient; 4 items for the guardian; 3 items for the radiologist; and 8 items applied to everyone involved; for a total of 26 items for the radiation protective behavior including: 12 items for the patient; 1 item for the guardian, 7 items for the radiologist; and 6 items applied to everyone involved. The specific check list is shown in (Table 5-6). Since our country has no safety management guidelines of its own to reduce the exposed dosage caused by PET-CTs, we believe the guidelines developed through this study means great deal to the field as it is not only appropriate for domestic circumstances, but also contains specific check lists for each target who may be exposed to radiation in regards to behavior and environment.

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

    International Nuclear Information System (INIS)

    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)

  14. Establishment of database for radiation exposure and safety assessment

    International Nuclear Information System (INIS)

    The nuclear electric energy in our country plays a major role for the national industrial development as well as for the secure living of the peoples. It is, however, considered as a socially dreadful elements because of the radiation materials exposed into the environment. In effect, the DB is intended to serve for the reference to the epidemical study upon the low-level radiation exposure involving the nuclear facilities, radio-isotope business enterprises, and the related workers at the radiation sites. In connection with the development of nuclear energy, the low-level radiation, associated with the radioisotope materials exposed into our environment out of nuclear facilities, is believed to possibly raise significant hazardous effects toward human persons. Therefor, it is necessary to take a positive counter measures by means of comprehensive quantitative estimates on its possibilities. In consequence, the low-level radiation effects do not bring about the immediate hazard cases, however, appear to possibly pose the lately caused diseases such as cancer cause, life reduction, and creation of mutation, etc. Therefore, it is intended to set up the social security with the secure safety, by conducting an advanced safety study on the low-level radiation

  15. Safety and Radiation Protection at Swedish Nuclear Power Plants 2007

    International Nuclear Information System (INIS)

    transparent basis for making decisions in safety matters. During the year it has however become apparent that further improvement measures are necessary. The plant has had a relatively large number of operational disturbances during 2007 which have been analysed in order to implement suitable measures. Modernisation projects follow the time schedules which were decided earlier for implementation in order to comply with the regulations. Some measures are already completed, others are underway, and the programme will continue until 2013. SKI is supervising the progress of the modernisation and the improvements to the physical protection of the plants. Forsmark Kraftgrupp AB has applied for permission to increase the thermal power in reactors Forsmark 1 - 3. The government has not as yet granted permission for these power increases. SKI has approved trial operation for Ringhals 1 and Ringhals 3 at the increased power levels during the year. For Ringhals 3 this is the first stage of the planned power increases. Ringhals has also applied to increase the thermal power in Ringhals 4. The government has granted permission for the thermal power increase in Oskarshamn 3. SKI is currently performing a safety review of this application. Oskarshamn have made an application to increase the thermal power in Oskarshamn 2. During 2007 SKI has performed inspections to control how nuclear safeguards are managed by the nuclear power stations. In all 80 inspections have been carried out. Nothing has been found during these inspections to indicate that there are any deficiencies in the nuclear safeguard activities. No serious incidents or accidents have occurred resulting in abnormal radiation exposure of personnel. Radioactive releases from the plants have resulted in calculated doses to the most exposed person in the critical group that are well below the environmental impact goal of 10 microsievert. Forsmark, which in recent years has had recurrent problems with the measurement of airborne

  16. Safety and Radiation Protection at Swedish Nuclear Power Plants 2007

    Energy Technology Data Exchange (ETDEWEB)

    2008-07-01

    transparent basis for making decisions in safety matters. During the year it has however become apparent that further improvement measures are necessary. The plant has had a relatively large number of operational disturbances during 2007 which have been analysed in order to implement suitable measures. Modernisation projects follow the time schedules which were decided earlier for implementation in order to comply with the regulations. Some measures are already completed, others are underway, and the programme will continue until 2013. SKI is supervising the progress of the modernisation and the improvements to the physical protection of the plants. Forsmark Kraftgrupp AB has applied for permission to increase the thermal power in reactors Forsmark 1-3. The government hasn't yet granted permission for these power increases. SKI has approved trial operation for Ringhals 1 and Ringhals 3 at the increased power levels during the year. For Ringhals 3 this is the first stage of the planned power increases. Ringhals has also applied to increase the thermal power in Ringhals 4. The government has granted permission for the thermal power increase in Oskarshamn 3. SKI is currently performing a safety review of this application. Oskarshamn have made an application to increase the thermal power in Oskarshamn 2. During 2007 SKI has performed inspections to control how nuclear safeguards are managed by the nuclear power stations. In all 80 inspections have been carried out. Nothing has been found during these inspections to indicate that there are any deficiencies in the nuclear safeguard activities. No serious incidents or accidents have occurred resulting in abnormal radiation exposure of personnel. Radioactive releases from the plants have resulted in calculated doses to the most exposed person in the critical group that are well below the environmental impact goal of 10 microsievert. Forsmark, which in recent years has had recurrent problems with the measurement of airborne

  17. Radiation Safety and Education in the Applicants of the Final Test for the Expert of Pain Medicine

    OpenAIRE

    Park, Pyong Eun; Park, Jung Min; Kang, Joo Eun; Cho, Jae Hun; Cho, Suk Ju; Kim, Jae Hun; Sim, Woo Seog; Kim, Yong Chul

    2012-01-01

    Background The C-arm fluoroscope is known as the most important equipment in pain interventions. This study was conducted to investigate the completion rate of education on radiation safety, the knowledge of radiation exposure, the use of radiation protection, and so on. Methods Unsigned questionnaires were collected from the 27 pain physicians who applied for the final test to become an expert in pain medicine in 2011. The survey was composed of 12 questions about the position of the hospita...

  18. Recent advances in applied nanoscience for food safety

    Science.gov (United States)

    Ongoing developments in nanotechnology offer potential to transform agriculture in several areas, including food safety, quality, packaging, product traceability, food processing, and bioactive delivery. These nanoscience-based applications utilize the unique properties of materials with a dimension...

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Mahesh, Mahadevappa [Johns Hopkins University School of Medicine, The Russell H. Morgan Department of Radiology and Radiological Science, Baltimore, MD (United States)

    2015-09-15

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

  1. Towards a convention on radiation safety and security

    International Nuclear Information System (INIS)

    An international legally biding undertaking that specifically addresses safety and security of ionizing radiation (or radiation in short) is an overdue necessity. Such an instrument has been requested by the scientific community for a long time. A quarter of a century has elapsed since it was first considered a growing necessity. The time seems to be ripe for legal experts to negotiate a Convention on Radiation Safety and Security. Thee purpose of this paper is to review the developments leading to such a conclusion and to refresh the request. Since their discoveries more that 100 years ago, the phenomena of radioactivity and the radiation emitted by radioactive substances and ad hoc apparatuses (such as x-ray machines and accelerators) have become widely used for human well being. Their use in medicine, for instance, has grown to such an extent as to become the major source of human radiation exposure. While radiation usage is very beneficial for mankind, endeavours involving radiation shall be safe and secure. Although the vast majority of radioactive sources used around the world are managed safely and securely, and bring many benefits to humankind, accidents involving radiation sources have occurred, some with serious —even fatal— consequences. Many of these accidents has been reported by the International Atomic Energy Agency; see for example references (IAEA, 1988, 1996b, 1998b, 2000a,b,c, 2002a,b). Thus, starting around the last decade of the past century, there was growing international concern about radiation sources that for one reason or another were not subject to regulatory control or over which regulatory control had been lost. Historically, the protection of people against radiation and implicitly the safe use of radiation sources have been governed by recommendations from the International Commission on Radiological Protection (ICRP), a professional charity founded in 1928, which over the years has developed, maintained, and elaborated an

  2. Radiation safety in sea transport of radioactive material in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Odano, N. [National Maritime Research Inst., Tokyo (Japan); Yanagi, H. [Nuclear Fuel Transport Co., Ltd., Tokyo (Japan)

    2004-07-01

    Radiation safety for sea transport of radioactive material in Japan has been discussed based on records of the exposed dose of sea transport workers and measured data of dose rate equivalents distribution inboard exclusive radioactive material shipping vessels. Recent surveyed records of the exposed doses of workers who engaged in sea transport operation indicate that exposed doses of transport workers are significantly low. Measured distribution of the exposed dose equivalents inboard those vessels indicates that dose rate equivalents inside those vessels are lower than levels regulated by the transport regulations of Japan. These facts clarify that radiation safety of inboard environment and handling of transport casks in sea transport of radioactive material in Japan are assured.

  3. Educational and experiential effects on radiographers' radiation safety behavior

    International Nuclear Information System (INIS)

    Forty-four radiographers from 11 hospitals in Northern California were observed for radiation safety behaviors in six categories. A multiple regression analysis was performed to determine if there was a significant relationship between the six radiation safety behaviors and the radiographer's age, sex, type of professional training, years since completion of professional training, years of professional practice, time of day, and exposure frequency. The multiple regression analysis showed that there was a significant relationship between use of gonadal shielding and years since completion of professional training, years of professional practice, type of training, and age. The multiple regression analysis also showed that the number of repeated films due to technical error was significantly related to the type of professional training a radiographer received

  4. 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

  5. International harmonization of radiation protection and safety standards. The role of the United Nations system

    International Nuclear Information System (INIS)

    extensive 928-page report, and in 1994 its supplementary 272-page report, to the UNGA. A new UNSCEAR report is expected by the end of 2000. On the other hand, the International Commission on Radiological Protection (ICRP), which in 1990 had revised its standing recommendations, has now issued a number of documents to apply these recommendations in specific situations. In 1991 six organizations - FAO, ILO, NEA/OECD, PAHO, WHO, and IAEA - created a Joint Secretariat coordinated by the International Atomic Energy Organization (IAEA) with the purpose of establishing the International Basic Standards for Protection against Ionizing Radiation and the Safety of Radiation Sources (the so-called BSS). This was the peak of decades of work and marked an unprecedented international co-operation that involved hundreds of experts from the Member States of the sponsoring organizations establishing the BSS. Within this framework, the objective of this paper is to present the significant role that the United Nations system of international organizations could play to achieve a genuine international consensus on radiation protection and safety standards. Not surprisingly, the paper will concentrate on the role and functions of the IAEA. The IAEA, is the only organization in the UN family with specific statutory functions, duties and responsibilities in the establishing international standards for radiation protection and safety. By analysing the functions and roles of UNSCEAR and the IAEA, it is clear how the UN policy on this matter has been built up and where it now stands. It should be emphasized that both UNSCEAR and the IAEA are not free 'think tanks'. They are governmental organizations. Their policies therefore reflect those of their constituencies, namely their Member States. Thus, the paper summarizes the status of UN policies on the health effects of radiation exposure, particularly on the controversial issue of the effects of low level radiation, as well as on the approach for

  6. Radiation Safety Act 1975 - No 44 of 1975

    International Nuclear Information System (INIS)

    This Act regulates the use of radioactive substances and irradiating apparatus, including particle accelerators as well as certain specified electronic products. The Act lays down a licensing and registration system for such substances and apparatus; it sets up a Radiological Council to administer the Act and to advise the Minister responsible for public health on matters of radiation safety. The radioactive Substances Act 1954 and the Amending Acts of 1960 and 1964 are repealed. (NEA)

  7. Developing the radiation protection safety culture in the UK

    International Nuclear Information System (INIS)

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

  8. Applying the Extended Parallel Process Model to workplace safety messages.

    Science.gov (United States)

    Basil, Michael; Basil, Debra; Deshpande, Sameer; Lavack, Anne M

    2013-01-01

    The extended parallel process model (EPPM) proposes fear appeals are most effective when they combine threat and efficacy. Three studies conducted in the workplace safety context examine the use of various EPPM factors and their effects, especially multiplicative effects. Study 1 was a content analysis examining the use of EPPM factors in actual workplace safety messages. Study 2 experimentally tested these messages with 212 construction trainees. Study 3 replicated this experiment with 1,802 men across four English-speaking countries-Australia, Canada, the United Kingdom, and the United States. The results of these three studies (1) demonstrate the inconsistent use of EPPM components in real-world work safety communications, (2) support the necessity of self-efficacy for the effective use of threat, (3) show a multiplicative effect where communication effectiveness is maximized when all model components are present (severity, susceptibility, and efficacy), and (4) validate these findings with gory appeals across four English-speaking countries.

  9. Radiation protection training of radiation safety officers in Finland in 2008

    International Nuclear Information System (INIS)

    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

  10. Statistical analysis applied to safety culture self-assessment

    International Nuclear Information System (INIS)

    Interviews and opinion surveys are instruments used to assess the safety culture in an organization as part of the Safety Culture Enhancement Programme. Specific statistical tools are used to analyse the survey results. This paper presents an example of an opinion survey with the corresponding application of the statistical analysis and the conclusions obtained. Survey validation, Frequency statistics, Kolmogorov-Smirnov non-parametric test, Student (T-test) and ANOVA means comparison tests and LSD post-hoc multiple comparison test, are discussed. (author)

  11. Applying radiation protection issues to hospitals radiological emergency preparedness

    International Nuclear Information System (INIS)

    Updating Hospitals emergency preparedness to Radiological Emergency situations was an opportunity to reevaluate key issues: What is the main threat - Nuclear or Radiological? RDD or industrial? As a result of such a discussion-what kind of radiation monitors to select? Should they be similar to those other emergency organizations use? What Personal Protective Equipment (PPE) level to decide on? Who are hospital emergency team members and how deep is there radiation protection knowledge? How and where to train them? Are drills needed? How often so normal hospital activity is not disturbed? What kind of manuals to prepare? This paper describes the process that led to the change of policy from preparedness to nuclear accidents only, to all kind of radiological emergencies with an emphasis on radiological terror. Supply of new radiation and contamination detection equipment took place, same as the one that other emergency teams have. A new and simple level C PPE applied. Training set different team members on same level. Several manuals prepared: How to prepare Hospital to contaminated casualties in order to minimize normal routine - in case there is an information on contaminated casualties on the way and in case it was discovered after they arrived, how to treat a contaminated casualty, to decontaminate him or not? How to decide that a casualty is contaminated or not? What to do with casualties belongings? What to do with contaminated equipment? How to exit a contaminated zone? How to set hospital back to ordinary work? etc. (author)

  12. 24 CFR 1005.111 - What safety and quality standards apply?

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 4 2010-04-01 2010-04-01 false What safety and quality standards... URBAN DEVELOPMENT LOAN GUARANTEES FOR INDIAN HOUSING § 1005.111 What safety and quality standards apply? (a) Loans guaranteed under section 184 must be for dwelling units which meet the safety and...

  13. Safety and radiation protection in Indian nuclear power plants

    International Nuclear Information System (INIS)

    Full text: Nuclear energy, an important option for electricity generation is environment friendly, technologically proven, economically competitive and associated with the advantages of energy security and diversity. At present, India has an installed nuclear power generation capacity of 4120 M We with 6 more reactors are under construction/ commissioning at 4 sites. Nuclear power program, in India, as of now is primarily based on pressurized heavy water technology and these reactors are designed with safety features, such as, independent and diverse shut down systems, emergency core cooling system, double containment; pressure suppression pool etc. The principles of redundancy, diversity, fail-safe and passive systems are used in the design. The fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation. In this regard the prime responsibility for safety rests with the organization responsible for facilities and activities that give rise to radiation risks and is achieved by establishing and maintaining the necessary competence, providing adequate training and information, establishing procedures and arrangements to maintain safety under all conditions; verifying appropriate design and the adequate quality of facilities and activities and of their associated equipment; ensuring the safe control of all radioactive material that is used, produced, stored or transported, ensuring the safe control of all radioactive waste that is generated. 'Radiation Protection for Nuclear Facilities', issued by Atomic Energy Regulatory Board (the regulatory authority for NPPs in India) is the basic document for following radiation protection procedures in NPPs. Approved work procedures for all radiation jobs exist. Pre job briefing and post job analysis are carried out. Radiation protection is integrated with plant operation. Radiation levels indicate the performance of several systems. Several measures are adopted in design and

  14. Radiation safety analysis of the ISS bone densitometer

    Science.gov (United States)

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

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

  15. Industrial Safety and Applied Health Physics Division, annual report for 1982

    Energy Technology Data Exchange (ETDEWEB)

    1983-12-01

    Activities during the past year are summarized for the Health Physics Department, the Environmental Management Department, and the Safety Department. The Health Physics Department conducts radiation and safety surveys, provides personnel monitoring services for both external and internal radiation, and procures, services, and calibrates appropriate portable and stationary health physics instruments. The Environmental Management Department insures that the activities of the various organizations within ORNL are carried out in a responsible and safe manner. This responsibility involves the measurement, field monitoring, and evaluation of the amounts of radionuclides and hazardous materials released to the environment and the control of hazardous materials used within ORNL. The department also collaborates in the design of ORNL Facilities to help reduce the level of materials released to the environment. The Safety Department is responsible for maintaining a high level of staff safety. This includes aspects of both operational and industrial safety and also coordinates the activities of the Director's Safety Review Committee. (ACR)

  16. Industrial Safety and Applied Health Physics Division, annual report for 1982

    International Nuclear Information System (INIS)

    Activities during the past year are summarized for the Health Physics Department, the Environmental Management Department, and the Safety Department. The Health Physics Department conducts radiation and safety surveys, provides personnel monitoring services for both external and internal radiation, and procures, services, and calibrates appropriate portable and stationary health physics instruments. The Environmental Management Department insures that the activities of the various organizations within ORNL are carried out in a responsible and safe manner. This responsibility involves the measurement, field monitoring, and evaluation of the amounts of radionuclides and hazardous materials released to the environment and the control of hazardous materials used within ORNL. The department also collaborates in the design of ORNL Facilities to help reduce the level of materials released to the environment. The Safety Department is responsible for maintaining a high level of staff safety. This includes aspects of both operational and industrial safety and also coordinates the activities of the Director's Safety Review Committee

  17. Radiation safety and protection in US dental hygiene programs

    International Nuclear Information System (INIS)

    A survey of radiation safety and protection measures used by programs teaching dental hygiene indicated some areas for concern. No barriers or radiation shieldings were used between operator and patient in four programs. Radiation monitoring devices were not worn by faculty operators in 16% of the programs. Fewer than half of the programs used thyroid shields for patients on a routine basis. Insufficient filtration for the kilovolt peak employed was used by 14% of the programs, and for 19% more the filtration was unknown or unspecified. Three programs used closed cones. Rectangular collimation was not used at all by 63% of the programs, and only 20% used E speed film routinely. Quality assurance for equipment maintenance and for film processing were in place at only 54% and 49% of the programs, respectively

  18. Relationship between knowledge, attitude, behavior, and self-efficacy on the radiation safety on dental hygienist

    Energy Technology Data Exchange (ETDEWEB)

    Han, Eun Ok; Jun, Sung Hee [Daegu Health College, Daegu (Korea, Republic of)

    2008-11-15

    The objective of this study is to draw an educational plant for reducing the probability of troubles caused by radiation for dental hygienists who are the major applicants of radiation equipments used in dental offices. This study investigated the knowledge and self-efficacy, which is the major variable that affects the attitude and behavior, on the radiation safety that is an educational approach. Also, this study obtained following results from a survey for 25 days from June 15, 2008 that was applied for 225 dental hygienists worked at dental offices and clinics in the area of Youngnam in order to verify the relationship between such variables. The average scores for the knowledge, attitude, and behavior were 54.28±16.33, 87.93±9.75, and 59.85±14.76, respectively. Also, the average score of the self-efficacy was 72.88±8.60. In the knowledge level for the radiation safety, ‘a case that prepares personal dosimeters’, ‘a case that establishes protection facilities’, ‘a case that presents 6⁓10 dental hygienists’, ‘a case that presents radiological technologists’, and ‘a case that is a general hospital’ represented high values. In the attitude level for the radiation safety, ‘a case who is a married person’, ‘a case that prepares personal dosimeters’, and ‘a case that is a general hospital’ showed high values. In the behavior level for the radiation safety, ‘a case that shows a career in dental hygienist or radiographic for 6⁓10 years’, ‘a case that attends radiation safety education’, ‘a case that establishes protection facilities’ showed high values. Also, in the self-efficacy level, ‘a case that who has a high education level more than graduate school education’ and ‘a case that establishes protection facilities’ represented high values. In the relationship between the knowledge, attitude, behavior, and self-efficacy for the radiation safety, it showed statistically significant differences in this

  19. Safety Training: Ergonomics - Applying ergonomic principles in the workplace

    CERN Multimedia

    Isabelle Cusato

    2010-01-01

        We propose a half day awareness session on the hazards posed by a poor posture while working on a screen (back pain, eyestrain, sore wrists…) and best practices to address them. The next sessions will be held on 18 November 2010 (morning session in French and afternoon session in English). The registration via the Safety Training catalogue is mandatory. Places will be allocated in order of receipt. For any further information, please contact Isabelle Cusato, 73811.  

  20. Applying the ionising radiation regulations to radon in the UK workplace

    International Nuclear Information System (INIS)

    As a response to the identification of a health risk from workplace radon in the UK, the Ionising Radiations Regulations include the protection of workers from excessive levels of radon. Employers are required to make risk assessments, and the interpretation of the Health and Safety Executive is that the regulations apply to workplace premises in locations already designated as Radon Affected Areas for domestic purposes, with the difference that in workplaces, it is the maximum winter radon concentration rather than the annual average which is the parameter of interest. This paper discusses the rationale behind the current regulatory environment, outlines the role and duties of Accredited Radiation Protection Advisers and summarises the strategies necessary to conform to the regulations. (authors)

  1. 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.

  2. A Study on Enhancement of Understanding of Radiation and Safety Management

    International Nuclear Information System (INIS)

    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

  3. Guidelines for radiation safety in interventional cardiology (JCS 2006)

    International Nuclear Information System (INIS)

    The guidelines are made for physicians in cardiovascular field who may be unfamiliar to radiation safety, to understand and know it easily. The introductory chapter describes the basic knowledge for management of radiation exposure and clinical feature of radiation-induced dermal damages like classification, clinical progress and case presentation. Following chapter is itemized, explained in a style of Q and A, and contains sections of; the fundamental knowledge's of radiation exposure management and of radiation skin damage, informed consent and measures for excessive exposure and skin damage crisis, factors influencing the exposure dose, contrivances to reduce the dose in patients, additional factors affecting the crisis of skin damage, contrivances to reduce the dose in medical personnel exposure, management of imaging instruments, methods to measure the exposure dose in patients, intervention in vessels other than the coronary artery, electro-physiological examinations and treatments, nuclear medical diagnoses, CT examinations, diagnosis and treatment of pregnant women, and present states in other countries. (T.I.)

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

    Directory of Open Access Journals (Sweden)

    Salih Sinan Gültekin

    2013-12-01

    Full Text Available Objective: Most of the radiopharmaceuticals used in nuclear medicine are excreted via the urinary system. This study evaluated the importance of a reduction in bladder radioactivity for radiation safety. Methods: The study group of 135 patients underwent several organ scintigraphies [40/135; thyroid scintigraphy (TS, 30/135; whole body bone scintigraphy (WBS, 35/135; myocardial perfusion scintigraphy (MPS and 30/135; renal scintigraphy (RS] by a technologist within 1 month. In full and empty conditions, static bladder images and external dose rate measurements at 0.25, 0.50, 1, 1.5 and 2 m distances were obtained and decline ratios were calculated from these two data sets. Results: External radiation dose rates were highest in patients undergoing MPS. External dose rates at 0.25 m distance for TS, TKS, MPS and BS were measured to be 56, 106, 191 and 72 μSv h-1 for full bladder and 29, 55, 103 and 37 μSv h-1 for empty bladder, respectively. For TS, WBS, MPS and RS, respectively, average decline ratios were calculated to be 52%, 55%, 53% and 54% in the scintigraphic assessment and 49%, 51%, 49%, 50% and 50% in the assessment with Geiger counter. Conclusion: Decline in bladder radioactivity is important in terms of radiation safety. Patients should be encouraged for micturition after each scintigraphic test. Spending time together with radioactive patients at distances less than 1 m should be kept to a minimum where possible.

  5. Radiation safety, protection and recommendations in dentistry - a review

    International Nuclear Information System (INIS)

    Radiation is the transmission of energy through space and matter. Diagnostic radiology uses ionizing radiations which have sufficient energy to ionize atoms or molecules in biological and other systems. X-rays used in diagnostic radiology are a potent mutagenic agent, capable of inducing both gene mutations and chromosomal aberrations. X-rays are extensively used in medical and dental practice for the purpose of diagnosis and treatment. X-rays provide useful information and aid in diagnosis but at the same time they also have the potential to cause harmful effects. In dentistry X-rays are used mainly for diagnosis. Radiation in doses required for dentistry may not present any major risks, however these small doses are not necessarily risk free. Hence, no exposure to X-rays can be considered completely free of risk, so the use of radiation by dentists is accompanied by a responsibility to ensure appropriate protection. Several radiation safety measures have been recommended and advocated to reduce harmful effects. Dental professionals are the only practitioners who perform radiographical examination of their patients themselves. Although the exposure used in dentistry is low every effort should be made to reduce radiation in order to prevent the accumulated dose to the dentist in their lifetime. The dose reduction can be achieved in three main steps. They are decision making, optimising radiologic procedures and patient protection. The potential for undesirable effects must be balanced against the benefits obtained from radiographs. Therefore, the aim of the paper is to review important parameters that must be taken into consideration in the clinical set up to reduce radiation exposure to patients and dental personnel. (author)

  6. Progress report: nuclear safety and radiation protection in 2006

    International Nuclear Information System (INIS)

    For the French Nuclear Safety Authority (Asn), the year 2006 was marked by two important nuclear laws being passed, one of which brought about a major change in its status. The year was a relatively satisfactory one with regard to nuclear safety, although the picture was more contrasted concerning radiation protection: in this area, more particularly in the medical field, the overall impression of good progress is offset by the declaration of a number of radiotherapy accidents. Given the benefits expected from radiotherapy treatment by the patient suffering from cancer, the conditions in which this activity is carried out are a subject of major concern for Asn, in the light of the serious risks linked to patient over-exposure. ( some important points as follows: the law on transparency and security in the nuclear field, the law on sustainable management of radioactive materials and waste, Asn: an independent administrative authority, EPR reactor project safety, I.R.R.S.: an international audit of Asn in 2006, harmonization of nuclear safety, cancer radiotherapy, improved information of the public after the T.S.N. law, taking account of organisational and human factors). (N.C.)

  7. Report on nuclear and radiation safety in Slovenia in 2001

    International Nuclear Information System (INIS)

    The Slovenian Nuclear Safety Administration (SNSA) has prepared a Report on Nuclear and Radiation Safety in Slovenia for 2001 as a regular form of reporting to the citizens of the Republic of Slovenia on the activities related to the nuclear fuel cycle and the use of the ionising sources. The report has been prepared in collaboration with the Health Inspectorate of the Republic of Slovenia (HIRS), the Administration for Civil Protection and Disaster Relief (ACPDR), the Pool for Assurance and Reinsurance of Liability for Nuclear Damage and the Pool for Decommissioning of the NPP Krsko and for the Radwaste Disposal from the NPP Krsko. The reports of the Agency for Radioactive Waste Management (ARAO), the Institute of Oncology, the Department of Nuclear Medicine of the Medical Centre Ljubljana and the technical support organisations are also included. The SNSA made no crucial modifications to the reports of the above mentioned institutions. The modifications were made just facilitate a reading of the reports.

  8. Nuclear and radiation safety in Slovenia. Annual report 2001

    International Nuclear Information System (INIS)

    The Slovenian Nuclear Safety Administration (SNSA) has prepared a Report on Nuclear and Radiation Safety in Slovenia for 2001 as a regular form of reporting to the citizens of the Republic of Slovenia on the activities related to the nuclear fuel cycle and the use of the ionising sources. The report has been prepared in collaboration with the Health Inspectorate of the Republic of Slovenia (HIRS), the Administration for Civil Protection and Disaster Relief (ACPDR), the Pool for Assurance and Reinsurance of Liability for Nuclear Damage and the Pool for Decommissioning of the NPP Krsko and for the Radwaste Disposal from the NPP Krsko. The reports of the Agency for Radioactive Waste Management (ARAO), the Institute of Oncology, the Department of Nuclear Medicine of the Medical Centre Ljubljana and the technical support organisations are also included. The SNSA made no crucial modifications to the reports of the above mentioned institutions. The modifications were made just facilitate a reading of the reports. (author)

  9. A study on radiation shielding and safety analysis for a synchrotron radiation beamline

    Energy Technology Data Exchange (ETDEWEB)

    Asano, Yoshihiro [Japan Atomic Energy Research Inst., Kansai Research Establishment, Synchrotron Radiation Research Center, Mikazuhi, Hyogo (Japan)

    2001-03-01

    Methods of shielding design and safety analysis are presented for a beam-line of synchrotron radiation. This paper consists of the shielding and safety study of synchrotron radiation with extremely intense and low energy photon below several hundreds keV, and the study for the behavior of remarkable high-energy photons up to 8 GeV, which can creep into beam-lines. A new shielding design code, STAC8 was developed to estimate the leakage dose outside the beam line hutch (an enclosure of the beam, optical elements or experimental instruments) easily and quickly with satisfactory accuracy. The code can calculate consistently from sources of synchrotron radiation to dose equivalent outside hutches with considering the build up effect and polarization effect. Validity of the code was verified by comparing its calculations with those of Monte Carlo simulations and measurement results of the doses inside the hutch of the BL14C of Photon Factory in the High Energy Accelerator Research Organization (KEK), showing good agreements. The shielding design calculations using STAC8 were carried out to apply to the practical beam-lines with the considering polarization effect and clarified the characteristics of the typical beam-line of the third generation synchrotron radiation facility, SPring-8. In addition, the shielding calculations were compared with the measurement outside the shield wall of the bending magnet beam-line of SPring-8, and showed fairly good agreement. The new shielding problems, which have usually been neglected in shielding designs for existing synchrotron radiation facilities, are clarified through the analysis of the beam-line shielding of SPring-8. The synchrotron radiation from the SPring-8 has such extremely high-intensity involving high energy photons that the scattered synchrotron radiation from the concrete floor of the hutch, the ground shine, causes a seriously high dose. The method of effective shielding is presented. For the estimation of the gas

  10. Radiation protection in Portugal: health, safety and legal aspects

    International Nuclear Information System (INIS)

    The paper describes the basic legal and technical principles governing radiation protection in Portugal. The methods used in the medical surveillance of occupationally exposed persons (especially in the assessment of biological effects) are described and the results of recent studies carried out with a view to improving biological dosimetry techniques are reported. An account is also given of dosimetry at nuclear centres in mines, at research establishments, in industry and in hospitals and private clinics, the accumulated doses being examined in the light of international recommendations relating to radiation protection. Statistical data on the granting of licences to different kinds of establishment are considered from the radiation safety point of view by the authors, who also describe the methods used for controlling waste from nuclear facilities and the measures taken in such special situations as the visit of a nuclear-powered ship to a Portuguese port or the disposal of radioactive waste into the Atlantic Ocean. A brief account is given of recent efforts to check on radioactive pollution (especially the contamination of milk by 90Sr). Lastly, the criteria followed in licensing and controlling Portuguese establishments which work with radioactive substances or other radiation sources are reviewed and, on the basis of experience, a critical appraisal is made of the application of the fundamental technical and legal principles, which presupposes the necessary co-operation between license-issuing authority, facility operator and staff

  11. Radiological protection for medical exposure to ionizing radiation. Safety guide

    International Nuclear Information System (INIS)

    radiotherapy owing to an ageing population. In addition, further growth in medical radiology can be expected in developing States, where at present facilities and services are often lacking. The risks associated with these expected increases in medical exposures should be outweighed by the benefits. For the purposes of radiation protection, ionizing radiation exposures are divided into three types: Medical exposure, which is mainly the exposure of patients as part of their diagnosis or treatment (see below); Occupational exposure, which is the exposure of workers incurred in the course of their work, with some specific exclusions; and Public exposure, which comprises all other exposures of members of the public that are susceptible to human control. Medical exposure is defined in the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS, the Standards) as: 'Exposure incurred by patients as part of their own medical or dental diagnosis or treatment; by persons, other than those occupationally exposed, knowingly while voluntarily helping in the support and comfort of patients; and by volunteers in a programme of biomedical research involving their exposure.' This Safety Guide covers all of the medical exposures defined above, with emphasis on the radiological protection of patients, but does not cover exposures of workers or the public derived from the application of medical radiation sources. Guidance relating to these exposures can be found in the Safety Guide on Occupational Radiation Protection. In addition to the IAEA, several intergovernmental and international organizations, among them the European Commission, the International Commission on Radiological Protection (ICRP), the Pan American Health Organization (PAHO) and the World Health Organization (WHO), have already published numerous recommendations, guides and codes of practice relevant to this subject area. National authorities should therefore

  12. Industrial safety and applied health physics. Annual report, 1979

    International Nuclear Information System (INIS)

    In connection with personnel monitoring, there were no external or internal exposures to personnel which exceeded the standards for radiation protection as defined in DOE Manual Chapter 0524. Only 55 employees received whole-body dose equivalent of one rem or greater. The highest whole-body dose equivalent to an employee was 2.8 rem. The highest internal exposure was less than one-half of a maximum permissible dose for any calendar quarter. During 1979, 57 portable health physics instruments were added to the inventory and 75 retired. The total number in service on January 1, 1979, was 977. With regards to environmental monitoring, there were no releases of gaseous waste from the Laboratory which were of a level that required an incident report to DOE. There were no releases of liquid radioactive waste from the Laboratory which were of a level that required an incident report to DOE. Soil samples were collected at all perimeter and remote monitoring stations and analyzed for eleven radionuclides including plutonium and uranium. Plutonium-239 content ranged from 0.01 to 0.06 pCi/g, and the uranium-235 content ranged from 0.01 to 0.05 pCi/g. Grass samples were collected at all perimeter and remote monitoring stations and analyzed for twelve radionuclides including plutonium and uranium. Plutonium-239 content ranged from 0.001 to 0.010 pCi/g, and uranium-235 content ranged from 0.001 to 0.010 pCi/g. Two radiation incidents involving radioactive materials were recorded during 1979. This compares with 14 incidents in 1978

  13. Optimization of measures for radiation safety and social security provision during man-caused radioactive contamination of large areas

    International Nuclear Information System (INIS)

    The paper describes optimization of measures undertaken to overcome effects of the large-scale radiation impact on the ground and population. It generalizes structural and content principles for developing target programs as a proven system of measures reducing the extent of such effects. Authors present a sample set of interdependent measures for provision of radiation safety and social security as applied to the Semipalatinsk Test Site and its affected areas. (author)

  14. Providing current radiation safety according to new version of 'Ukrytie' object regulation

    International Nuclear Information System (INIS)

    Main provisions are given of the 'Ukryttia' object's Regulation related to provision of radiation safety during the object's operation. The safety is provided due to the realization by the object's personnel of functions of global monitoring of current radiation conditions, as well as of the measures of operative or preventive suppression of radiation abnormalities sources

  15. Qualified Presumption of Safety (QPS) is a generic risk assessment approach applied by the European Food Safety Authority (EFSA)

    DEFF Research Database (Denmark)

    Leuschner, R. G. K.; Robinson, T. P.; Hugas, M.;

    2010-01-01

    Qualified Presumption of Safety (QPS) is a generic risk assessment approach applied by the European Food Safety Authority (EFSA) to notified biological agents aiming at simplifying risk assessments across different scientific Panels and Units. The aim of this review is to outline the implementation...... and value of the QPS assessment for EFSA and to explain its principles such as the unambiguous identity of a taxonomic unit, the body of knowledge including potential safety concerns and how these considerations lead to a list of biological agents recommended for QPS which EFSA keeps updated through...

  16. Radiation safety management in health care - The application of Quality Function Deployment

    International Nuclear Information System (INIS)

    The paper presents a study of the potential for applying the Quality Function Deployment (QFD) method to the analysis of the framework for safety management contained in the Ionising Radiation (Medical Exposure) Regulations (IRMER) of 2000. The QFD method has been successfully applied to many industrial and manufacturing processes in order to ensure that quality is built into products at the outset rather than tested for after their production. In this context, the term quality is used to describe the degree to which the needs and requirements of the customer are fulfilled. More frequently, now, the QFD approach is being applied to health care in order to engineer clinical processes that can best fulfil the needs of the patient. In the case of diagnostic radiology, safety management must not only be concerned with radiation protection but, more importantly, with the accuracy and consistency of any diagnostic outcome. Both are important patient needs. A first stage analysis of IRMER 2000 is presented that assesses how patients' needs are expressed by the individual IRMER components of justification, optimisation, clinical audit, expert advice, equipment and training. The analysis involved a QFD assessment by four radiation protection experts with over 100 man-years of experience. A second stage analysis assesses how the individual IRMER components have been engineered into a safety management framework through specific requirements embodied in IRMER 2000. The results of this assessment are discussed in terms of clinical, human, operational management and equipment related aspects of the radiological process. This study highlights how the QFD approach may be applied to engineer specific aspects of radiological practice that play a key role in ensuring that patients' needs are fully met. As an example, clinical audit requirements are analysed by means of the QFD method to indicate the design requirements of information and knowledge based systems that can provide the

  17. Radiation Safety System for SPIDER Neutral Beam Accelerator

    Science.gov (United States)

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

    2011-12-01

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

  18. Radiation Safety System for SPIDER Neutral Beam Accelerator

    Energy Technology Data Exchange (ETDEWEB)

    Sandri, S.; Poggi, C. [ENEA, Radiation Protection Institute, IRP-FUAC, Frascati (Italy); Coniglio, A. [Medical Physics Department, S. Giovanni Calibita Hospital, Fatebenefratelli, Isola Tiberina, Roma (Italy); D' Arienzo, M. [ENEA, Ionizing Radiation Metrology National Institute, METR, Casaccia, Rome (Italy)

    2011-12-13

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

  19. Food Safety Detection Methods Applied to National Special Rectification of Product Quality and Food Safety

    Institute of Scientific and Technical Information of China (English)

    2007-01-01

    @@ Afour-month period of national special rectification for product quality and food safety officially started on August 25, and was focused on eight fields, including those of agricultural products and processed foods.

  20. Innovative approach to training radiation safety regulatory professionals

    International Nuclear Information System (INIS)

    Full text: The supply of human resources required to adequately manage a radiation safety regulatory program has diminished in the last five years. Competing professional opportunities and a reduction in the number of health physics secondary schools have made it necessary to look at alternative methods of training. There are limited educational programs in the US that prepare our professionals for careers in the Radiation Regulatory Programs. The state of Florida's radiation control program embraced a new methodology using a combination of didactic and work experience using qualification journals, subject matter experts, and formalized training to develop a qualified pool of employees to perform the regulatory functions and emergency response requirements of a state radiation control program. This program uses a task-based approach to identify training needs and draws upon current staff to develop and implement the training. This has led to a task-oriented staff capable of responding to basic regulatory and emergency response activities within one year of employment. Florida's program lends itself to other states or countries with limited resources that have experienced staff attrition due to retirement or competing employment opportunities. Information on establishing a 'task-based' pool of employees that can perform basic regulatory functions and emergency response after one year of employment will be described. Initial task analysis of core functions and methodology is used to determine the appropriate training methodology for these functions. Instructions will be provided on the methodology used to 'mentor' new employees and then incorporate the new employees into the established core functions and be a useful employee at the completion of the first year of employment. New training philosophy and regime may be useful in assisting in the development of programs in countries and states with limited resources for training radiation protection personnel. (author)

  1. Applying systems thinking to law enforcement safety: recommendation for a comprehensive safety management framework

    OpenAIRE

    DeBoard, Maggie A.

    2015-01-01

    Each year, approximately 100,000 police officers experience work-related occupational injuries, and more than 100 are killed on the job, in training accidents, routine operations, and emergency response. Many of these injuries and deaths are considered preventable. Although the law enforcement profession has recently begun to place an emphasis on safety, with the goal of reducing injuries and fatalities, no systematic or comprehensive approach to safety management exists to oversee and coordi...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-12-01

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

  3. The system of radiation protection applied in Czechoslovakia

    International Nuclear Information System (INIS)

    The concept of the radiation protection system (RPS) that has been gradually set up in Czechoslovakia was based on the Recommendations of the International Commission on Radiological Protection. A decree defines the responsibility, as well as more detailed obligations of organizations using radiation sources, as regards the protection of workers as well as the public, and includes the obligation to ensure an effective monitoring of radiation situations and of doses to persons. Expert supervision of adherence to the radiation protection regulations is carried out by the Hygiene Service, a public health inspection service whose activities in radiation protection are set up at the regional and central level. In each region there is a Radiation Hygiene Department with qualified personnel and appropriate instrumentation for the evaluation of exposure situations which may occur in the region. The departments supervise all workplaces using radiation sources, prepare binding recommendations to the regional health offices regarding the design of laboratories, licenses for the use of radiation sources, and approval for the start or termination of a practice. Central components of the structure directing the RPS in the country are the chief health officers of Bohemia and Slovakia and their expert bases - the Radiation Hygiene Centres at the Institutes for Hygiene and Epidemiology in both Republics. Apart from preparation or radiation protection standards and regulations, guidance as to methods and quality assurance for the work of regional Departments, these expert bases play a co-ordinating role in the system of handling radiation accidents and providing medical assistance to overexposed people. The Radiation Hygiene Centre in Prague acts as a centre for the radiation monitoring network in cases of nuclear accidents, in which the regional stations, nuclear power plants, research institutes and other bodies participate. A system of technical services in radiation protection

  4. Proceedings of the 2nd annual meeting of Japanese Society of Radiation Safety Management 2003 Tsukuba

    International Nuclear Information System (INIS)

    This is the program and the proceedings of the 2nd annual meeting of Japanese Society of Radiation Safety Management held from December 3rd through the 5th of 2003. The sessions held were: (1) Research on Low-level Waste, (2) Topics related to Detector, Measurement, and Instrument, (3) Dose Level and Imaging Plate, (4) Radiation, (5) Safety Education and Safety Evaluation. The poster sessions held were: (1) Safety Education, Safety Evaluation, Shielding, and so on, (2) Control System and Control Technology, (3) Detector and Radiation Measurement, (4) Topics Related to Imaging Plate, (5) Environment and Radiation Measurement, and (6) Radiation Control. Symposia held were: (1) 'Regarding Basic Concept to Incorporate International Exemption Level in Regulation' as the keynote lecture and (2) 'Regarding Correspondence Associated with Legal Revision and Radiation Safety Regulation'. Regarding these topics, after the explanation from each area, panel discussions were held. (S.K.)

  5. Educational effect for the attendance frequency of radiation safety training course and using radioisotope

    International Nuclear Information System (INIS)

    Radiation safety training course has been started on March, 2001 by Radioisotope Research Center, University of Tokushima. And the RI Center has also given re-training course for three years from 2001 to 2003. In the recent courses, a radiation worker's knowledge and recognition about Radiation Safety Handling was investigated, relating with the attendance frequency of those courses. It was found that the basic radiation safety behavior such as putting on monitoring badge, lab coat still was not understood for some persons. On the other hand, the RI center's radiation safety training course gave a correct knowledge and recognition on the radiation safety for most of radiation workers. Furthermore, the times of the attendance improved about that recognition. (author)

  6. Proceedings of the Eighth Scientific Presentation on Environment and Radiation Safety

    International Nuclear Information System (INIS)

    The eight of proceeding scientific meeting environmental and radiation safety are research activity report have been presented in August 23-24,2000. There are 33 articles that presented in two groups A : 16 articles about (biomedical and environmental safety) ; B : 17 articles about (dosimetry; standardization and radiation protection) The porpose of the preceeding be able to reference research activity for Development Health and Personnel Safety, Dosimetry Calibration Nuclear Medicine, Boimedical and in particular for Radiation Monitoring. There are 33 articles indexed individually

  7. A conceptual framework for road safety and mobility applied to cycling safety.

    Science.gov (United States)

    Schepers, Paul; Hagenzieker, Marjan; Methorst, Rob; van Wee, Bert; Wegman, Fred

    2014-01-01

    Scientific literature lacks a model which combines exposure to risk, risk, and the relationship between them. This paper presents a conceptual road safety framework comprising mutually interacting factors for exposure to risk resulting from travel behaviour (volumes, modal split, and distribution of traffic over time and space) and for risk (crash and injury risk). The framework's three determinants for travel behaviour are locations of activities; resistances (generalized transport costs); needs, opportunities, and abilities. Crash and injury risks are modelled by the three 'safety pillars': infrastructure, road users and the vehicles they use. Creating a link in the framework between risk and exposure is important because of the 'non-linear relationship' between them, i.e. risk tends to decrease as exposure increases. Furthermore, 'perceived' risk (a type of travel resistance) plays a role in mode choice, i.e. the perception that a certain type of vehicle is unsafe can be a deterrent to its use. This paper uses theories to explain how the elements in the model interact. Cycling is an area where governments typically have goals for both mobility and safety. To exemplify application of the model, the paper uses the framework to link research on cycling (safety) to land use and infrastructure. The model's value lies in its ability to identify potential consequences of measures and policies for both exposure and risk. This is important from a scientific perspective and for policy makers who often have objectives for both mobility and safety.

  8. Proceedings of the 8th annual meeting of Japanese Society of Radiation Safety Management 2009 Nagasaki

    International Nuclear Information System (INIS)

    This is the program and the proceedings of the 8th annual meeting of Japanese Society of Radiation Safety Management held from December 2nd through the 4th of 2009. The sessions held were: (1) Exposure Reduction and Dose Level Evaluation/ Shielding Design 1 and 2, (2) Standardization Activities regarding Radiation Protection, (3) Emission and Drainage Control/Contamination Inspection/Waste Handling and Clearance, (4) Radiation Measurement 1 and 2, (5) Education Method/Radiation and Utilization of Radioactive Isotopes, and (6) Safety Control of Radiation Source. Two keynote lectures held were: (1) 'Acknowledgment of Radiation Risk' and 'Trend in Radiation Safety Administration'. The topic of one international symposium held was 'International Strategy for Radiation Risk Control'. One special session held was 'Toward Standardization of Safety Handling Law of Radioactive Iodine' by the ad hoc committee. Also, 47 poster sessions were held. (S.K.)

  9. Application of SSNTD for maintenance of radiation and nuclear safety of the Sarcophagus

    International Nuclear Information System (INIS)

    Object 'Shelter' (known world-wide as the Sarcophagus) is a source of very high radiological and nuclear hazard. Transfer of the Sarcophagus into an ecologically safe site is a task not only for Ukraine but also for the world community. A composite approach to maintenance of radiation and nuclear safety of the Sarcophagus applying spectrometric methods using solid state nuclear track detectors (SSNTD) is suggested in this paper. The aspects are: (1) monitoring of transuranium element inhalation intake to a human body of nuclear workers; (2) neutron flux evaluation in some premises of the Sarcophagus; (3) fuel hot particle detection in air of working zones; (4) radon and thoron simultaneous measurements

  10. A conceptual framework for road safety and mobility applied to cycling safety.

    NARCIS (Netherlands)

    Schepers, P. Hagenzieker, M. Methorst, R. Wee, B. van & Wegman, F.C.M.

    2013-01-01

    This paper presents a conceptual road safety framework comprising factors for risk (crash and injury risk), and for exposure to risk resulting from travel behaviour (volumes, modal split, and distribution of traffic over time and space). The model’s value lies in its ability to identify potential ef

  11. A conceptual framework for road safety and mobility applied to cycling safety.

    NARCIS (Netherlands)

    Schepers, P. Hagenzieker, M. Methorst, R. Wee, B. van & Wegman, F.C.M.

    2013-01-01

    Scientific literature lacks a model which combines exposure to risk, risk, and the relationship between them. This paper presents a conceptual road safety framework comprising mutually interacting factors for exposure to risk resulting from travel behaviour (volumes, modal split, and distribution of

  12. A conceptual framework for road safety and mobility applied to cycling safety

    NARCIS (Netherlands)

    Schepers, P.; Hagenzieker, M.P.; Methorst, R.; Van Wee, G.P.; Wegman, F.C.M.

    2013-01-01

    Scientific literature lacks a model which combines exposure to risk, risk, and the relationship between them. This paper presents a conceptual road safety framework comprising mutually interacting factors for exposure to risk resulting from travel behaviour (volumes, modal split, and distribution of

  13. Application of an informatics-based decision-making framework and process to the assessment of radiation safety in nanotechnology.

    Science.gov (United States)

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

    2015-02-01

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

  14. Current status and development perspectives of state nuclear and radiation safety regulation in the Russian Federation

    International Nuclear Information System (INIS)

    transition of the safe use of atomic energy regulation to the regulatory framework where technical regulations will be applied in the Russian Federation], it is necessary to complete very soon the development of federal rules and regulations in the nuclear field (including regulations on the production and use of MOX fuel) and concentrate efforts on producing within stringent time limits a number of technical regulations, including the generic technical regulation 'On Nuclear and Radiation Safety'. It will be also necessary to introduce relevant changes to some federal laws and legal acts of the Russian Federation. Substantial assistance in this respect is rendered by experts of the G-8 Nuclear Safety and Security Working Group, EC regulatory bodies and international organizations (IAEA, OECD/NEA). b) According to the 'Fundamentals of State Policy Pertaining to Ensuring Nuclear and Radiation Safety in the Russian Federation for the Period up to Year 2010 and Further Perspective', approved by the President of the Russian Federation on 4 December 2004, it is necessary to solve a number of significant tasks aimed at enhancing the state safety regulation of atomic energy use, including the improvement of the licensing and oversight effectiveness. c) It has become imminent to develop an emergency response concept in the system of Gosatomnadzor of Russia and the concept of state regulation of nuclear and radiation safety for facilities produced by peaceful nuclear explosion

  15. 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)

    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

  16. 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.

  17. Radiation Safety Professional Certification Process in a Multi-Disciplinary Association

    International Nuclear Information System (INIS)

    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

  18. Radiation Safety Professional Certification Process in a Multi-Disciplinary Association

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-07-01

    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.

  19. Employing ionizing radiation to enhance food safety. A review

    International Nuclear Information System (INIS)

    Food irradiation is employed to ensure food safety or food sterility, extend its shelf-life and reduce the losses due to sprouting, ripening or pests. In the Czech Republic mainly spices, mixed spices and dried vegetables are exposed to ionizing radiation. The leading suppliers of irradiated foodstuffs in Europe are Belgium, France and the Netherlands. In the USA, food irradiation is more common and there are also attempts to enforce irradiation not only for food safety, but also for technological purposes. Even though irradiation is a prospective technology, its application causes physico-chemical changes that may affect nutritional adequacy and sensory characteristics of irradiated food. In this paper, the chemical changes of basic food components (proteins, saccharides, fats) are reviewed. Some chemical changes lead to the formation of radiolytic products whose risks are still subject of scientific research. It is expected that the main use of gamma irradiation will be the treatment of diets for patients suffering from different disorders of the immune system, allergic patients or for the army and space flights. Irradiation may be a critical control point in the production of some types of foodstuffs

  20. Romanian experience on safety and security of radiation sources

    International Nuclear Information System (INIS)

    Romania has established the first administrative structure for controlling the deployment of the nuclear activities in 1961 and the first Romanian nuclear law was published in 1974. In the present, it is in force the Law no. 111, published in 1996 and republished in 2003. Moreover, there are available facilities and services to the persons authorized to manage radioactive sources. The regulation for safety and security of radioactive sources was amended two times in order to implement the international recommendations for setting up the national system for accounting and control of radiation sources and to coordinate the recovery activities. As part of national control programme, the national inventory of sources and devices is updated permanently, when issuing a new authorization, when modifying an existing one, or when renewing an authorization system and records in the database. The government responsibility for the orphan sources is stated in the law on radioactive waste management and decommissioning fund. There is a protocol between CNCAN, Ministry of Internal and Ministry of Health and Family regarding the co-operation in the case of finding orphan sources. When a radiation source is spent, it becomes radioactive waste that has to be disposed off properly. Depending on the case, the holder of a spent source has the possibility either to return the radioactive source to its manufacturer for regeneration or to transfer it to the Radioactive Waste Treatment Facility. (author)

  1. Proceedings of the 7th annual meeting of Japanese Society of Radiation Safety Management 2008 Kanazawa

    International Nuclear Information System (INIS)

    This is the program and the proceedings of the 7th annual meeting of Japanese Society of Radiation Safety Management held from December 3rd through the 5th of 2008. The sessions held were: (1) Software, (2) Radiation Education 1 and 2, (3) Radiation Measurement 1 to 3, (4) Radiation Safety Control, (5) Contamination Control, and (6) Exposed Dose and Dose Level Evaluation. Two special sessions held were: (1) 'Handmade Software for Radiation Safety Control' and (2) 'Learning Radiation Safety Control from Latest Accidents'. 3 keynote lectures were held. 2 invited lectures by the researchers from the United States and Russia were also held. Also, the topic of one panel discussion was 'Goals of Academic Societies related to Radiation Control'. In addition, 2 luncheon seminars were held. (S.K.)

  2. Radiation safety aspects in CA-thyroid treatment

    International Nuclear Information System (INIS)

    The isolation room in hospital at the All India Institute of Medical Sciences (AIIMS), New Delhi (India) is located on the 6th floor of the ward block with two beds. Effluent from the isolation room flows down to ground floor through an independent ducting line and then directed to the delay tank system through manholes. Routine radiation survey around the isolation room, along the plumbing line from 6th floor to the ground level, along the manholes and around the fencing of the storage delay tank is being done. Measurements in and around the isolation rooms are done daily whereas other measurements are done at least once a week normally on the day of maximum discharge of radioactivity in the effluent. The average radiation dose levels near the patient bed in general ward on 6th floor which is in front of the isolation room is 0.3 to 0.35 μSv/h which is slightly higher than the background level (0.2 μSv/h). Dose levels along the plumbing line from 6th to 1st floor is around 0.6 μSv/h at the sites accessible to public. Radiation level in manhole number 1 to 5 varies from 3 to 0.9 μSv/h whereas manholes from 6 to 10 show the dose rate from 0.5 to 0.4 μSv/h. The radiation dose rate around the fence remains between 0.2-0.3 μSv/h. There is no habitation above manholes 1 to 5 nor that area is accessible to public. There is free passage above manholes 6-8 and again there is no habitation near manhole 9 and 10. Measurements show that the activity release from delay tank and its dilution in the main sewer is within tolerance limits. Mandatory routine measurements have been helpful to maintain our confidence level on radiation safety standards at our centre. (author)

  3. Safety of radiation sources and security of radioactive materials. Contributed papers

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA) in co-operation with the European Commission (EC), International Criminal Police Organization (INTERPOL) and the World Customs Organization (WCO) organized an International Conference on the Safety of Radiation Sources and the Security of Radioactive Materials, in Dijon, France, from 14 to 18 September 1998. The Government of France hosted this Conference through the Commissariat a l'energie atomique, Direction des applications militaires (CEA/DAM). This TECDOC contains the contributed papers dealing with the topics of this Conference which were accepted by the Conference Programme Committee for presentation. The papers written in one of the two working languages of the Conference, English or French are presented here each by a separate abstract. Ten technical sessions covered the following subjects: the regulatory control of radiation sources, including systems for notification, authorization and inspection; safety assessment techniques applied to radiation sources and design and technological measures including defense in depth and good engineering practice; managerial measures, including safety culture, human factors, quality assurance, qualified experts, training and education; learning from operational experience; international co-operation, including reporting systems and databases; verification of compliance, monitoring of compliance and assessment of the effectiveness of national programmes for the safety of sources; measures to prevent breaches in the security of radioactive materials, experience with criminal acts involving radioactive materials; detection and identification technologies for illicitly trafficked radioactive materials; response to detected cases and seized radioactive materials, strengthening of the awareness, training and exchange of information. The IAEA plans to issue the proceedings of this Conference containing the invited presentations, rapporteurs and Chairpersons overviews and summaries

  4. Radiation processing of leafy vegetables to ensure their microbial safety

    International Nuclear Information System (INIS)

    Leafy vegetables which are consumed in raw form such as spinach, coriander and mint were found to be heavily burdened with microbial load including presumptive coliform, an indicator of pathogenic contaminations. Total aerobic plate counts in fresh spinach, coriander and mint samples collected from different location of Mumbai and nearby cities were found to be in the order of ∼ 107 to ∼ 108 CFU/g. In these samples yeast and mould count was in the order of ∼105 CFU/g and presumptive coliform in the order of ∼ 104 to ∼105 CFU/g. As per USFDA coliform load in the food commodity should be nil. The finding thus indicates that these fresh vegetables are not safe for raw consumption. Hence there is utmost need of process which can ensure the safety by reducing their microbial load below permissible level (<104 CFU/gm) and coliform load to nil without affecting the appearance and quality of such produce. In this study gamma radiation was used for hygienization of leafy vegetables. The sample were first cleaned in potable water followed by sodium hypochlorite wash (200 ppm for 20 min), air dried, packed in styrofoam based tray, wrapped with cling film and radiation processed at 1 to 2.5 kGy and stored at 4 and 10℃ . Post irradiation microbiological analysis of radiation processed samples was carried out at in 2 kGy irradiated samples total plate count was below ∼103 CFU/g and presumptive coliform count was below detectable level. Yeast and mould count in these samples also reduced to below ∼ 103 CFU/g. Based on the study the following combination treatment can be given to raw leafy vegetables, washing with potable water (5 min) → sodium hypochlorite (200 ppm 20 min) wash → Air drying → Packaging in styrofoam based tray and wrapping with cling film → Irradiation at 2 kGy → storage at 4℃ . Besides ensuring safety the treatment also resulted in increased shelf life extension of the commodities up to 20 days. (author)

  5. Communication and Public Information in Development and Maintenance of Radiation Safety

    International Nuclear Information System (INIS)

    The natural source of Non-Ionizing radiation (NIR) in our environment is the sun. Artificial NIR is widely used in medical and industrial applications and also in households. The most important medical NIR applications are phototherapy, surgical lasers and magnetic resonance imaging. In industry NIR is applied in radio frequency heaters and laser printing. NIR has applications even in entertainment and cosmetics: High power lasers are used in light shows and sun beds emit artificial ultraviolet radiation (UVR) for tanning. From the safety point of view the field is indeed very wide from harmless and common items to devices which can cause acute health hazards. The use of non-ionizing radiation needs neither any safety licence nor other kind of authorisation. The users of NIR devices varies from professionals in health care or lighting technology to those who only use them as a sideline in their main work like beauticians. Also laypersons use various NIR devices like microwave ovens, laser pointers and mobile phones. Many NIR devices are used in applications where the user does not have the knowledge to understand the health risks associated with the device. Thus the only way is to educate the users by communication and public information. (orig.)

  6. Proceedings of the Seminar on Environmental and Radiation Safety Aspect at Non-nuclear Industry

    International Nuclear Information System (INIS)

    The Seminar on Environmental and Radiation Safety Aspect at Non-nuclear Industry held on March 2003 in Jakarta. The purpose of this Seminar be able to information exchange among research workers in National Nuclear Energy Agency. The Seminar discussed about Science and Technology of Radiation Safety and Environment. There are 17 papers which have separated index. (PPIN)

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

    International Nuclear Information System (INIS)

    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

  8. A collaborative effort of medical and educational facilities for radiation safety training of nurses

    International Nuclear Information System (INIS)

    The proper understanding of radiation safety by nursing staffs in hospitals are essential not only for radiation protection of themselves against occupational radiation exposure but for quality nursing for patients who receive medical radiation exposure. The education program on radiation in nursing schools in Japan is, however, rather limited, and is insufficient for nurses to acquire basic knowledge of radiation safety and protection. Therefore, the radiation safety training of working nurses is quite important. A hospital-based training needs assignment of radiation technologists and radiologists as instructors, which may result in temporary shortage of these staffs for patients' services. Additionally, the equipments and facilities for radiation training in a hospital might not be satisfactory. In order to provide an effective education regarding radiation for working nurses, the radiation safety training course has been conducted for nurse of the university hospital by the collaboration of medical and educational staffs in Nagasaki University. This course was given for 6 hours in Radioisotope Research Center, a research and education facility for radiation workers using radioisotopes. The curriculum of this course included basics of radiation, effects of radiation on human health, procedures in clinical settings for radiation protection and practical training by using survey meters, which were mainly based on the radiation safety training for beginners according to the Japanese law concerning radiation safety with a modification to focus on medical radiation exposure. This course has been given to approximately 25 nurses in a time, and held 13 times in May 2000 through October 2003 for 317 nurse overall. The pre-instruction questionnaire revealed that 60% of nurses felt fears about radiation diagnosis or therapy, which reduced to less than 15% in the post-instruction surveillance. The course also motivated nurses to give an answer to patients' questions about

  9. 应用锥体束 CT分析肝癌图像引导放疗的摆位误差及外放边界%Cone Beam CT Applied to Analysis of Set-up Error and Safety Margin in Image-Guided Radiation Therapy for Liver Cancer

    Institute of Scientific and Technical Information of China (English)

    卿莉萍; 梁世雄; 洪超善; 付庆国; 韩青

    2014-01-01

    目的:分析千伏级锥体束CT ( KV-CBCT )肝癌图像引导放疗摆位误差,为肝癌放疗计划靶区(PTV)的外放边界提供参考。方法应用医科达Synergy直线加速器治疗31例肝癌患者,KV-CBCT扫描采集的X线容积图像( XVI)与计划CT图像的靶中心匹配,获得腹背( X)、头脚( Y)、左右( Z)三个方向的线性误差x、y、z和绕X、Y、Z轴旋转形成的旋转误差u、v、w。由公式计算出肝癌临床靶区( CTV)到计划靶区( PTV)的外放边界值( MPTV )。结果共进行275次 CBCT 扫描,其在 X、Y、Z 方向上摆位误差 x、y、z 中位数分别为1.70 mm、1.30 mm、0.80 mm,旋转误差u、v、w分别为0.65°、0.38°、0.31°。 MPTV在X、Y、Z方向上分别为4.11 mm、8.49 mm、4.94 mm。结论采用KV-CBCT技术测量肝癌图像引导放疗的摆位误差,为肝癌放疗MPTV提供参考,提高了肝癌放疗的精准性。%Objective To analyze the set-up errors in image-guided radiation therapy for liver cancer guided with kilo-voitage cone beam computed tomography ( CBCT ) to calculate the referential safety margin of plan target volume ( PTV) .Methods Thirty-one patients with liver cancer were involved in the treatment with Elekta Synergy linear accelerator , the kilo-voltage CBCT-collected volume of X-ray images(XVI) was matched with the center of target of planning CT images to obtain the linearity errors(x,y,z) and the rotational errors(u,v,w) in three directions:back-belly(X),head-feet(Y),left-right (Z).The margin(MPTV) between clinical target volume(CTV) and PTV was calculated based on the formula .Results A total of 275 CBCT scans showed that in the X ,Y,Z directions,the mean linear errors ( x,y,z) were 1.70 mm, 1.30 mm,0.80 mm,respectively,and the rotational errors(u,v,w) were 0.65°,0.38°,0.31°,respectively.MPTV in three-dimensional directions(X,Y,Z) were 4.11 mm,8.49 mm,4.94 mm,respectively.Conclusion Kilo

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

    International Nuclear Information System (INIS)

    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

  11. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1987-12-01

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

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

    International Nuclear Information System (INIS)

    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

  14. Notification and authorization for the use of radiation sources (supplement to IAEA Safety Standards Series No. GS-G-1.5)

    International Nuclear Information System (INIS)

    The achievement and maintenance of a high level of safety in the use of radiation sources depend on there being a sound legal and governmental infrastructure, including a national regulatory body with well-defined responsibilities and functions. These responsibilities and functions include establishing and implementing a system for notification and authorization for control over radiation sources, including a system for review and assessment of applications for authorization. The Safety Requirements publication entitled Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety establishes the requirements for legal and governmental infrastructure. The term 'infrastructure' refers to the underlying structure of systems and organizations. This includes requirements concerning the establishment of a regulatory body for radiation sources and the responsibilities and functions assigned to it. The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards or the BSS) establish basic requirements for protection against risks associated with exposure to ionizing radiation and for the safety of radiation sources. The application of the BSS is based on the presumption that national infrastructures are in place to enable governments to discharge their responsibilities to for radiation protection and safety. This TECDOC provides practical guidance on the process for dealing with applications for authorization and accepting notifications to regulatory bodies. Examples of guidelines that may be used by persons required to notify or apply for authorization and of the regulatory body's review and assessment procedures are provided in the Appendices. The TECDOC is oriented towards national regulatory infrastructures concerned with protection and safety for radiation sources used in medicine, industry, agriculture, research and education

  15. Evaluation of safety, an unavoidable requirement in the applications of ionizing radiations

    International Nuclear Information System (INIS)

    The safety assessments should be conducted as a means to evaluate compliance with safety requirements (and thus the application of fundamental safety principles) for all facilities and activities in order to determine the measures to be taken to ensure safety. It is an essential tool in decision making. For long time we have linked the safety assessment to nuclear facilities and not to all practices involving the use of ionizing radiation in daily life. However, the main purpose of the safety assessment is to determine if it has reached an appropriate level of safety for an installation or activity and if it has fulfilled the objectives of safety and basic safety criteria set by the designer, operating organization and the regulatory body under the protection and safety requirements set out in the International Basic safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. This paper presents some criteria and personal experiences with the new international recommendations on this subject and its practical application in the region and demonstrates the importance of this requirement. Reflects the need to train personnel of the operator and the regulatory body in the proportional application of this requirement in practice with ionizing radiation

  16. 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)

    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

  17. Risk analysis methods: their importance for safety assessment of practices using radiation

    International Nuclear Information System (INIS)

    Radiation safety has been based for many years on verification of compliance with regulatory requirements, codes of practice and international standards, which can be considered prescriptive methods. Accident analyses have been published, lessons have been learned and safety assessments have incorporated the need to check whether a facility is ready to avoid accidents similar to the reported ones. These approaches can be also called 'reactive methods'. They have in common the fundamental limitation of being restricted to reported experience, but do not take into account other potential events, which were never published or never happened, i.e. latent risks. Moreover, they focus on accident sequences with major consequences and low probability but may not pay enough attention to other sequences leading to lower, but still significant consequences with higher probability. More proactive approaches are, therefore, needed, to assess risk in radiation facilities. They aim at identifying all potential equipment faults and human error, which can lead to predefined unwanted consequences and are based on the general risk equation: Risk = Probability of occurrence of an accidental sequence * magnitude of the consequences. In this work, a review is given of the experience obtained by the countries of the Ibero American Forum of Nuclear and Radiation Safety Regulatory Organizations, by applying proactive methods to radiotherapy practice. In particular, probabilistic safety assessment (PSA) used for external beam treatments with linear electron accelerators and two studies, on cobalt 60 therapy and brachytherapy using the risk-matrix approach are presented. The work has identified event sequences, their likelihood of occurrence, the consequences, the efficiency of interlocks and control checks and the global importance in terms of overall risk, to facilitate decision making and implementation of preventive measures. A comparison is presented of advantages and limitations of

  18. Basic Safety Standards for Radiation Protection - 1967 Edition

    International Nuclear Information System (INIS)

    This first revision of the Basic Safety Standards was approved by the IAEA Board of Governors in September 1965. It was prepared with the assistance of a panel of experts chaired by Prof. L. Bugnard, Director of the French Institut National d'Hygiene, and attended by representatives of several international organizations. Comments from Member States were considered and changes were introduced on the basis of recommendations made by the International Commission on Radiological Protection in 1966. The Director General of the IAEA has been authorized by the Board to apply the revised Standards to IAEA and IAEA-assisted operations. It has also been recommended that the national regulations of Member States should conform, as far as is practicable, to the revised Standards. (author)

  19. Applying different quality and safety models in healthcare improvement work: Boundary objects and system thinking

    International Nuclear Information System (INIS)

    A number of theoretical models can be applied to help guide quality improvement and patient safety interventions in hospitals. However there are often significant differences between such models and, therefore, their potential contribution when applied in diverse contexts. The aim of this paper is to explore how two such models have been applied by hospitals to improve quality and safety. We describe and compare the models: (1) The Organizing for Quality (OQ) model, and (2) the Design for Integrated Safety Culture (DISC) model. We analyze the theoretical foundations of the models, and show, by using a retrospective comparative case study approach from two European hospitals, how these models have been applied to improve quality and safety. The analysis shows that differences appear in the theoretical foundations, practical approaches and applications of the models. Nevertheless, the case studies indicate that the choice between the OQ and DISC models is of less importance for guiding the practice of quality and safety improvement work, as they are both systemic and share some important characteristics. The main contribution of the models lay in their role as boundary objects directing attention towards organizational and systems thinking, culture, and collaboration

  20. The nuclear safety and the radiation protection in France in 2003

    International Nuclear Information System (INIS)

    Nine points are reviewed: the law project relative to the safety and openness in nuclear field, the safety of the European PWR type Reactor, the priorities in radiation protection, inspection of radiation protection, the surveillance of patients exposure to ionizing radiations, the hot days and dryness of summer 2003 and the functioning of nuclear power plant, the national planning of radioactive waste management, the becoming of high level and years living radioactive waste, the European nuclear policy. (N.C.)

  1. Safety of radiation sources and security of radioactive materials. A Romanian approach

    International Nuclear Information System (INIS)

    After a brief explanation on the scope of applications of nuclear energy and practices with ionizing radiation in Romania, the report explains the current national infrastructure for radiation safety making reference in particular to the National Commission for Nuclear Activities Control as the regulatory authority for the safety of radiation sources. The report also describes the existing legal framework, provides information on the list of normative acts in force, and on the system of authorization, inspection and enforcement, which operates effectively. (author)

  2. Radiobiological basis for setting neutron radiation safety standards

    International Nuclear Information System (INIS)

    Present neutron standards, adopted more than 20 yr ago from a weak radiobiological data base, have been in doubt for a number of years and are currently under challenge. Moreover, recent dosimetric re-evaluations indicate that Hiroshima neutron doses may have been much lower than previously thought, suggesting that direct data for neutron-induced cancer in humans may in fact not be available. These recent developments make it urgent to determine the extent to which neutron cancer risk in man can be estimated from data that are available. Two approaches are proposed here that are anchored in particularly robust epidemiological and experimental data and appear most likely to provide reliable estimates of neutron cancer risk in man. The first approach uses gamma-ray dose-response relationships for human carcinogenesis, available from Nagasaki (Hiroshima data are also considered), together with highly characterized neutron and gamma-ray data for human cytogenetics. When tested against relevant experimental data, this approach either adequately predicts or somewhat overestimates neutron tumorigenesis (and mutagenesis) in animals. The second approach also uses the Nagasaki gamma-ray cancer data, but together with neutron RBEs from animal tumorigenesis studies. Both approaches give similar results and provide a basis for setting neutron radiation safety standards. They appear to be an improvement over previous approaches, including those that rely on highly uncertain maximum neutron RBEs and unnecessary extrapolations of gamma-ray data to very low doses. Results suggest that, at the presently accepted neutron dose limit of 0.5 rad/yr, the cancer mortality risk to radiation workers is not very different from accidental mortality risks to workers in various nonradiation occupations

  3. On applying safety archetypes to the Fukushima accident to identify nonlinear influencing factors

    International Nuclear Information System (INIS)

    Nuclear power plants are typically characterized as high reliable organizations. In other words, they are organizations defined as relatively error free over a long period of time. Another relevant characteristic of the nuclear industry is that safety efforts are credited to design. However, major accidents, like the Fukushima accident, have shown that new tools are needed to identify latent deficiencies and help improve their safety level. Safety archetypes proposed elsewhere (e. g., safety issues stalled in the face of technological advances and eroding safety) consonant with International Atomic Energy Agency (IAEA) efforts are used to examine different aspects of accidents in a systemic perspective of the interaction between individuals, technology and organizational factors. Safety archetypes can help consider nonlinear interactions. Effects are rarely proportional to causes and what happens locally in a system (near the current operating point) often does not apply to distant regions (other system states), so that one has to consider the so-called nonlinear interactions. This is the case, for instance, with human probability failure estimates and safety level identification. In this paper, we discuss the Fukushima accident in order to show how archetypes can highlight nonlinear interactions of factors that influenced it and how to maintain safety levels in order to prevent other accidents. The initial evaluation of the set of archetypes suggested in the literature showed that at least four of them are applicable to the Fukushima accident, as is inferred from official reports on the accident. These are: complacency (that is, the effects of complacency on safety), decreased safety awareness, fixing on symptoms and not the real causes and eroding safety. (author)

  4. On applying safety archetypes to the Fukushima accident to identify nonlinear influencing factors

    Energy Technology Data Exchange (ETDEWEB)

    Sousa, A.L., E-mail: alsousa@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Ribeiro, A.C.O., E-mail: antonio.ribeiro@bayer.com [Bayer Crop Science Brasil S.A., Belford Roxo, RJ (Brazil); Duarte, J.P., E-mail: julianapduarte@poli.ufrj.br [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Escola Politecnica. Departamento de Engenharia Nuclear; Frutuoso e Melo, P.F., E-mail: frutuoso@nuclear.ufrj.br [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COOPE/UFRJ), RJ (Brazil). Programa de Engenharia Nuclear

    2013-07-01

    Nuclear power plants are typically characterized as high reliable organizations. In other words, they are organizations defined as relatively error free over a long period of time. Another relevant characteristic of the nuclear industry is that safety efforts are credited to design. However, major accidents, like the Fukushima accident, have shown that new tools are needed to identify latent deficiencies and help improve their safety level. Safety archetypes proposed elsewhere (e. g., safety issues stalled in the face of technological advances and eroding safety) consonant with International Atomic Energy Agency (IAEA) efforts are used to examine different aspects of accidents in a systemic perspective of the interaction between individuals, technology and organizational factors. Safety archetypes can help consider nonlinear interactions. Effects are rarely proportional to causes and what happens locally in a system (near the current operating point) often does not apply to distant regions (other system states), so that one has to consider the so-called nonlinear interactions. This is the case, for instance, with human probability failure estimates and safety level identification. In this paper, we discuss the Fukushima accident in order to show how archetypes can highlight nonlinear interactions of factors that influenced it and how to maintain safety levels in order to prevent other accidents. The initial evaluation of the set of archetypes suggested in the literature showed that at least four of them are applicable to the Fukushima accident, as is inferred from official reports on the accident. These are: complacency (that is, the effects of complacency on safety), decreased safety awareness, fixing on symptoms and not the real causes and eroding safety. (author)

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

    Science.gov (United States)

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

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

  6. Problems in radiation safety of personell dealing with tritium

    International Nuclear Information System (INIS)

    The problems of radiation safety of personnel working with tritium in oil-fields, at poultry plants when ionizing air, in watch making and instrument making industries, scientific laboratories are considered. The irradiation levels of the personnel engaged in preparation of tritium compounds and products constitute 0.1-1.2 rem quaterly. The dynamics of forming an internal irradiation dose are close to linear and the levels of tritium content in body are practically constant. When working in oil-fields, especially dangerous are the operations of diluting HTO in tanks and pumping labelled water into oil wells, where the dose amounts to 10-100 mrem per operation. The results of irradiation at poultry plants, evaluations of irradiation levels for personnel and population using the poultry bred in the atmosphere containing tritium are presented. Discussed are also the problems of radiotoxicity relating to tritium luminous compounds of permanent action as well as the results of studying their intake by animals and their distribution in the organism and excretion

  7. Dynamic solar radiation control in buildings by applying electrochromic materials

    Energy Technology Data Exchange (ETDEWEB)

    Jelle, B.P.; Gustavsen, A.

    2010-07-01

    Full text: Smart windows like electrochromic windows (ECWs) are windows which are able to regulate the solar radiation throughput by application of an external voltage. The ECWs may decrease heating, cooling and electricity loads in buildings by admitting the optimum level of solar energy and daylight into the buildings at any given time, e.g. cold winter climate versus warm summer climate demands. In order to achieve as dynamic and flexible solar radiation control as possible, the ECWs may be characterized by a number of solar radiation glazing factors, i.e. ultraviolet solar transmittance, visible solar transmittance, solar transmittance, solar material protection factor, solar skin protection factor, external visible solar reflectance, internal visible solar reflectance, solar reflectance, solar absorbance, emissivity, solar factor and colour rendering factor. Comparison of these solar quantities for various electrochromic material and window combinations and configurations enables one to select the most appropriate electrochromic materials and ECWs for specific buildings. Measurements and calculations were carried out on two different electrochromic window devices. (Author)

  8. Radiation and Reason Why radiation at modest dose rates is quite harmless and current radiation safety regulations are flawed

    CERN Document Server

    CERN. Geneva

    2013-01-01

    Data on the impact of ionising radiation on life are examined in the light of evolutionary biology. This comparison confirms that fear of nuclear radiation is not justified by science itself; rather it originates in a failure of public trust in nuclear science, a relic of the international politics of the Cold War era. Current ionisation safety regulations appease this fear but without scientific support and they need fundamental reformulation. This should change the reaction to accidents like Fukushima, the cost of nuclear energy and the application of nuclear technology to the supply of food and fresh water. Such a boost to the world economy would require that more citizens study and appreciate the science involved – and then tell others -- not as much fun as the Higgs, perhaps, but no less important! www.radiationandreason.com

  9. ASN report of the status of nuclear safety and radiation protection in France in 2012

    International Nuclear Information System (INIS)

    After a presentation of the French Nuclear Safety Authority (ASN), its missions, some key figures illustrating its activities and its organisation, this report proposes an overview of marking events and of actions undertaken by the ASN after the Fukushima accident. Then, the report proposes a detailed and commented overview of actions undertaken by the ASN in different fields and domains: nuclear activities, principles and actors of nuclear safety and radiation protection control, regulation, control of nuclear activities and of exposures to ionizing radiations, radiological and post-accidental emergency situations, public information and transparency, international relationships, regional overview of nuclear safety and radiation protection. The last part addresses activities controlled by the ASN: medical use of ionizing radiations, industrial, research and veterinary uses and source safety, transport of radioactive materials, electronuclear plants, installations related to nuclear fuel cycle, nuclear research and other nuclear installations, safety of dismantling of base nuclear installations, radioactive wastes and polluted sites

  10. Education and Training in Radiation, Transport and Waste Safety Newsletter, No. 3, May 2014

    International Nuclear Information System (INIS)

    Building competence through education and training in radiation protection, radioactive waste safety, and safety in transport of radioactive material is fundamental to the establishment of a comprehensive and sustainable national infrastructure for radiation safety, which in turn is essential for the beneficial uses of radiation while ensuring appropriate protection of workers, patients, the public and the environment. IAEA’s Division of Radiation, Transport and Waste Safety provides direct assistance to Member States via a range of tools and mechanisms, such as by organizing educational and training events, developing standardized syllabi with supporting material and documents, and by fostering methodologies to build sustainable competence and enhance effectiveness in the provision of training. The main objective is to support Member States in the application of the IAEA Safety Standards. Seminars and additional activities are also promoted to broaden knowledge on relevant areas for an effective application of the standards

  11. Industrial Safety and Applied Health Physics Division annual report for 1981

    International Nuclear Information System (INIS)

    Activities over the past year are summarized for the Health Physics Department, the Environmental Management Program, and the Safety Department. The Health Physics Department conducts radiation and safety surveys, provides personnel monitoring services for both external and internal radiation, and procures, services, and calibrates appropriate portable and stationary health physics instruments. It was determined that the maximum whole-body dose sustained by an employee was about 3.8 rems, which is 76% of the applicable standard of 5 rems. The greatest cumulative dose to the skin of the whole body received by an employee during 1981 was about 5.9 rems, or 39% of the applicable standard of 15 rems. Atmospheric iodine sampled by the Department of Environmental Management at the perimeter stations averged 0.13E to 14 μCi/cc during 1981. This average represents 131I released to uncontrolled areas. All air samples taken had values below the allowable standards. The concentrations of 90Sr in milk from both the immediate and remote environs of ORNL are also within FRC range I. The average value of 1.5 E to 9 μCi/mL represents 0.5% of the CG/sub w/ for drinking water applicable to individuals in the general population. The Safety Department reported that the continuing emphasis on safety during CY 1981 resulted in significant improvements in the ORNL safety program: safety performance was better than all CY 1981 on-the-job injury and illness goals. Through December 31, 1981, the Laboratory had worked 600 days and accumulated 14,015,826 exposure-hours since the last lost-work-day case

  12. Study on development of education model and its evaluation system for radiation safety

    CERN Document Server

    Seo, K W; Nam, Y M

    2002-01-01

    As one of the detailed action strategy of multi object preparedness for strengthening of radiation safety management by MOST, this project was performed, in order to promote the safety culture for user and radiation worker through effective education program. For the prevention of radiological accident and effective implementation of radiation safety education and training, this project has been carried out the development of education model and its evaluation system on radiation safety. In the development of new education model, education course was classified; new and old radiation worker, temporary worker, lecturer and manager. The education model includes the contents of expanding the education opportunity and workplace training. In the development of evaluation system, the recognition criteria for commission-education institute and inside-education institute which should establish by law were suggested for evaluation program. The recognition criteria contains classification, student, method, facilities, ...

  13. Radiation safety during construction of the encapsulation at the Chernobyl nuclear power plant

    International Nuclear Information System (INIS)

    A review is given of the main radiation safety problems which were solved during design and construction of the encapsulation for Unit 4 of the Chernobyl nuclear power plant which was destroyed in the accident of 26 April 1986. Information is given on the conditions under which large scale restoration work was performed, and on the design stipulations laid down for construction of the encapsulation for the destroyed unit. The paper discusses the technical, organizational and health measures which were used to ensure that radiation safety regulations and standards were observed during construction. The problems of organizing a radiation safety service inside the construction and assembly organization which built the encapsulation are discussed. Finally, conclusions are drawn with regard to the experience which has been gained in the area of radiation safety implementation during large scale post-accident restoration work under problematic radiation conditions such as those at the Chernobyl nuclear power plant site. (author). 7 refs, 6 figs, 1 tab

  14. Radiation protection in dentistry. Recommended safety procedures for the use of dental x-ray equipment. Safety code 30

    International Nuclear Information System (INIS)

    The Radiation Protection Bureau has prepared a series of documents on safety codes to set out requirements for the safe use of radiation-emitting equipment. This Safety Code has been prepared to provide specific guidance to the dentist, dental hygienist, dental assistant and other support personnel concerned with safety procedures and equipment performance. Dental radiography is one of the most valuable tools used in modern dental health care. It makes possible the diagnosis of physical conditions that would otherwise be difficult to identify. The use of dental radiological procedures must be carefully managed, because x-radiation has the potential for damaging healthy cells and tissues. Although no known occurrence of cancer or genetic damage has been observed from radiation doses delivered in modern dentistry, and until more evidence is available, one should practice radiation hygiene with the same care as would be dictated if a hazard were known to exist. The aim of radiation protection in dentistry is to obtain the desired clinical information with minimal radiation exposure to patients, dental personnel and the public. 15 tabs

  15. On the state of the radiation safety in the atomic energy and nuclear industry of Russia

    International Nuclear Information System (INIS)

    The general aspects of the activity of organs of government in the field of human radiation protection and some other problems of nuclear industry connecting with the new economic and politic situation in Russia have been discussed. There are present information about the organs of government relating to the questions of radiation safety and the major directions of governmental policy in this fields. Some problems of the elimination of the consequences of the accidents in NPPs (Chernobyl, Chelyabinsk), the programs of the radiation safety improvement of population and the information about new normative nuclear safety documents have also been written in this report. (author)

  16. Progress in the Regulation of Radiation Environmental Safety in the Utilization of Mineral Resources in China

    International Nuclear Information System (INIS)

    In the paper, the background to the progress made in the regulation of radiation environmental safety in the utilization of mineral resources other than uranium (thorium) ores in China is first introduced. The regulatory experience of radiation environmental safety in the utilization of mineral resources in international organizations and industrial countries (e.g. International Commission on Radiological Protection, IAEA, European Union and United States of America) is surveyed and analysed. Finally, the scope and requirements of regulation on the radiation environmental safety in the utilization of mineral resources in China are stated. (author)

  17. ASN report on the status of nuclear safety and radiation protection in France in 2011

    International Nuclear Information System (INIS)

    The first part of this huge report proposes a detailed overview of ASN activities in different fields: ionizing radiations related to nuclear activities and risks for health and the environment, principles and actors of nuclear safety control, of radiation protection and of protection of the environment, regulation, control of nuclear activities and exposures to ionizing radiations, emergency situations, public information and transparency, international relationships, regional overview of nuclear safety and radiation protection. The second part addresses the activities controlled by the ASN: medical use of ionizing radiations, non medical use of ionizing radiations, transport of radioactive materials, electronuclear power stations, facilities involved in the nuclear fuel cycle, research facilities and other nuclear installations, the safety of dismantling of nuclear base installations, radioactive wastes and polluted sites and soils

  18. Relationship between knowledge, attitude, behavior, and self-efficacy on the radiation safety management of radiation workers in medical institutions

    Energy Technology Data Exchange (ETDEWEB)

    Han, Eun Ok [Daegu Health College, Daegu (Korea, Republic of)

    2007-06-15

    Radiation safety managements in medical institutions are needed to protect certain radiation damages as a part of National Coalition. This study investigates the characteristics of self-efficacy that become the major factor on the knowledge, attitude, and behavior on the radiation safety management of radiation workers as an approach of educational aspects and analyzes the relationship between such factors to provide basic materials for improving the activity level of radiation safety managements. In order to implement the goal of this study, a survey was performed for 1,200 workers who were engaged in radiation treatments in medical centers, such as general hospital, university hospital, private hospital, and public health center for 42 days from July 23, 2006. Then, the results of the analysis can be summarized as follows: 1. Average scores on knowledge, attitude, and behavior in the radiation safety management were presented as 75.76{+-}11.20, 90.55{+-}8.59, 80.58{+-}11.70, respectively. Also, the average score of self-efficacy was recorded as 73.55{+-}9.82. 2. Knowledge levels in the radiation safety management showed significant differences according to the sex, age, marriage, education, and experience. Also, males of married, older, highly educated, and largely experienced represented high knowledge levels. Attitude levels in the radiation safety management showed certain significant differences according to the type of medical centers in which private hospitals showed a relatively low level compared to that of high levels in university hospitals. Behavior levels in the radiation safety management also represented significant differences according to the age, marriage, education, experience, and types of medical centers. Factors in married, general hospital, older, highly educated, and largely experienced showed high behavior levels. In addition, the self-efficacy showed certain differences according to the marriage and types of medical centers. Factors in

  19. Relationship between knowledge, attitude, behavior, and self-efficacy on the radiation safety management of radiation workers in medical institutions

    International Nuclear Information System (INIS)

    Radiation safety managements in medical institutions are needed to protect certain radiation damages as a part of National Coalition. This study investigates the characteristics of self-efficacy that become the major factor on the knowledge, attitude, and behavior on the radiation safety management of radiation workers as an approach of educational aspects and analyzes the relationship between such factors to provide basic materials for improving the activity level of radiation safety managements. In order to implement the goal of this study, a survey was performed for 1,200 workers who were engaged in radiation treatments in medical centers, such as general hospital, university hospital, private hospital, and public health center for 42 days from July 23, 2006. Then, the results of the analysis can be summarized as follows: 1. Average scores on knowledge, attitude, and behavior in the radiation safety management were presented as 75.76±11.20, 90.55±8.59, 80.58±11.70, respectively. Also, the average score of self-efficacy was recorded as 73.55±9.82. 2. Knowledge levels in the radiation safety management showed significant differences according to the sex, age, marriage, education, and experience. Also, males of married, older, highly educated, and largely experienced represented high knowledge levels. Attitude levels in the radiation safety management showed certain significant differences according to the type of medical centers in which private hospitals showed a relatively low level compared to that of high levels in university hospitals. Behavior levels in the radiation safety management also represented significant differences according to the age, marriage, education, experience, and types of medical centers. Factors in married, general hospital, older, highly educated, and largely experienced showed high behavior levels. In addition, the self-efficacy showed certain differences according to the marriage and types of medical centers. Factors in married

  20. The activity at the state organs of Russia in the field for providing radiation safety

    International Nuclear Information System (INIS)

    The principles of reliable, efficient radiation safety of enterprises, research institute and organizations of Minatom of Russian Federation, environmental protection and some other problems have been discussed in this report. It consists of three parts. The first contents the information of the governmental and industrial safety systems on the territory of Russian Federation. The second part comprises the findings distinguishing the safety of the NPPs and the enterprises of nuclear industry. Some problems of the actual researches and application developments including the development of new international nuclear safety standards based on recommendations of International Committee of Radiation Protection have been written in third part. (author)

  1. The Safety Assessment of OPR-1000 for Station Blackout Applying Combined Deterministic and Probabilistic Procedure

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Dong Gu; Ahn, Seung-Hoon; Cho, Dae-Hyung [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-05-15

    This is termed station blackout (SBO). However, it does not generally include the loss of available AC power to safety buses fed by station batteries through inverters or by alternate AC sources. Historically, risk analysis results have indicated that SBO was a significant contributor to overall core damage frequency. In this study, the safety assessment of OPR-1000 nuclear power plant for SBO accident, which is a typical beyond design basis accident and important contributor to overall plant risk, is performed by applying the combined deterministic and probabilistic procedure (CDPP). In addition, discussions are made for reevaluation of SBO risk at OPR-1000 by eliminating excessive conservatism in existing PSA. The safety assessment of OPR-1000 for SBO accident, which is a typical BDBA and significant contributor to overall plant risk, was performed by applying the combined deterministic and probabilistic procedure. However, the reference analysis showed that the CDF and CCDP did not meet the acceptable risk, and it was confirmed that the SBO risk should be reevaluated. By estimating the offsite power restoration time appropriately, the SBO risk was reevaluated, and it was finally confirmed that current OPR-1000 system lies in the acceptable risk against the SBO. In addition, it was demonstrated that the proposed CDPP is applicable to safety assessment of BDBAs in nuclear power plants without significant erosion of the safety margin.

  2. Experiments in atomic and applied physics using synchrotron radiation

    International Nuclear Information System (INIS)

    A diverse program in atomic and applied physics using x rays produced at the X-26 beam line at the Brookhaven National Synchrotron Light Source is in progress. The atomic physics program studies the properties of multiply-ionized atoms using the x rays for photo-excitation and ionization of neutral atoms and ion beams. The applied physics program builds on the techniques and results of the atomic physics work to develop new analytical techniques for elemental and chemical characterization of materials. The results are then used for a general experimental program in biomedical sciences, geo- and cosmochemistry, and materials sciences. The present status of the program is illustrated by describing selected experiments. Prospects for development of new experimental capabilities are discussed in terms of a heavy ion storage ring for atomic physics experiments and the feasibility of photoelectron microscopy for high spatial resolution analytical work. 21 refs., 11 figs., 2 tabs

  3. Radiation Protection and Nuclear Safety Regulatory Inspection: a happy marriage?

    International Nuclear Information System (INIS)

    As the subsidiary of the Belgian Federal Agency for Nuclear Control (FANC), Bel V performs the regulatory inspections and safety assessments in nuclear installations, according to the Belgian Royal Decree of July 20. 2001. This Royal Decree is not meant to give a recipe on how to perform inspections and therefore requires interpretation. This paper presents the inspection techniques and practices applied by the Bel V inspectors in order to comply with the spirit of the Royal Decree, using the available resources. AT Bel V the inspections are based on the sampling principle in combination with the experience feedback process. Inspections occur frequently, typically once a week. Concerning documentation, the inspector looks at a sample of documents, the licensee knows he has to produce high-quality documents that have to be correct and as a consequence the licensee has to set internal independent review. If the inspector were to look at every document, the licensee may consider the inspector as a mere reviewer as he checks every document and the global quality of the documentation may decrease. In order to optimize the inspections, the inspection reports circulate among all the members of Bel V (inspectors and experts). Everyone is invited to comment these reports if he deems that the inspector should be made aware of an important issue, that the inspector should take a closer look at a certain aspect,.... These remarks help the inspector to prepare the next inspection. The slides of the presentation have been added at the end of the paper

  4. Comparison of Design and Practices for Radiation Safety among Five Synchrotron Radiation Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Liu, James C.; Rokni, Sayed H.; /SLAC; Asano, Yoshihiro; /JAERI-RIKEN, Hyogo; Casey, William R.; /Brookhaven; Donahue, Richard J.; /LBL, Berkeley

    2005-06-29

    There are more and more third-generation synchrotron radiation (SR) facilities in the world that utilize low emittance electron (or positron) beam circulating in a storage ring to generate synchrotron light for various types of experiments. A storage ring based SR facility consists of an injector, a storage ring, and many SR beamlines. When compared to other types of accelerator facilities, the design and practices for radiation safety of storage ring and SR beamlines are unique to SR facilities. Unlike many other accelerator facilities, the storage ring and beamlines of a SR facility are generally above ground with users and workers occupying the experimental floor frequently. The users are generally non-radiation workers and do not wear dosimeters, though basic facility safety training is required. Thus, the shielding design typically aims for an annual dose limit of 100 mrem over 2000 h without the need for administrative control for radiation hazards. On the other hand, for operational and cost considerations, the concrete ring wall (both lateral and ratchet walls) is often desired to be no more than a few feet thick (with an even thinner roof). Most SR facilities have similar operation modes and beam parameters (both injection and stored) for storage ring and SR beamlines. The facility typically operates almost full year with one-month start-up period, 10-month science program for experiments (with short accelerator physics studies and routine maintenance during the period of science program), and a month-long shutdown period. A typical operational mode for science program consists of long periods of circulating stored beam (which decays with a lifetime in tens of hours), interposed with short injection events (in minutes) to fill the stored current. The stored beam energy ranges from a few hundreds MeV to 10 GeV with a low injection beam power (generally less than 10 watts). The injection beam energy can be the same as, or lower than, the stored beam energy

  5. ESR/alanine dosimetry applied to radiation processing

    International Nuclear Information System (INIS)

    The radiation processing of food products is specified in terms of absorbed dose, and processing quality is assessed on the basis of absorbed dose measurements. The validity of process quality control is highly dependent on the quality of the measurements and associated instrumentation; in this respect, dosimetry calibration by an Organization with official status provides an essential guarantee of validity to the quality control steps taken. The Laboratoire de Metrologie des Rayonnements Ionisants (L.M.R.I.) is the primary standards and evaluation laboratory approved by the Bureau National de Metrologie (B.N.M.), which is the French National Bureau of Standards. The LMRI implements correlation procedures in response to the various requirements which arise in connection with high doses and doserates. Such procedures are mainly based on ESR/alanine spectrometry, a dosimetry technique ideally suited to that purpose. Dosemeter geometry and design are tailored to operating conditions. Photon dosemeters consist of a detector material in powder or compacted form, and a wall with thickness and chemical composition consistent with the application. Electron dosemeters have a detector core of compacted alanine with thickness down to a few tenths of a millimeter. The ESR/alanine dosimetry technique, developed at LMRI is a flexible, reliable and accurate tool which effectively meets the various requirements arising in the field of reference dosimetry, where high doses and doserates are involved. (author)

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

    International Nuclear Information System (INIS)

    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

  7. Nuclear safety and radiation protection report of the Cruas-Meysse nuclear facilities - 2014

    International Nuclear Information System (INIS)

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 111 and 112). Then, the nuclear safety and radiation protection measures taken regarding the facilities 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 any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  8. Nuclear safety and radiation protection report of the Civaux nuclear facilities - 2013

    International Nuclear Information System (INIS)

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 158 and 159). Then, the nuclear safety and radiation protection measures taken regarding the facilities 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 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

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

    International Nuclear Information System (INIS)

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 103, 104, 114 and 115). Then, the nuclear safety and radiation protection measures taken regarding the facilities 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 any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  10. Nuclear safety and radiation protection report of Blayais nuclear facilities - 2012

    International Nuclear Information System (INIS)

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 86 and 110). Then, the nuclear safety and radiation protection measures taken regarding the facilities 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 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  11. Nuclear safety and radiation protection report of the Nogent-sur-Seine nuclear facilities - 2013

    International Nuclear Information System (INIS)

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 129 and 130). Then, the nuclear safety and radiation protection measures taken regarding the facilities 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 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  12. Nuclear safety and radiation protection report of the Paluel nuclear facilities - 2013

    International Nuclear Information System (INIS)

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 103, 104, 114 and 115). Then, the nuclear safety and radiation protection measures taken regarding the facilities 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 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  13. Nuclear safety and radiation protection report of the Dampierre-en-Burly nuclear facilities - 2013

    International Nuclear Information System (INIS)

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 84 and 85). Then, the nuclear safety and radiation protection measures taken regarding the facilities 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 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

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

    International Nuclear Information System (INIS)

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 135 and 142). Then, the nuclear safety and radiation protection measures taken regarding the facilities 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 any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  15. Nuclear safety and radiation protection report of the Dampierre-en-Burly nuclear facilities - 2014

    International Nuclear Information System (INIS)

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 84 and 85). Then, the nuclear safety and radiation protection measures taken regarding the facilities 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 any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  16. On the strategy of the Republic of Tajikistan in the sphere of radiation safety

    International Nuclear Information System (INIS)

    Full text: Current situation. During the period of the USSR breakup, the radiation safety in the Republic of Tajikistan was not at the due level because of the secrecy of many problems. Population of Tajikistan practically was not informed about situation with the radiation safety around the tailing dumps of the Northern Tajikistan. In the 90 's of the past century, the infrastructure of the radiation safety of the RT was destroyed. At present, the strategy of the Republic of Tajikistan in the field of radiation safety for 2008-2015 is under development. There are 4 laws and 7 provisions on radiation safety in force in the Republic of Tajikistan. Aims and tasks of the Republic of Tajikistan in the sphere of radiation safety. The aim of the Republic of Tajikistan in the sphere of the radiation safety consists in creation of the highly efficient system in the sphere of RS. In order to achieve the aims of the strategy, it is proposed to resolve the following tasks: a) Conservation and re-cultivation of the uranium industry wastes; b) Strengthening the regulatory structure on the RS; c) Development and modernization of the radiotherapy and nuclear medicine; d) Development of the laboratories base on RS (at present, there is no control over the norms of RS); e) Production of a catalogue on the sites contaminated by radioactivity; f) Development of the map of the geo-pathogenous zones of the Republic; g) Reconstruction of the RCBRW; h) Physical protection of all the facilities using IRS; i) Issuing licenses in accordance with the Law of the Republic of Tajikistan 'On the Radiation Safety'; j) Transportation and burial of the spent RS; k) Personnel training and strengthening the materials and technological base. (author)

  17. Mobile phone radiation health risk controversy: the reliability and sufficiency of science behind the safety standards

    OpenAIRE

    Leszczynski Dariusz; Xu Zhengping

    2010-01-01

    Abstract There is ongoing discussion whether the mobile phone radiation causes any health effects. The International Commission on Non-Ionizing Radiation Protection, the International Committee on Electromagnetic Safety and the World Health Organization are assuring that there is no proven health risk and that the present safety limits protect all mobile phone users. However, based on the available scientific evidence, the situation is not as clear. The majority of the evidence comes from in ...

  18. A Quantitative Feasibility Study on Potential Safety Improvement Effects of Advanced Safety Features in APR-1400 when Applied to OPR-1000

    Energy Technology Data Exchange (ETDEWEB)

    Ualikhan Zhiyenbayev [KAIST, Daejeon (Korea, Republic of); Chung, Dae Wook [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-10-15

    This study aims to test the feasibility of the applications using Probabilistic Safety Assessment (PSA). Particularly, three of those advanced safety features are selected as follows: 1. Providing an additional Emergency Diesel Generator (EDG); 2. Increasing the capacity of Class 1E batteries; 3. Placing a Refueling Water Storage Tank (RWST) inside containment, i.e., change from RWST to IRWST. The Advanced Power Reactor 1400 (APR-1400) adopts several advanced safety features compared to its predecessor, the Optimized Power Reactor 1000 (OPR-1000), which includes an additional Emergency Diesel Generator, increase in battery capacity, in-containment refueling water storage tank (IRWST), and so on. Considering the remarkable advantages of these safety features in safety improvement and the design similarities between APR-1400 and OPR-1000, it is feasible to apply key advanced safety features of APR-1400 to OPR-1000 to enhance the safety. The selected safety features are incorporated into OPR-1000 PSA model using the Advanced Information Management System (AIMS) for PSA and CDFs are re-evaluated for each application and combination of three applications. Based on current results, it is concluded that three of key advanced safety features of APR-1400 can be effectively applied to OPR-1000, resulting in considerable safety improvement. In aggregate, three advanced safety features, which are an additional EDG, increased battery capacity and IRWST, can reduce the CDF of OPR-1000 by more than 15% when applied altogether.

  19. A safety assessment methodology applied to CNS/ATM-based air traffic control system

    International Nuclear Information System (INIS)

    In the last decades, the air traffic system has been changing to adapt itself to new social demands, mainly the safe growth of worldwide traffic capacity. Those changes are ruled by the Communication, Navigation, Surveillance/Air Traffic Management (CNS/ATM) paradigm , based on digital communication technologies (mainly satellites) as a way of improving communication, surveillance, navigation and air traffic management services. However, CNS/ATM poses new challenges and needs, mainly related to the safety assessment process. In face of these new challenges, and considering the main characteristics of the CNS/ATM, a methodology is proposed at this work by combining 'absolute' and 'relative' safety assessment methods adopted by the International Civil Aviation Organization (ICAO) in ICAO Doc.9689 , using Fluid Stochastic Petri Nets (FSPN) as the modeling formalism, and compares the safety metrics estimated from the simulation of both the proposed (in analysis) and the legacy system models. To demonstrate its usefulness, the proposed methodology was applied to the 'Automatic Dependent Surveillance-Broadcasting' (ADS-B) based air traffic control system. As conclusions, the proposed methodology assured to assess CNS/ATM system safety properties, in which FSPN formalism provides important modeling capabilities, and discrete event simulation allowing the estimation of the desired safety metric.

  20. Study of radiation safety conditions in different hospitals in Nepal

    International Nuclear Information System (INIS)

    Radiology in Nepal began in 1923, but the current date niguna no infrastructure in radiation protection to control the use of ionizing radiation in different areas. Only recently Nepal is part of the IAEA and this should be a support and an acceleration creating the right conditions. The purpose of this study was to determine the status of radiation protection in medicine. Due to the lack of regulation, monitoring or quality control, not even recommended.

  1. Radiation safety culture for developing country. Adoption of the minimum operational radiation protection programme in developing country

    International Nuclear Information System (INIS)

    The purpose for this document was to present some Itemization about the Minimum Radiation safety Requirements and an Integrated strategy Aiming at Establishing an Adequate Infrastructure for developing country, non major power reactor programme. The capacity for its implementation will allow these countries, about 50% of the IAEA's Member States, to improve marginal radiation protection, specially those recipients of technical assistance and do not meet the minimum requirements of the IAEA's Basic Safety Standards for Radiation Protection, reasonably progress in the implementation of safety regulations depends on the concept of priority of the government and its understanding and conviction about the basic requirements for protection against the risks associated with exposure to ionizing radiation. Considering the above assumption, there is no doubt to conclude that reasons for the deficiency of sources control and dose limitation in many countries, 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 among competent authorities in the country, dealing with similar type of licensing and inspection. (author)

  2. Automated Radiation Measurements for Aviation Safety (ARMAS) Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Commercial aircrew members and frequent flyers face radiation hazards from the effects of cosmic rays and solar energetic particles. During significant solar...

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

    International Nuclear Information System (INIS)

    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

  4. Study on dosimetric and radiation safety performance parameters of helical tomotherapy unit

    Institute of Scientific and Technical Information of China (English)

    Ma Yongzhong; Yang Bo; Feng Zechen; Wang Hongfang; Wan Ling

    2015-01-01

    Objective To understand the functional status and radiation protection requirements of helical tomotherapy (TOMO) unit when it is applied in clinic treatment so as to promote the construction of TOMO quality control system.Methods A helical tomotherapy unit with a type of tomotherapy Hi-Art was employed as the radiotherapy unit.A series of tests and analyses on dosimetric and radiation safety performance parameters of the TOMO unit were conducted with the use of a A1SL ionization chamber,a set of solid water equivalent phantoms and other test equipments.The performance parameters were compared with that of a conventional 6 MV accelerator with a type of ARTISTE.Results The deviations of static and dynamic output dose were-1.51% and 1.18%,respectively.The values of PDD10/PDD1.5 and PDD20/PDD1.5 were 0.608 and 0.318 within the range of X-ray quality parameters calibration.Under the different field conditions of 40 cm × 5 cm,40 cm × 2.5 cm and 40 cm × 1 cm,the stability of transverse/longitudinal dose distribution curve was no more than 1.20% and the offset distance of Jaw width was smaller than 0.5 mm.Radiation leakage ratio of the treatment rotating center from the muhileaf collimator (MLC) was 0.20%.No matter the average or the maximum value of the leakage radiation from couch plane was less than 0.02%.Conclusions The performances and testing requirements of TOMO unit are different from a conventional electron linear accelerator,the quality control index of TOMO unit should be set seperately and tested strictly in terms of the specific requirements of the unit by complying with the QC programme.The reliable quality control system should be established and effectively implemented to serve the radiotherapy quality and radiation safety effectively in the tomotherapy.

  5. ENSURING RADIATION SAFETY AT THE XXVII WORLD SUMMER UNIVERSIADE IN KAZAN BY ROSPOTREBNADZOR BODIES AND ORGANIZATIONS Communication 1. Ensuring radiation safety at the preparatory phase

    Directory of Open Access Journals (Sweden)

    G. G. Onischenko

    2013-01-01

    Full Text Available After the terrorist attack at theBostonMarathon, Federal and Republican executive bodies took increased security measures during the XXVII World Summer Universiade inKazan. Bodies and Organizations of the Federal Service for Surveillance on Consumer Rights Protection and Human Well-being (Rospotrebnadzor were participants of all preparatory activities and directly provided security of the Student Games inKazan. This report analyzes the experience of providing radiation safety by Rospotrebnadzor experts at the stage of preparation for the Universiade. So far, Rospotrebnadzor organizations had no experience of providing radiation safety of such large-scale events. Analysis of the performed work with account for both positive and negative experiences is especially important in the context of preparations for the safety providing of the Olympic Winter Games inSochiin 2014. 

  6. Importance of the Radiations Safety officer in the optimisation of occupational doses

    International Nuclear Information System (INIS)

    The decree 86-1103 of October 2 1986, relating to the protection of the health of workers and the general public against the dangers arising from ionizing radiation, describes the function and the tasks of radiation safety officers. In article 17, we can read In any institution concerned by this present decree, handling and use of radioactive sources or electrical generator, of ionizing radiation, shall always be carried out under the surveillance of a RADIATION SAFETY OFFICER. This officer is designated by the employer and has attended a radiation protection course successfully. This radiation protection course consists in a few days course given by a registered institution. Health institutions are concerned by this decree just like any company, except nuclear power plant. (Author)

  7. Sports injuries, drowning and exposure to radiation concern Canada Safety Council meeting

    International Nuclear Information System (INIS)

    Hazards associated with surface sports, aquatic sports and exposure to radiation were considered at a meeting of the Canada Safety Council in late 1979. The session on radiation noted that 6 of 20000 radiation workers wearing dosimeters were exposed to a dose in excess of 5 rem, the annual limit set by the Atomic Energy Control Board. Radiographers were in the job classification receiving the highest doses of ionizing radiation. Concern was expressed for the emission of damaging radiation from broken mercury vapour lamps. Increased regulation rather than training was seen as the most effective solution. (T.I.)

  8. IAEA safety glossary. Terminology used in nuclear, radiation, radioactive waste and transport safety. Version 1.0. Working material

    International Nuclear Information System (INIS)

    The IAEA safety standards for nuclear installations, radiation protection, radioactive waste management and the transport of radioactive materials have been historically developed in four separate programmes, each of them developing its own terminology. The purpose was to explain the meaning of technical terms that might be unfamiliar to a reader; to explain any special meanings assigned to common words or terms and to define precisely how terms are used in particular publications to avoid ambiguity concerning some important aspects of their meaning. It is intended primarily to provide guidance to the drafters and reviewers of Agency safety related publications, including IAEA Technical officers, consultants and members of Technical Committees, Advisory Groups and safety standards advisory bodies. It is also likely to be a useful source of information for other Agency staff, notably editors and translators, and for external users of IAEA safety related publications

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

    International Nuclear Information System (INIS)

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

  10. General radiation hygiene and safety aspects in dental radiography

    International Nuclear Information System (INIS)

    A presentation of all essential aspects concerning practical radiation hygiene in dental radiography is given. The report reflects the established opinion and practice of the National Institute of Radiation Hygiene evolved through many years of experience in this field. The principal target group includes all dental staff members in Norway

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

    International Nuclear Information System (INIS)

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

  12. The radiation safety information computational center (RSICC) - Forty years of nuclear knowledge management

    International Nuclear Information System (INIS)

    Established in 1962, RSICC has seen 40 years of research and growth in the areas of radiation transport, radiation shielding, and radiation safety. During this period, the use of computers was initiated and RSICC has been innovative in the knowledge management of the products (software and data) developed within the user community. RSICC technology base includes about 1400 computer codes and about 300 data packages, representing the legacy of many scientists, both living and dead. Over the years, more than 5000 scientists have used the center at one time or another. Today, the number of registered users is close to 5000. Through software and data dissemination, RSICC has served as the focal point for this network of researchers, and promoted the exchange and enhancement of technology. In 1994, RSIC was changed to Radiation Safety Information Computational Center (RSICC), a change that was dictated by wider application of RSICC's software collection and rapidly moving Internet technology. RSICC's mission is to provide in-depth coverage of the radiation transport field to meet the needs of the international shielding community. RSICC collects, organizes, evaluates and disseminates technical information involving shielding and protection from the radiation associated with fission and fusion reactors, outer space, accelerators, weapons, medical facilities, and nuclear waste management. The Center provides in-depth coverage of radiation transport topics: - Radiation production and sources, - Criticality safety, - Radiation protection and shielding, - Radiation detectors and measurements, - Shielding materials properties, - Radiation waste management, - Shields and shipping cask design, - Radiation safety and assessment, - Atmospheric dispersion and environmental dose, - The physics of the interaction of radiation with matter. In support of a number of government-sponsored programs, RSICC - Collects, maintains, analyzes, and distributes technical computing software in

  13. Post-graduate course on radiation protection and nuclear safety. Vol. 1,2

    International Nuclear Information System (INIS)

    The course handbook on radiation protection and nuclear safety containing two parts some was prepared mainly by scientists of the Nuclear Regulatory Authority (ARN) of the Argentine Republic, under the auspices of the International Atomic Energy Agency. The contents o this handbook have the principals aspects: radiation detection, radio dosimetry, biological effects of the ionizing radiation, occupational exposure, environmental effects, contamination and decontamination, radioactive waste management, transport of radioactive materials, medical and industrial applications and the Argentine regulatory system

  14. Training requirements for persons with specific radiation safety roles defined in United Kingdom legislation

    International Nuclear Information System (INIS)

    This article describes the respective roles of key persons who have specific responsibilities under United Kingdom (UK) legislation for ensuring that work with sources of ionising radiation is undertaken safely. It also considers the training requirements for these people and how they are typically addressed. Particular focus is placed on the roles of persons who directly supervise work with ionising radiation and the qualified experts who provide advice on radiation protection legislation and safety requirements. (orig.)

  15. Proceedings of the 9th annual meeting of Japanese Society of Radiation Safety Management 2010 Hiroshima

    International Nuclear Information System (INIS)

    This is the entitled program and proceedings held from December 1st through 3rd of 2010. The sessions including poster, invited/special speeches etc. are exposure reduction and dose level evaluation, shielding design, radioactive waste handling and its effective use, radiation measurement, safety control of radiation source, radioactive waste management (aerosol, liquid), education on radiation, molecular imaging, image analysis, radioactivity in environment, contamination inspection. (J.P.N)

  16. The radiation techniques of tomotherapy & intensity-modulated radiation therapy applied to lung cancer

    OpenAIRE

    Zhu, Zhengfei; Fu, Xiaolong

    2015-01-01

    Radiotherapy (RT) plays an important role in the management of lung cancer. Development of radiation techniques is a possible way to improve the effect of RT by reducing toxicities through better sparing the surrounding normal tissues. This article will review the application of two forms of intensity-modulated radiation therapy (IMRT), fixed-field IMRT and helical tomotherapy (HT) in lung cancer, including dosimetric and clinical studies. The advantages and potential disadvantages of these t...

  17. Research projects of the Finnish Centre for Radiation and Nuclear Safety 1996-1997

    International Nuclear Information System (INIS)

    The research activities of the Finnish Centre for Radiation and Nuclear Safety (STUK) are based on the Centre's primary task of preventing and restricting adverse effects of radiation. As a rule, studies concerning nuclear safety (part 1 of the publication) are studies originating from the regulatory function of STUK; these are directed and funded by the Centre but the Centre does not carry them out itself. In contrast, studies dealing with radiation exposure and health risks (part 2 of the publication) are conducted by the Centre itself, often in cooperation with some other research institute or university. Results of these studies are published in open scientific literature

  18. Radiation safety infrastructure in developing countries: a proactive approach for integrated and continuous improvement

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (the Agency) is authorized, by its statute, to establish or adopt safety standards for the protection of health and minimization of danger to life and property, and to provide for their application to its own operations as well as to operations under its control or supervision. The Agency has been assisting, since the mid 1960's, its Member States through mainly its Technical Cooperation Programme (TCP) to improve their national radiation safety infrastructures. However up to the early nineties, assistance was specific and mostly ad hoc and did not systematically utilize an integrated and harmonized approach to achieving effective and sustainable national radiation safety infrastructures in Member States. An unprecedented and integrated international cooperative effort was launched by the Agency in 1994 to establish and/or upgrade the national radiation safety infrastructure in more than 90 countries within the framework of its TCP through the so-called Model Project on Upgrading Radiation Protection Infrastructure. In this project proactive co-operation with Member States was used in striving towards achieving an effective and sustainable radiation safety infrastructure, compatible with the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the BSS) and related standards. Extension to include compatibility with the guidance of the Code of Conduct on the Safety and Security of Radioactive Sources occurred towards the end of the Model Project in December 2004, and with the more recent ensuing follow up projects that started in 2005. The Model Project started with 5 countries in 1994 and finished with 91 countries in 2004. Up to the end of 2007 more than one hundred Member States had been participating in follow up projects covering six themes - namely: legislative and regulatory infrastructure; occupational radiation protection; radiation protection in medical

  19. Report on administrative work at radiation safety center in fiscal year 2000

    Energy Technology Data Exchange (ETDEWEB)

    Uda, Tatsuhiko; Sakuma, Yoichi; Kawano, Takao; Yamanishi, Hirokuni; Shinotsuka, Kazunori; Asakura, Yamato; Miyake, Hitoshi

    2002-05-01

    National Institute for Fusion Science constructed Large Helical Device (LHD) which is the largest magnetic confinement plasma experimental device using super conductive magnet coils. It took eight years to construct and the first plasma shot had been carried out on March 1998. Since then plasma confinement experiments have been improved. This is the report of administrative work at the radiation safety center considering radiation protection for workers at the LHD and related devices, and radiation monitoring in the site. Major scope is as follows. (1) Radiation measurement and dose monitoring in the radiation controlled area and in the site using particularly developed monitoring system named as Radiation Monitoring System Applicable to Fusion Experiments (RMSAFE). (2) Establishment of education and registration system for radiation workers and access control system for the LHD controlled area. I hope that as like the published report of fiscal year 1999, the present report will be helpful for management of future radiation protection in the research institute. (author)

  20. Some elementary concepts of radiation health and safety in underground uranium mines

    International Nuclear Information System (INIS)

    Some elementary concepts of radiation health and safety in underground uranium mines are discussed. This report reviews the main radiation sources which contribute to the contamination of mine atmospheres and hence to the exposure of mine workers. A brief discussion of the biological effects of ionizing radiation, with special reference to radon and its progeny, is followed by the introduction of the presently accepted radiation indexes for radiation hazard (WL) and radiation exposure (WLM). Finally, a succinct review of the available techniques for radiation control and monitoring in underground uranium mines is complemented by a discussion of various methods of personnel radiation protection, including the use of respirators, job rotation, personnel dosimetry and medical surveillance

  1. Law on protection against ionising radiation and nuclear safety in Slovenia

    International Nuclear Information System (INIS)

    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)

  2. Plus 90 and counting: Countries rise to the challenge of radiation safety

    International Nuclear Information System (INIS)

    Full text: Radiation science is the source of tools and technologies that help to address some of the most pressing issues of our times - human health, food and agriculture, industry, energy and environmental management. In many cases, the data and information gathered by applying radiation-based technologies simply cannot be obtained through any other means. Nor can the impressive results. Consider these figures. On average, over 25 million nuclear imaging procedures are carried out per year around the world to diagnose disease; annually, almost 10 million people benefit from radiopharmaceuticals (radioactive drugs), often in the context of cancer treatment. At the same time, advanced molecular and radioisotope techniques are being used to develop more effective measures to combat infectious diseases such as malaria, hepatitis, and tuberculosis. Techniques to fortify staple food crops provide vital nutrients to populations that have enough to eat, but lack the variety needed to be well-nourished. The ability to eliminate harmful bacteria and pests from the surface of raw produce enhances storage and transport - and opens opportunities to export markets. Radiation-based technologies, many of which have proven effective over decades of use in the developed world, now contribute to virtually every sector of society. In keeping with the underlying principles of the United Nations, the IAEA is committed to ensuring that all of its Member States have equal access to the advantages offered by these powerful tools. In return, the States must accept the responsibility for protecting the public and the environment from radiation exposure. Yet about once every other day, authorities at one of the world's busiest ports Rotterdam in The Netherlands detect radioactive material in shipments of scrap metal coming through their docks. Mostly the sources of radiation are pieces of old hospital equipment or industrial instruments that do not pose high health risks. The scrap metal

  3. Proceedings of the 6. Argentine congress on radiation protection and nuclear safety

    International Nuclear Information System (INIS)

    The 6th Argentine Congress on Radiation Protection and Nuclear Safety was organized by the Radioprotection Argentine Society, in Buenos Aires, between the 22 and 24 of september of 1998. In this event, were presented almost 66 papers in the following sessions, about these subjects: 1.- Safety in nuclear installations. 2.- Control of nuclear material and physical protection of nuclear installations. 3.- Programs of quality assurance. 4.- Training, technical information and public information. 5.- Physical dosimetry. 6.- Physical dosimetry and occupational radiation protection. 7.- Exposure of the natural radiation. 8.- Environmental radiological safety. 9.- Biological effects of the ionizing radiations and biological dosimetry. 10.- Radiological protection of the medical practice and the radiological emergencies. 11.- Radioactive wastes management. 12.- Transport of radioactive materials

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

    Science.gov (United States)

    Lewis, Robert K

    2016-10-01

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

  5. Proceedings of the 5th annual meeting of Japanese Society of Radiation Safety Management 2006 Nagoya

    International Nuclear Information System (INIS)

    This is the program and the proceedings of the 5th annual meeting of Japanese Society of Radiation Safety Management held from November 29th through December 1st of 2006. The sessions held are: (1) Radiation Measurement 1, (2) Education Method, (3) Radiation Control, (4) Waste Handling, Contamination Inspection, and Renewal, (5) Exposure Reduction, Radiation Evaluation, and Radioactivity Control (6) Radiation Measurement 2, (7) Operation Environment, (8) Medical Exposure, (9) Radiation Measurement 3, (10) Software, IT Technology, and Data Processing, (11) Emission and Drainage Handling, and (12) Radiation Effect and Contamination Countermeasure. The poster sessions held are: (1) Radiation Measurement, (2) Environmental Radiation, (3) Scattering Rate, Penetration Rate, and Contamination Inspection, (4) Education Method, (5) Medical Exposure, (6) Access Control and Software, and (7) Radiation Control Method and Monitoring. The symposia held are: (1) 'Toward Establishment of Guideline for Safe X-ray Handling Education' and 'International Situation of Radiation Safety'. 2 keynote lectures were also held. (S.K.)

  6. Radiation safety estimation for a new radiation shielding system of Co-60 irradiator of the IIIA, Cuba

    International Nuclear Information System (INIS)

    New design of the radiation shielding system of IIIA irradiator was simulated using MCNP code. Exposure doses inside the irradiator on goods maze and outside the irradiator were calculated by both analytical solution of the radiation transport equation and MCNP simulation. The results show a good agreement between the two methods. The result illustrated that the new design of IIIA irradiator has been covered radiation safety. Dose rates at loading and un-loading stations are smaller than 1.0 µSv/h, and that at outside irradiator is about 0.5 µSv/h. (author)

  7. EDF - The Inspector General's report on Nuclear Safety and Radiation Protection 2012

    International Nuclear Information System (INIS)

    After a first chapter in which the Inspector General states his own vision of facts and results regarding nuclear safety and radiation protection for 2012, the next chapters address the following topics: the contrasted results of nuclear operating safety, the need to remain vigilant in nuclear safety management, the challenge of occupational safety, the need of new ambitious goals for radiation protection, an updated training which must be better led by line management, maintenance as a strategic issue, the long road ahead for nuclear technical information system (SDIN), the need of better attention to chemistry in operations, the new impetus of EPRs, plant life extension conditioned by nuclear safety, the mobilization of nuclear operators after Fukushima, and noteworthy operating events

  8. Feasibility study of applying the passive safety system concept to fusion–fission hybrid reactor

    International Nuclear Information System (INIS)

    The fusion–fission hybrid reactor can produce energy, breed nuclear fuel, and handle the nuclear waste, etc., with the fusion neutron source striking the subcritical blanket. The passive safety system consists of passive residual heat removal system, passive safety injection system and automatic depressurization system was adopted into the fusion–fission hybrid reactor in this paper. Modeling and nodalization of primary loop, partial secondary loop and passive core cooling system for the fusion–fission hybrid reactor using relap5 were conducted and small break LOCA on cold leg was analyzed. The results of key transient parameters indicated that the actuation of passive safety system could mitigate the accidental consequence of the 4-inch cold leg small break LOCA on cold leg in the early time effectively. It is feasible to apply the passive safety system concept to fusion–fission hybrid reactor. The minimum collapsed liquid level had great increase if doubling the volume of CMTs to increase its coolant injection and had no increase if doubling the volume of ACCs

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

    International Nuclear Information System (INIS)

    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

  10. [Risk Analysis applied to food safety in Brazil: prospects and challenges].

    Science.gov (United States)

    Figueiredo, Ana Virgínia de Almeida; Miranda, Maria Spínola

    2011-04-01

    The scope of this case study is to discuss the ideas of the Brazilian Codex Alimentarius Committee (CCAB) coordinated by National Institute of Metrology, Standardization and Industrial Quality (Inmetro), with respect to the Codex Alimentarius norm on Risk Analysis (RA) applied to Food Safety. The objectives of this investigation were to identify and analyze the opinion of CCAB members on RA and to register their proposals for the application of this norm in Brazil, highlighting the local limitations and potential detected. CCAB members were found to be in favor of the Codex Alimentarius initiative of instituting an RA norm to promote the health safety of foods that circulate on the international market. There was a consensus that the Brazilian government should incorporate RA as official policy to improve the country's system of food control and leverage Brazilian food exports. They acknowledge that Brazil has the technical-scientific capacity to apply this norm, though they stressed several political and institutional limitations. The members consider RA to be a valid initiative for tackling risks in food, due to its ability to improve food safety control measures adopted by the government.

  11. Automated Radiation Measurements for Aviation Safety (ARMAS) Project

    Data.gov (United States)

    National Aeronautics and Space Administration — The existing state-of-the-art for physics-based, data-driven, climatological specification of the global radiation environment is the capability embodied by Nowcast...

  12. Radiation safety knowledge and practices among Irish orthopaedic trainees.

    LENUS (Irish Health Repository)

    Nugent, M

    2014-04-23

    Fluoroscopy is frequently used in orthopaedic surgery, particularly in a trauma setting. Exposure of patients and staff to ionising radiation has been studied extensively; however, little work has been done to evaluate current knowledge and practices among orthopaedic trainees.

  13. Sequential procedure for the design of checklists applied to the patient safety

    Directory of Open Access Journals (Sweden)

    Pardal-Refoyo JL

    2014-07-01

    Full Text Available Introduction: Checklists are cognitive mnemonic aid to guide in performing complex tasks under stress or fatigue, reduce errors of omission and identify critical incidents function. There is a lack of specific methodological aid for their processing. Objective: The aim of the study was to design a structured development of checklists applied to patient safety process (PS. Material and methods: Systematic review. Ten papers were selected, five related to the structure of the checklists, three related to PS research methods (root cause analysis -RCA- and failure mode and effects analysis -FMEA-, one related to construction indicators and one with consensus methods. Results: A sequential process in 15 steps was designed to help the development of LV applied to the SP collecting elements proposed in the literature reviewed. Conclusions: The development of LV SP applied to a particular process should follow a sequential model which includes the literature review, the ACR and FMEA methods and consensus.

  14. The radiation measurement applied to beam lifetime study on the synchrotron radiation facilities

    Science.gov (United States)

    Li, Yuxiong; Li, Juexin; Liu, Zuping; Cui, Yonggang; Gong, Guanghua; Shao, Beibei

    2003-06-01

    To collect beam loss information from an accelerator radiation field is helpful to machine study and operation. For a synchrotron radiation storage ring, shower electrons give a distinct clue to loss location and a BLM-XS model detector is suitable to detect them. Recently, we set up a new beam loss monitoring system by this method for National Synchrotron Radiation Laboratory (NSRL) storage ring. It does not interfere with the vacuum chamber and machine operation. Different from other systems, the detectors are used in pairs, fixed on opposite sides of the chamber separately. Some interesting phenomena about beam lifetime were observed. We located exactly where an excessive beam loss took place during ramping process and solved the problem. It was proved that gas accumulated at the front ends of photo-beam lines strongly impacted the electron beam and led to beam lifetime decreases. The cause of beam lifetime decrease because of superconducting wiggler is discussed.

  15. The Revised International Basic Safety Standards and Their Potential Impact on Radiation Protection in Medicine

    International Nuclear Information System (INIS)

    The Revised International Basic Safety Standards (international BSS) were published as an interim edition in November 2011. The international BSS cover radiation protection in all uses of radiation and have an important role in many countries, especially in the developing world. Issues of particular relevance for the next decade, addressed in the international BSS include responsibilities for patient radiation protection, justification for medical exposure of individual patients, imaging of asymptomatic individuals for the early detection of disease, software that can influence the delivery of medical exposure, diagnostic reference levels, voluntary safety reporting systems, radiological reviews, personal monitoring and the dose limit for the lens of the eye. The international BSS should provide an effective regulatory basis for radiation protection in medicine for the next decade, but effective implementation is needed. Further, the international BSS not only set the basic requirements but also provide the foundation for enabling additional actions to continuously improve radiation protection in medicine. (author)

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

    International Nuclear Information System (INIS)

    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)

  17. Attitude of the Korean dentists towards radiation safety and selection criteria

    International Nuclear Information System (INIS)

    X-ray exposure should be clinically justified and each exposure should be expected to give patients benefits. Since dental radiographic examination is one of the most frequent radiological procedures, radiation hazard becomes an important public health concern. The purpose of this study was to investigate the attitude of Korean dentists about radiation safety and use of criteria for selecting the frequency and type of radiographic examinations. The study included 267 Korean dentists. Five questions related to radiation safety were asked of each of them. These questions were about factors associated with radiation protection of patients and operators including the use of radiographic selection criteria for intraoral radiographic procedures. The frequency of prescription of routine radiographic examination (an example is a panoramic radiograph for screening process for occult disease) was 34.1%, while that of selective radiography was 64.0%. Dentists' discussion of radiation risk and benefit with patients was infrequent. More than half of the operators held the image receptor by themselves during intraoral radiographic examinations. Lead apron/thyroid collars for patient protection were used by fewer than 22% of dental offices. Rectangular collimation was utilized by fewer than 15% of dental offices. The majority of Korean dentists in the study did not practice radiation protection procedures which would be required to minimize exposure to unnecessary radiation for patients and dental professionals. Mandatory continuing professional education in radiation safety and development of Korean radiographic selection criteria is recommended.

  18. Attitude of the Korean dentists towards radiation safety and selection criteria

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Do [Dept. of Oral and Maxillofacial Radiology and Wonkwang Dental Research Institute, College of Dentistry, Wonkwang University, Iksan (Korea, Republic of); Ludlow, John B. [Graduate Program in Oral and Maxillofacial Radiology, School of Dentistry, University of North Carolina, Chapel Hill (United States)

    2013-09-15

    X-ray exposure should be clinically justified and each exposure should be expected to give patients benefits. Since dental radiographic examination is one of the most frequent radiological procedures, radiation hazard becomes an important public health concern. The purpose of this study was to investigate the attitude of Korean dentists about radiation safety and use of criteria for selecting the frequency and type of radiographic examinations. The study included 267 Korean dentists. Five questions related to radiation safety were asked of each of them. These questions were about factors associated with radiation protection of patients and operators including the use of radiographic selection criteria for intraoral radiographic procedures. The frequency of prescription of routine radiographic examination (an example is a panoramic radiograph for screening process for occult disease) was 34.1%, while that of selective radiography was 64.0%. Dentists' discussion of radiation risk and benefit with patients was infrequent. More than half of the operators held the image receptor by themselves during intraoral radiographic examinations. Lead apron/thyroid collars for patient protection were used by fewer than 22% of dental offices. Rectangular collimation was utilized by fewer than 15% of dental offices. The majority of Korean dentists in the study did not practice radiation protection procedures which would be required to minimize exposure to unnecessary radiation for patients and dental professionals. Mandatory continuing professional education in radiation safety and development of Korean radiographic selection criteria is recommended.

  19. Proceedings of the 4th annual meeting of Japanese Society of Radiation Safety Management 2005 Kyoto

    International Nuclear Information System (INIS)

    This is the program and the proceedings of the 4th annual meeting of Japanese Society of Radiation Safety Management held from November 23rd through the 25th of 2005. The sessions held were: (1) Medical Exposure, (2) Environmental Measurement and Radiation Source Handling, (3) Radiation Measurement and Influence of Electromagnetic Waves, (4) Utilization of Irradiation, (5) Countermeasures against Contamination and Inspection of Contamination, (6) Imaging Plate, (7) Controlled Measurement and Dose Evaluation, (8) Working Environment Measurement 1, (9) Working Environment Measurement 2, (10) Establishment of Software and System, (11) Radiation Education 1, (12) Radiation Education 2, and (13) Exposure Reduction and Safety Control. The poster sessions held were: (1) Exposure Reduction and Radiation Evaluation, (2) Radiation Measurement and Influence of Electromagnetic Waves, (3) Education Training, (4) Safety Control, (5) Software, Data Handling, and Shielding Calculation, and (6) Environmental Radioactivity. The keynote lectures held were: (1) 'Situation of Medical Exposure' and (2) 'Cosmic Radiation While Boarding on Airplanes'. The symposia held were: (1) 'Food Irradiation' and (2) 'Life Science'. (S.K.)

  20. Use of information technologies to contribute for optimizing the safety radiation management in Cuba

    International Nuclear Information System (INIS)

    This paper presents the results achieved in Cuba, with the development of a group of information management tools to implement radiation safety systemic and proactive approaches to safety and ICT supported. These tools were designed for different organisms with responsibility for the security at the country level, to the regulatory authority, for user entities, for individual monitoring services and other radiation protection services. It describes the philosophy of information management model used, the characteristics of the developed tools and their integration, the work performed for the homogenization of information available and the ability to capture and deliver data at different levels in decision making. The tools developed are based on the use of variables and indicators of importance to the safety and the systemic approach adopted allows to facilitate the optimization process for supervision of safety practices as well as contribute to the management of knowledge in radiation safety, through a synergistic combination of process data, information, information management systems, and the creative and innovative radiation safety experts

  1. Promoting radiation protection and safety for X-ray inspection systems

    International Nuclear Information System (INIS)

    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)

  2. Promoting radiation protection and safety for x-ray inspection systems

    International Nuclear Information System (INIS)

    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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Pavlovitchev, A.M.

    2001-09-28

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

  4. Mobile phone radiation health risk controversy: the reliability and sufficiency of science behind the safety standards

    Directory of Open Access Journals (Sweden)

    Leszczynski Dariusz

    2010-01-01

    Full Text Available Abstract There is ongoing discussion whether the mobile phone radiation causes any health effects. The International Commission on Non-Ionizing Radiation Protection, the International Committee on Electromagnetic Safety and the World Health Organization are assuring that there is no proven health risk and that the present safety limits protect all mobile phone users. However, based on the available scientific evidence, the situation is not as clear. The majority of the evidence comes from in vitro laboratory studies and is of very limited use for determining health risk. Animal toxicology studies are inadequate because it is not possible to "overdose" microwave radiation, as it is done with chemical agents, due to simultaneous induction of heating side-effects. There is a lack of human volunteer studies that would, in unbiased way, demonstrate whether human body responds at all to mobile phone radiation. Finally, the epidemiological evidence is insufficient due to, among others, selection and misclassification bias and the low sensitivity of this approach in detection of health risk within the population. This indicates that the presently available scientific evidence is insufficient to prove reliability of the current safety standards. Therefore, we recommend to use precaution when dealing with mobile phones and, whenever possible and feasible, to limit body exposure to this radiation. Continuation of the research on mobile phone radiation effects is needed in order to improve the basis and the reliability of the safety standards.

  5. Radiation safety and culture of prevention in the use of radioactive materials in industry : criteria and trends

    International Nuclear Information System (INIS)

    As time goes by and experience is gained, modernization and technological development show the need to implement more complex programs and procedures to ensure a high level of compliance with radiation safety, particularly in those activities in which radioactive material is used in industry. A relevant aspect of present technology is the concern to introduce mechanisms to prevent radiological accidents or incidents, to ensure early detection of failures. This includes systems that either individually or as a whole, increase the level of responsibility of the different disciplines involved, so as to avoid a situation that could lead to loss of control of the facility or part of it. The prevention of an abnormal situation, overexposure of workers or unwanted risks, should be considered in the level of vulnerability of the facility, a concept drawn from international protection systems and which is applied directly in radiation safety. Preventive management, risk communication and proposals for change or improvement along with the detection of risks and training, constitute all the factors contained within prevention policies. Dose limitation, optimization and justification, old tools used for decades, could not be replaced by other modern concepts and criteria. ALARA culture (including performance indicators) should be considered. The atmosphere at work, working under pressure as well as other factors such as quality issues, ethics of prevention, etc. align with this idea of prevention and safety, besides changes in attitude, towards risk prevention (methods, reports, intervention guides, working instructions, and any other helpful tool), are followed by preventive, as well as predictive and corrective maintenance, applied to minimize the dose absorbed by workers. A clear policy of prevention is needed as well as an appropriate level of radiation safety which should be taken into account since the very beginning of the development of a given practice. All these

  6. Radiation Safety and Culture of Prevention in the Use of Radioactive Materials in Industry. Criteria and Trends

    International Nuclear Information System (INIS)

    As time goes by and experience is gained, modernization and technological development show the need to implement more complex programs and procedures to ensure a high level of compliance with radiation safety, particularly in those activities in which radioactive material is used in industry. A relevant aspect of present technology is the concern to introduce mechanisms to prevent radiological accidents or incidents, to ensure early detection of failures. This includes systems that either individually or as a whole, increase the level of responsibility of the different disciplines involved, so as to avoid a situation that could lead to loss of control of the facility or part of it. The prevention of an abnormal situation, overexposure of workers or unwanted risks, should be considered in the level of vulnerability of the facility, a concept drawn from international protection systems and which is applied directly in radiation safety. Preventive management, risk communication and proposals for change or improvement along with the detection of risks and training, constitute all the factors contained within prevention policies. Dose limitation, optimization and justification, old tools used for decades, could not be replaced by other modern concepts and criteria. ALARA culture (including performance indicators) should be considered. The atmosphere at work, working under pressure as well as other factors such as quality issues, ethics of prevention, etc. align with this idea of prevention and safety, besides changes in attitude, towards risk prevention (methods, reports, intervention guides, working instructions, and any other helpful tool), are followed by preventive, as well as predictive and corrective maintenance, applied to minimize the dose absorbed by workers. A clear policy of prevention is needed as well as an appropriate level of radiation safety which should be taken into account since the very beginning of the development of a given practice. All these

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

    Energy Technology Data Exchange (ETDEWEB)

    Lacroix, M. [Canadian Irradiation Center, Research Laboratory in Sciences Applied to Food, INRS-Institut Armand-Frappier, 531 Boulevard des Prairies, Laval, Quebec (Canada)], E-mail: monique.lacroix@iaf.inrs.ca; Turgis, M. [Canadian Irradiation Center, Research Laboratory in Sciences Applied to Food, INRS-Institut Armand-Frappier, 531 Boulevard des Prairies, Laval, Quebec (Canada); Borsa, J. [MDS Nordion, 447 March Road, Kanata, Ontario, K2K 2P7 (Canada); Millette, M.; Salmieri, S.; Caillet, S. [Canadian Irradiation Center, Research Laboratory in Sciences Applied to Food, INRS-Institut Armand-Frappier, 531 Boulevard des Prairies, Laval, Quebec (Canada); Han, J. [Sungkyunkwan University, Department of Food Science and Biotechnology, Suwon 440-746 (Korea, Republic of)

    2009-11-15

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

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

    International Nuclear Information System (INIS)

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

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

    Science.gov (United States)

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

    2009-11-01

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

  10. Safety and regulatory aspects of radiation processing facilities in India

    International Nuclear Information System (INIS)

    The number of gamma and electron radiation processing facilities (RPFs) is increasing all over the world. This is mainly due to their multifarious applications in the field of medicine, industry, agriculture and research. The most wide spread use of these facilities are for sterilisation of medical and pharmaceutical products, preservation of food stuffs, polymer synthesis and modifications, eradication of insect infestation and in the management of public health and environment. In India, at present, a total of nineteen gamma radiation-processing facilities (GRAPFs) are under operation for various purposes, four are under construction and several facilities have obtained site clearance for installation of GRAPF. There are five radiation processing accelerator (RPA) facilities operating in the country for other than food irradiation purposes. The ISOMED, the first commercial gamma radiation processing plant for sterilisation of medical products was commissioned at the Bhabha Atomic Research Centre (BARC), Mumbai in 1974 by the Department of Atomic Energy (DAE), Government of India. The regulatory controls have been briefly outlined in this article

  11. Systems Engineering and Safety Issues in Scientific Facilities Subject to Ionizing Radiations

    Directory of Open Access Journals (Sweden)

    Pierre Bonnal

    2013-10-01

    Full Text Available The conception and development of large- scale scientific facilities emitting ionizing radiations rely more on project management practices in use in the process industry than on systems engineering practices. This paper aims to highlight possible reasons for this present situation and to propose some ways to enhance systems engineering so that the specific radiation safety requirements are considered and integrated in the approach. To do so, we have reviewed lessons learned from the management of large-scale scientific projects and more specifically that of the Large Hadron Collider project at CERN. It is shown that project management and systems engineering practices are complementary and can beneficially be assembled in an integrated and lean managerial framework that grants the appropriate amount of focus to safety and radiation safety aspects.

  12. A Methods and procedures to apply probabilistic safety Assessment (PSA) techniques to the cobalt-therapy process. Cuban experience

    International Nuclear Information System (INIS)

    This paper presents the results of the Probabilistic Safety Analysis (PSA) to the Cobalt Therapy Process, which was performed as part of the International Atomic Energy Agency's Coordinated Research Project (CRP) to Investigate Appropriate Methods and Procedures to Apply Probabilistic Safety Assessment (PSA) Techniques to Large Radiation Sources. The primary methodological tools used in the analysis were Failure Modes and Effects Analysis (FMEA), Event Trees and Fault Trees. These tools were used to evaluate occupational, public and medical exposures during cobalt therapy treatment. The emphasis of the study was on the radiological protection of patients. During the course of the PSA, several findings were analysed concerning the cobalt treatment process. In relation with the Undesired Events Probabilities, the lowest exposures probabilities correspond to the public exposures during the treatment process (Z21); around 10-10 per year, being the workers exposures (Z11); around 10-4 per year. Regarding to the patient, the Z33 probabilities prevail (not desired dose to normal tissue) and Z34 (not irradiated portion to target volume). Patient accidental exposures are also classified in terms of the extent to which the error is likely to affect individual treatments, individual patients, or all the patients treated on a specific unit. Sensitivity analyses were realised to determine the influence of certain tasks or critical stages on the results. As a conclusion the study establishes that the PSA techniques may effectively and reasonably determine the risk associated to the cobalt-therapy treatment process, though there are some weaknesses in its methodological application for this kind of study requiring further research. These weaknesses are due to the fact that the traditional PSA has been mainly applied to complex hardware systems designed to operate with a high automation level, whilst the cobalt therapy treatment is a relatively simple hardware system with a

  13. Applying Qualitative Hazard Analysis to Support Quantitative Safety Analysis for Proposed Reduced Wake Separation Conops

    Science.gov (United States)

    Shortle, John F.; Allocco, Michael

    2005-01-01

    This paper describes a scenario-driven hazard analysis process to identify, eliminate, and control safety-related risks. Within this process, we develop selective criteria to determine the applicability of applying engineering modeling to hypothesized hazard scenarios. This provides a basis for evaluating and prioritizing the scenarios as candidates for further quantitative analysis. We have applied this methodology to proposed concepts of operations for reduced wake separation for closely spaced parallel runways. For arrivals, the process identified 43 core hazard scenarios. Of these, we classified 12 as appropriate for further quantitative modeling, 24 that should be mitigated through controls, recommendations, and / or procedures (that is, scenarios not appropriate for quantitative modeling), and 7 that have the lowest priority for further analysis.

  14. Information report on nuclear safety and radiation protection of the ECRIN INB - Issue 2014

    International Nuclear Information System (INIS)

    Published in compliance with the French code of the environment, this report first presents the Malvesi establishment, the ECRIN basic nuclear installation (INB), the COMURHEX II project, and the policy for a sustainable development and continuous progress of this establishment. It describes the various measures regarding nuclear safety and radiation protection: nuclear safety, safety guarantee for personnel and installations, management of emergency situations, preservation of staff health and protection, inspections, actions undertaken regarding nuclear safety and radiation protection. It reports nuclear events which occurred, describes the management of effluents and the control of the environment (environmental policy, management of effluents from the Malvesi establishment, management of effluents from the ECRIN INB, reduction of consumptions). It addresses the waste management (industrial and radioactive wastes) and the management of other impacts of the ECRIN INB. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

  15. Radiation safety in industrial radiography in the Philippines

    International Nuclear Information System (INIS)

    The article presents the application of radiography in almost all sectors of the industry from construction stage of plants, in oil and gas, petrochemical and power industry which are the biggest users of radiography. Industrial radiography is being conducted using a set of operational procedures developed by the level 3 radiographer and approved by the Radiological Health and Safety Officer (RHSO) to ensure safe and successful completion of the activity

  16. Radiation safety issues in the water treatment plant - Indoor radon and gamma radiation

    Energy Technology Data Exchange (ETDEWEB)

    Jantsikene, A.; Kiisk, M.; Suursoo, S.; Koch, R. [University of Tartu, Institute of Physics (Estonia); Lumiste, L. [Tallinn University of Technology, Department of Chemical Engineering (Estonia)

    2014-07-01

    the second stage filters, classifying them as radioactive material. {sup 222}Rn activity generated in the filter columns was compared to {sup 222}Rn activity entering the plant with raw water; the latter was estimated via liquid scintillation technique. The results indicate that {sup 222}Rn inflow is insignificant compared to the {sup 222}Rn generation in the columns. The estimated difference is in six orders of magnitude. Six alpha-track detectors were placed inside the treatment plant (in filter hall and working rooms) for measuring {sup 220}Rn and {sup 222}Rn indoor air concentrations. The obtained results are above 200 Bq/m{sup 3}. According to the Estonian Standard EVS 840:2009 'Design of radon-safe buildings', the annual radon concentration in living-, rest- and workrooms should remain below 200 Bq/m{sup 3}. The implemented investigation presented in this paper reveals the importance of monitoring radiation safety of the workers of this water treatment plant. Document available in abstract form only. (authors)

  17. Nuclear safety criteria applied in site selection - the practice in France

    International Nuclear Information System (INIS)

    In France, the safety of nuclear facilities is the responsibility of the Ministry for Industry and Research (Central Department for the Safety of Nuclear Facilities). The first part of the paper deals with the conception and contents of the site studies which are included in a safety report with the object of obtaining authorization to go ahead with work on the establishment of a facility. The conception is governed by the following two considerations: (a) the site is a place where the natural elements and living organisms occur and which is characterized by the permanent presence of the human factor, while the proposed nuclear facility will - like any industrial facility - present risks and have an impact on the site, particularly through the discharge of radioactive effluent and potentially in consequence of a nuclear accident; (b) the site exercises an influence - in fact, it even imposes constraints - on the nuclear facility. The site study as submitted by the operators to the authorities responsible for the safety evaluation traditionally consists of six sections, covering: (I) description and history of the site; (II) meteorological conditions; (III) hydrology of the area; (IV) geological and seismological conditions; (V) ecological factors; (VI) natural and/or previous radioactivity at the site. These six sections contain the data which serve as a basis for applying the two considerations spelled out above. However, the two corresponding directions of study and analysis do not settle the fundamental problem of the distribution of the population around the site. Methods for dealing with this problem are suggested in the second part of the paper; they take into account the efforts made so far at the international level. The authors consider that limiting criteria should not be based solely on the radioactive effluent discharges associated with normal operation but on the radioactivity releases associated with accidents. The methods proposed by them constitute

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

    OpenAIRE

    Dianati, Mansoor; Zaheri, Azita; TALARI, Hamid reza; Deris, Fateme; Rezaei, Sara

    2014-01-01

    Background: Radiological examinations for patients who are hospitalized at intensive care units are usually performed using portable radiography devices. However they may require knowledge and safety precautions of nurses. Objectives: The aim of the study was to investigate ICU nurses’ knowledge of radiation safety and their behaviors towards portable radiological examinations. Materials and Methods: In total, 44 intensive care nurses were recruited for this cross-sectional descriptive study ...

  19. Spinal cord biological safety of image-guided radiation therapy versus conventional radiation therapy

    Institute of Scientific and Technical Information of China (English)

    Wanlong Xu; Xilinbaoleri; Hao Liu; Ruozheng Wang; Jingping Bai

    2012-01-01

    Tumor models were simulated in purebred Beagles at the T9-10 levels of the spinal cord and treated with spinal image-guided radiation therapy or conventional radiation therapy with 50 or 70 Gy total radiation. Three months after radiation, neuronal injury at the T9-10 levels was observed, including reversible injury induced by spinal image-guided radiation therapy and apoptosis induced by conventional radiation therapy. The number of apoptotic cells and expression of the proapoptotic protein Fas were significantly reduced, but expression of the anti-apoptotic protein heat shock protein 70 was significantly increased after image-guided radiation therapy compared with the conventional method of the same radiation dose. Moreover, the spinal cord cell apoptotic index positively correlated with the ratio of Fas/heat shock protein 70. These findings indicate that 3 months of radiation therapy can induce a late response in the spinal cord to radiation therapy; image-guided radiation therapy is safer and results in less neuronal injury compared with conventional radiation therapy.

  20. Control of the safety of radiation sources and the security of radioactive materials

    International Nuclear Information System (INIS)

    Since its creation in 1950, the National Atomic Energy Commission (CNEA) of Argentina, was established as the competent authority in the control of nuclear applications in relation to the protection against the hazardous effects of ionizing radiation and the safety of installations. In 1958, the Executive issued Decree 842 approving the Regulation for Using Radioisotopes and Ionising Radiations, to control use and application of radioactive materials and radiation emitted by them or from nuclear reactions. A part of the CNEA, the Regulatory Branch, was then formed and very rapidly established itself as the national authority in the areas of radiation and nuclear safety, safeguards and non-proliferation assurances, and physical protection. In the present paper, only the control of radioactive sources will be presented. The Nuclear Regulatory Authority (ARN) is empowered to establish standards and enforce their application to the possession and use of radiation sources. The regulatory goals are: ensure that the radioactive materials are imported, exported produces, transferred, stored, used, or disposed of, only by registrants or licensed persons in authorised or licensed installations, as required by Argentine regulations; ensure that registrants or licensees do everything reasonable and compatible with their possibilities regarding safety and security of radiation sources; ensure that the radioactive materials are handed over to another user, or are disposed of as radioactive waste, only when transfer or disposal was specifically authorised by the Regulatory Authority; keep an updated database of all the sealed radioactive sources in use in the country; prevent the illicit traffic of radiation sources; ensure safety and security of disused radioactive sealed sources, doing whatever necessary to maintain the required control; ensure that technical characteristics of imported of locally produced radioactive sources comply with Argentine safety requirements

  1. Applying Hamming Code to Memory System of Safety Grade PLC (POSAFE-Q) Processor Module

    International Nuclear Information System (INIS)

    If some errors such as inverted bits occur in the memory, instructions and data will be corrupted. As a result, the PLC may execute the wrong instructions or refer to the wrong data. Hamming Code can be considered as the solution for mitigating this mis operation. In this paper, we apply hamming Code, then, we inspect whether hamming code is suitable for to the memory system of the processor module. In this paper, we applied hamming code to existing safety grade PLC (POSAFE-Q). Inspection data are collected and they will be referred for improving the PLC in terms of the soundness. In our future work, we will try to improve time delay caused by hamming calculation. It will include CPLD optimization and memory architecture or parts alteration. In addition to these hamming code-based works, we will explore any methodologies such as mirroring for the soundness of safety grade PLC. Hamming code-based works can correct bit errors, but they have limitation in multi bits errors

  2. 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.

  3. Annual report 2005 on the radiation and nuclear safety in the Republic of Slovenia

    International Nuclear Information System (INIS)

    The year 2005 was without major problems in the area of protection against ionizing radiation and nuclear safety in Slovenia. There were no events that would present radiological threat to the population. This report contains the essential data on the status in the areas of radiation protection and nuclear safety in the country, and is aimed at a wider group of interested public. At the same time the extended version is prepared consisting of all the details and data which would be of interest to a narrower group of professionals. It is available in electronic form on a CD-ROM or at the home page of the SNSA. (author)

  4. Safety assessment of the disposal of sealed radiation sources in boreholes

    International Nuclear Information System (INIS)

    The Radioactive Waste Management Laboratory (RNML) at the Nuclear Energy Research Institute (NERI) in Sao Paulo, Brazil, is developing the concept of a repository for disused sealed radiation sources in a deep borehole. Several thousands disused sealed radiation sources are stored at NERI awaiting the decision on final disposal and tens of thousands are still under the possession of the licensees. A significant fraction of these sources are long-lived and will require final disposal in a geological repository. The purpose of this paper is to identify and discuss suitable safety assessment strategies for the repository concept and to illustrate a rational approach for a long-term safety assessment methodology. (author)

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

    International Nuclear Information System (INIS)

    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

  6. Organization and implementation of a national regulatory infrastructure governing protection against ionizing radiation and the safety of radiation sources. Interim report for comment

    International Nuclear Information System (INIS)

    A number of IAEA Member States are undertaking to strengthen their radiation protection and safety infrastructures in order to facilitate the adoption of the requirements established in the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Standards). In this connection, the IAEA has developed a technical co-operation programme (Model Project on Upgrading Radiation Protection Infrastructure) to improve radiation protection and safety infrastructures in 51 Member States, taking into account national profiles and needs of the individual participating, countries. The present report deals with the elements of a regulatory infrastructure for radiation protection and safety and intends to facilitate the, implementation of the Basic Safety Standards in practice. It takes into account the proposals in an earlier report, IAEA-TECDOC-663, but it has been expanded to include enabling legislation and modified to be more attuned to infrastructure issues related to implementation of the Standards. The orientation is toward infrastructures concerned with protection and safety for radiation sources used in medicine, agriculture, research, industry and education rather than infrastructures for protection and safety for complex nuclear facilities. It also discusses options for enhancing the effectiveness and efficiency of the infrastructure in accordance with the size and scope of radiation practices and available regulatory resources within a country

  7. Public perception of radiation safety - a case study in Brazil

    International Nuclear Information System (INIS)

    A questionnaire-based survey was conducted in Brazil in order to assist the development of a strategy of communicating radiation issues with the public. The survey contains questions about knowledge of basic concepts, credibility in the sources of information about radiation, recall of the Goiania accident, reaction to an emergency situation (including the Goiania accident), and waste-related risk comparison. An analysis of this survey and a discussion about practical issues of a target-oriented communication program are presented. The communication program is addressed to the nuclear community, regulatory authority, educational centers, the media and the public and includes topics such as the present crisis of confidence, limitations, misconceptions and requirements, and communicating in a crisis situation

  8. Electromagnetic Radiation Measurements and Safety Issues of some Cellular

    Directory of Open Access Journals (Sweden)

    A. Mousa

    2011-01-01

    Full Text Available As the mobile telecommunication systems are tremendously growing allover the world then the numbers of handheld andbase stations are also rapidly growing and it became very popular to see these base stations distributed everywhere in theneighborhood and on roof tops which has caused a considerable amount of panic to the public in Palestine concerning witherthe radiated electromagnetic field from these base stations may cause any health effect or hazard. This paper focuses on theradiated electromagnetic energy from some typical mobile base stations around the city of Nablus. The exposure levels dueto these stations were measured and compared to some international standard guidelines like ICNIRP and FCC to see if itmeets these standards, this is in order to answer some of the public fear and concern. The results are presented and somecomments are made on the other sources of electromagnetic radiation in the 200 kHz to 3 GHz range.

  9. Nuclear Research Centre Juelich. 1984 annual work report of the Department for Safety and Radiation Protection

    International Nuclear Information System (INIS)

    The Department for Safety and Radiation Protection continues to be responsible for coordinating radiation protection, safety and protection at the KFA. It supports the other institutes and departments in performing the safety tasks allotted to them. The principal tasks of the Department are in administrative and technical assistance to these organization units and in safeguards. Administrative assistance involves, for example, regulation of the radiation protection organization in the institutes, including the appointment of radiation protection officers (Strahlenschutzbeauftragte). Furthermore, this includes the central handling of the registration system with the authorities and dealing with outside firms thus considerably relieving the institutes of their administrative tasks. Handling licensing procedures and the central accountancy of radioactive materials is also to be mentioned in this context. Technical assistance largely consists of developing, maintaining and repairing radiation measuring instruments and in the monitoring of personnel by evaluating personnel dosimeters and incorporation controls for radioactive sources. The safeguards tasks of the Department concern the very staff-intensive physical protection, as well as environmental protection and industrial safety. (orig./HSCH)

  10. Safety and security of radiation sources and radioactive materials: A case of Zambia - least developed country

    International Nuclear Information System (INIS)

    In Zambia, which is current (1998) classified as a Least Developed Country has applications of nuclear science and technology that cover the medical, industrial, education and research. However, the application is mainly in medical and industry. Through the responsibility of radiation source is within the mandate of the Radiation Protection Board. The aspects involving security fall on different stake holders some that have no technical knowledge on what radiation is about. The stake holders in this category include customs clearing and forwarding agents, state security/defence agencies and the operators. Such a situation demands a national system that should be instituted to meet the safety and security requirements but takes into account the involvement of the diverse stake holders. In addition such system should avoid unnecessary exposure, ensure safety of radioactive materials and sources, detect illicit trade and maintain integrity of such materials or sources. This paper will provide the status on issue in Zambia and the challenges that exist to ensure further development in application of Nuclear Science and Technology (S and T) in the country takes into account the safety and security requirements that avoid deliberate and accidental loss of radiation sources and radioactive materials. The Government has a responsibility to ensure that effective system is established and operated to protect radiation sources and radioactive materials from theft, sabotage and ensure safety. (author)

  11. Nuclear safety and radiation protection report of the Cattenom nuclear facilities - 2011

    International Nuclear Information System (INIS)

    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 facilities of the Cattenom nuclear power plant (INB 124, 125, 126 and 137, Moselle (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities 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 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  12. Nuclear safety and radiation protection report of the Tricastin operational hot base nuclear facilities - 2013

    International Nuclear Information System (INIS)

    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 2013, 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

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

    International Nuclear Information System (INIS)

    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

  14. Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2010

    International Nuclear Information System (INIS)

    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 facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities 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 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  15. Nuclear safety and radiation protection report of the Dampierre-en-Burly nuclear facilities - 2010

    International Nuclear Information System (INIS)

    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 facilities of the Dampierre-en-Burly nuclear power plant (INB 84 and 85, Loiret, 45 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities 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 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  16. Modernization and consolidation of the European radiation protection legislation. The new EURATOM radiation protection basic safety standards

    International Nuclear Information System (INIS)

    With the development of new basic safety standards for the protection against the dangers arising from ionising radiation, foreseen in Article 2 and Article 30 of the Euratom Treaty, the European Commission modernises and consolidates the European radiation protection legislation. The new Directive offers in a single coherent document, basics safety standards for radiation protection which take account of the status-quo of science and technology, cover all relevant radiation sources, including natural radiation sources, integrate protection of workers, members of the public, patients and the environment, cover all exposure situations, planned, existing, emergency, and harmonise numerical values with international standards. After having received very positive opinions of the Article 31 Group of Experts and the European Economic and Social Committee, the proposed Directive has reached agreement in the Working Party on Atomic Questions of the European Council (WPAQ). The Opinion of the European Parliament is expected in September 2013, which would allow a publication of the Directive in the Official Journal of the European Union by the end of 2013. (orig.)

  17. Radiation Safety Regulatory Policy and Rule for NORM Industries in China

    International Nuclear Information System (INIS)

    Background information and the basic status concerning NORM industries in China is briefly introduced in the paper, including current natural radiation levels and the main results of a general survey related to NORM industries implemented by the Ministry of Environmental Protection. An introduction to the radiation safety regulatory policy and rule for NORM industries in China is also briefly presented. Finally, some considerations concerning NORM regulatory issues are discussed. (author)

  18. Applied Strategies for Improving Patient Safety: A Comprehensive Process To Improve Care in Rural and Frontier Communities

    Science.gov (United States)

    Westfall, John M.; Fernald, Douglas H.; Staton, Elizabeth W.; VanVorst, Rebecca; West, David; Pace, Wilson D.

    2004-01-01

    Medical errors and patient safety have gained increasing attention throughout all areas of medical care. Understanding patient safety in rural settings is crucial for improving care in rural communities. To describe a system to decrease medical errors and improve care in rural and frontier primary care offices. Applied Strategies for Improving…

  19. Radiation safety supervisory system in Latvia and its role in prevention of unauthorised practices with radiation sources

    International Nuclear Information System (INIS)

    This report provides an overview of the practical and legal aspects of the use of radiation sources. The existing regulatory infrastructure is briefly analysed and proposed systems are described. The proposed interactions between the regulatory body and the advisory board are presented and some details about joint activities of different institutions concerning radiation safety are given. An implementation example of the supervisory system in combating illicit trafficking is analysed and the essential components in the prevention of illicit trafficking are assessed. Some findings of investigations are quoted regarding improvements in protection and prevention on the national and the international level. (author)

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

    International Nuclear Information System (INIS)

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

  1. Inspection of radiation sources and regulatory enforcement (supplement to IAEA Safety Standards Series No. GS-G-1.5)

    International Nuclear Information System (INIS)

    The achievement and maintenance of a high level of safety in the use of radiation sources depends on there being a sound legal and governmental infrastructure, including a national regulatory body with well-defined responsibilities and functions. These responsibilities and functions include establishing and implementing a system for carrying out regulatory inspections, and taking necessary enforcement actions. The Safety Requirements publication entitled Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety establishes the requirements for legal and governmental infrastructure. The term 'infrastructure' refers to the underlying structure of systems and organizations. This includes requirements concerning the establishment of a regulatory body for radiation sources and the responsibilities and functions assigned to it. The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards or the BSS) establish basic requirements for protection against risks associated with exposure to ionizing radiation and for the safety of radiation sources. The application of the BSS is based on the presumption that national infrastructures are in place to enable governments to discharge their responsibilities to for radiation protection and safety. This TECDOC provides practical guidance on the processes for carrying out regulatory inspections and taking enforcement actions. It includes information on the development and use of procedures and standard review plans (i.e. checklists) for inspection. Specific procedures for inspection of radiation practices and sources are provided in the Appendices

  2. Radiation Protection from a Radiobiological Perspective Safety Related Technological Profession in Need of a Better Scientific Foundation. Part A - Old and Simple Concept

    International Nuclear Information System (INIS)

    This series of three papers (parts A, B and C) is meant primarily for non-radio biologists professionals working in the area of radiation protection. It aims at pointing out the less than sound scientific foundations of a human safety related profession and the need for a better scientific theory in this area. However, this by itself might not be enough to apply the relevant and much necessary changes and updates to methodologies for radiation risk assessment crucial for the radiation protection profession. Public responsibility and administrative courage to address the emerging new information is not less imperative

  3. Radiation safety and accident experience at gamma irradiation plants

    International Nuclear Information System (INIS)

    Gamma irradiation plants for the sterilization of medical products, preservation of food grains and for various other applications employ multikilocurie 60Co sealed sources inside shielded irradiation cells. A number of interlocks are provided between the cell entry door and the source raise mechanisms, in order to prevent the entry of any person to the cell when the source is in the exposed condition. The present paper gives the general safety features and the interlocks employed in these plants along with the safety features of irradiation plants at BARC, namely 106 Ci Isomed plant for the sterilization of medical products, 105 Ci FIPLY plant for research in food preservation and 105 Ci PANBIT plant for industrial research. Over the last two decades five cases of accidental exposure have been reported in literature in which the operator gained entry to the irradiation cell when the source was in the exposed condition. Two of these cases resulted in fatalities while the remaining three cases resulted in hospitalization of the exposed individuals for six to seven weeks. A brief outline of these accidental exposure cases and the causes of the accidents are discussed in this paper. (author). 19 refs

  4. KIRDI Association with Radiation Protection Growing the Safety Culture

    International Nuclear Information System (INIS)

    As Kenya reaches for vision 2030, Nondestructive Testing Technology will require better quality and safety of operation, more reliable information on the current status, usability and an object’s life expectation. Mechanical stresses are not visible to most of conventional NDT methods and they are usually the main and the first indicator of problems. The solution to this will be using the indicator of Mechanical Stresses (IMS). The (IMS-Magneto-Anisotropic indicator of mechanical stresses, searches for conditions of deterioration to estimate the possible failure based on measuring concentration and the gradient of mechanical stress on Ferro-Magnetic parts. This early detection assures quality and safety is required of materials tested. Equipment used at Kenya Ports Authority (KPA) and in the sugar factories are initially target for this investigation. The quality of stress release by Heat Treatment of vibration will be determined; quick check to identify high stress areas in welds will be done. The critical areas will be inspected by RT or UT. Money will be saved on reliable inspection which sees the defect before it become a defect. (Author)

  5. International movement on radiation safety related to the ICRP and the IAEA-RADWASS

    International Nuclear Information System (INIS)

    Nowadays discussion on Radiation Safety has a spread of world wide range. The main framework on radiation safety was constructed by ICRP (International Commission on Radiological Protection), which was established in 1928. This term of the committee was from June 1993 to May 1997 and the first plenary meeting was held at the Queen's hotel in Bournemouth of the United Kingdom on September 1993. The outline of this meeting, especially related items to the Committee 4, were summarized in this paper. The second point of our workshop considerations is radioactive waste problems, which are now under discussion in RADWASS (Radioactive Waste Safety Standards) project of IAEA (International Atomic Energy Agency). This IAEA-RADWASS will last nearly 10 years to cover whole subjects. These discussed items are arranged into various international standards; the safety fundamental, the safety standards, the safety guides and the safety practices. These systematic approach, if we could summarize, would be effective not only to the specialists but also to a general public to get an acceptance of radioactive waste problem. Here, this IAEA-RADWASS project is reviewed. (author)

  6. Public perception of radiation safety - a case study in Brazil

    International Nuclear Information System (INIS)

    Since the early 1980s, Brazil has been operating installations which run the gamut of the nuclear fuel cycle, from uranium mining and milling to a nuclear power plant. A second power plant is under construction and is planned to come on stream in 1999. In 1987, Brazil was shaken by the largest radiological accident on record involving a unit of radiotherapy equipment. This accident contaminated large areas of Goiania, a city of some 1 million inhabitants, and generated 3500 m3 of radioactive waste. At present, apart from the facilities involved in the nuclear fuel cycle, close to 2600 installations in Brazil utilize radioactive materials in medicine, industry and research. Following the Goiania accident, the Brazilian authorities built a final subsurface disposal facility, which is currently in operation, for the waste generated by the cleanup of the city. Studies are now under way for the selection of a national waste repository. However, in spite of all the activities mentioned, the Brazilian public is largely unaware of both the benefits and the real risks of radiation. In order to assist in the development of an appropriate communication strategy focusing on radiation issues and directed at the public, a survey was undertaken. The survey contained questions on basic knowledge, the credibility of information sources dealing with radiation issues, recollections of the Goiania accident, reacting to an emergency situation in general and Goiania in particular and on waste related risk comparison. An analysis of this survey is presented. Practical issues are reviewed, including a target oriented communication programme involving the nuclear community, the regulatory authority, educational centres, the media and the public. The topics addressed are the present crisis of confidence, limitations, misconceptions and requirements, and communicating in a situation of crisis. (author)

  7. Safety of radiation sources and security of radioactive materials. Proceedings of an international conference

    International Nuclear Information System (INIS)

    This International Conference, hosted by the Government of France and co-sponsored by the European Commission, the International Criminal Police Organization (Interpol) and the World Customs Organization (WCO), was the first one devoted to the safety of radiation sources and the security of radioactive materials and - for the first time - brought together radiation safety experts, regulators, and customs and police officers, who need to closely co-operate for solving the problem of illicit trafficking. The technical sessions reviewed the state of the art of twelve major topics, divided into two groups: the safety of radiation sources and the security of radioactive materials. The safety part comprised regulatory control, safety assessment techniques, engineering and managerial measures, lessons from experience, international cooperation through reporting systems and databases, verification of safety through inspection and the use of performance indicators for a regulatory programme. The security part comprised measures to prevent breaches in the security of radioactive materials, detection and identification techniques for illicit trafficking, response to detected cases and seized radioactive materials, strengthening awareness, training and exchange of information. The Conference was a success in fostering information exchange through the reviews of the state of the art and the frank and open discussions. It raised awareness of the need for Member States to ensure effective systems of control and for preventing, detecting and responding to illicit trafficking in radioactive materials. The Conference finished by recommending investigating whether international undertakings concerned with an effective operation of national systems for ensuring the safety of radiation sources and security of radioactive materials

  8. Progress report: nuclear safety and radiation protection in France in 2005

    International Nuclear Information System (INIS)

    The Asn (Nuclear safety authority) considers that 2005 was a satisfactory year in terms of nuclear safety and radiation protection. However, further progress can and must be made. 2005 was a year of great progress for the Asn as it consolidated its organisation and working methods, in accordance with the 2005-2007 strategic plan it set for itself. The Asn continued progress in the field of radiation protection has given rise to various new regulations to improve the legislative and regulatory framework in this area. 2005 was marked by significant progress in the process of harmonizing national nuclear safety policies Against a backdrop of the preparation of a bill on management of radioactive materials and waste, to be presented to Parliament in March 2006, 2005 was a year of important milestones. The Asn control activities encompass the following seven areas: development of general regulations for nuclear safety and radiation protection; management of individual authorization requests and receipt of declarations; inspection of nuclear activities; organisation of radiological surveillance of individuals and of the environment; preparation for management of emergency situations and implementation if necessary; contribution to public information on nuclear safety and radiation protection; determination of the French position within international community. Main topics in 2005: government bill on transparency and security in the nuclear field; the challenges and ambitions of the Asn; controlling exposure to radon; EPR Reactor Project Safety; working towards a law on radioactive waste in 2006; I.R.R.T.: an international audit of Asn in 2006; harmonization of nuclear safety in Europe; Chernobyl: what has been achieved over the past 20 years; informing the Public; internal authorizations. (N.C.)

  9. Training in nuclear and radiation safety in Latin American and Caribbean

    International Nuclear Information System (INIS)

    From thirty-three years, Argentina has taken the commitment to train professionals in the field of nuclear and radiation safety for the care and protection of workers and public in general. Sponsored by the IAEA and supported by the Faculty of Engineering of the University of Buenos Aires (FIUBA), an undertaking was made to encourage the training of scientists and experts in the countries of the region in order to establish a strong safety culture in radiation in individuals and maintaining high standards of safety practices using ionizing radiation. In 2012, the Graduate Course in Radiation Protection and Safety of Radiation Sources has acquired the status of 'Specialization' of the FIUBA, a category that further hierarchies skills training in the subject. This is a highly anticipated achievement by the implications for academic institutions, national and regional level, contributing to the strengthening of the Regional Training Center for Latin America and the Caribbean, acknowledged in a long-term agreement between the IAEA and Argentina in September 2008. Due to increased demand for nuclear activity, it is important to continue and deepen further training in radiological and nuclear areas. In order to satisfy both national and regional needs a process of increase on training offer training is being carried out, under the jurisdiction frame of the Nuclear Regulatory Authority. This paper presents the achievements of the country so far as regards training of human resource in radiation protection and nuclear safety in the region and highlights the challenges ahead for the extension of the offer in education and training. (author)

  10. Positioning radiation safety in occupational safety and health programme in an organization

    International Nuclear Information System (INIS)

    The Atomic Energy Licensing Act 1984, which is under purview of the Ministry of Science, Technology and Environment, and Occupational Safety and Health Act, OSHA 1994, under Ministry of Human Resources were discussed. RPO responsibilities were discussed in detailed. As the conclusion, organization which complies with the provisions of the AELA 1984 are well on the way to complying the requirements of OSHA 1994

  11. The status of safety of radiation sources and security of radioactive materials in Ethiopia

    International Nuclear Information System (INIS)

    Since 1993, the National Radiation Protection Authority (NRPA) has been empowered by the 'Radiation Protection Proclamation no. 79/1993' to authorize and inspect regulated activities, issue guidelines and standards and enforce the legislation and regulations. The report describes the status of the safety of radiation sources and the security of radioactive materials in Ethiopia and the progress made towards building a sound and effective national regulatory infrastructure. Also, the report highlights the challenges and difficulties encountered and concludes by indicating the way forward towards the strategic goals. (author)

  12. Radiation safety analysis and drafting radwaste management scheme during arrangement of sanitary inspection room site

    International Nuclear Information System (INIS)

    Basic results of activities aimed at fulfillment of economic Contract No 152/2002 with Kiev 'Energoproyekt' Institute are shown. Radiation conditions analysis for work implementation is carried out. Transport and technology schemes for radwaste management depending on its types and categories are prepared. A set of measures is offered for radiation protection of personnel involved in erection of sanitary inspection room. Collective dose of current exposure for personnel involved in above works is estimated. Acceptability of adopted design solutions in terms of radiation safety provision is assessed

  13. 10 CFR 35.50 - Training for Radiation Safety Officer.

    Science.gov (United States)

    2010-01-01

    ... science with a minimum of 20 college credits in physical science; (ii) Have 5 or more years of professional experience in health physics (graduate training may be substituted for no more than 2 years of the required experience) including at least 3 years in applied health physics; and (iii) Pass an...

  14. Safety consequences of the release of radiation induced stored energy

    International Nuclear Information System (INIS)

    Due to the disposal of HLW in a salt formation gamma energy will be deposited in the rock salt. Most of this energy will be converted into heat, whilst a small part will create defects in the salt crystals. Energy is stored in the damaged crystals. Due to uncertainties in the models and differences in the disposal concepts the estimated values for the stored energy range from 10 to 1000 J/g in the most heavily damaged crystals close to the waste containers. The amount of radiation damage decays exponentially with increasing distance from the containers and at distances larger than 0.2 m the stored energy can be neglected. Given the uncertainties in the model predictions and in the possible release mechanism an instantaneous release of stored energy cannot be excluded completely. Therefore the thermo-mechanical consequences of a postulated instantaneous release of an extremely high amount of radiation induced stored energy have been estimated. These estimations are based on the quasi-static solutions for line and point sources. To account for the dynamic effects and the occurrence of fractures an amplification factor has been derived from mining experience with explosives. A validation of this amplification factor has been given using post experimental observations of two nuclear explosions in a salt formation. For some typical disposal concepts in rock salt the extent of the fractured zone has been estimated. It appeared that the radial extent of the fractured zone is limited to 5 m. Given the much larger distance between the individual boreholes and the distance between the boreholes and the boundary of the salt formation (more than 100 m), the probability of a release of radiation induced stored energy creating a pathway for the nuclides from the containers to the groundwater, is extremely low. The radiological consequences of a groundwater intrusion scenario induced by this very unprobable pathway are bounded by the 'standard' groundwater intrusion

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

    Science.gov (United States)

    Gaona, Enrique; Enríquez, Jesús G. Franco

    2004-09-01

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

  16. CURRENT TRENDS OF THE PROVISION FOR RADIATION SAFETY OF THE POPULATION OF THE RUSSIAN FEDERATION

    Directory of Open Access Journals (Sweden)

    G. G. Onishenko

    2014-01-01

    Full Text Available P.V.Ramzaev”The article is devoted to the actual issues ofRussian Federationpopulation radiation safety providing at the present stage. The important role of radiation-hygienic passportization is underlined in the process of the obtaining of objective information of radiation situation in the country, of population exposure doses from the all sources: artificial and natural, from the use of ionizing irradiation sources in medicine. The leading role is shown of the natural ionizing irradiation sources in the level of the country population exposure. The main directions of activities are stated aimed on the decreasing of population exposure doses from the natural sources. The brief characteristics is given of the radiation situation on the territories radioactively contaminated after the accident on the Chernobyl NPP, in the Pacific Ocean basin after the accident on the “Fukushima-1”NPP, of the main measures for radiation protection providing and for counteraction to radiation terrorism during the period of international sports and mass actions which were carried out in Russia in the last years (XXVII World Summer Universiade in2013 inKazan, XXII Olympic and XI Winter Paralympics Games in2014 inSochi. The most important tasks are defined for the improvement ofRussian Federationpopulation radiation safety at the present stage.

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

    Science.gov (United States)

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

    2015-04-01

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

  18. Radiation protection and safety for final disposal of radioactive wastes stored in Abadia de Goias, Brazil

    International Nuclear Information System (INIS)

    This standard aims to satisfy the radiation protection and safety conditions required by Brazilian Nuclear Energy Commission (CNEN) for final disposal of radioactive wastes stored in Abadia de Goias. These wastes are products of the accident happened in 1987 caused by the Cs-137 source violation. (M.V.M.)

  19. Information report on nuclear safety and radiation protection of the Tricastin AREVA site, 2010 edition

    International Nuclear Information System (INIS)

    This report presents the Tricastin site, the different arrangements concerning nuclear safety and radiation protection on this site, and recent nuclear events. It describes how site releases are managed and how the environment is controlled and monitored, how wastes are managed, and how other impacts are controlled. It finally presents the different actions regarding transparency and information

  20. The Use of Radiation to Develop Organic Farming for Food Safety

    International Nuclear Information System (INIS)

    The conference of the use of radiation to develop organic farming for food safety was held on 28-29 September 2006 in Bangkok. This conference contain paper on non-power applications of nuclear technology in farming, agriculture and industry.

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

    Science.gov (United States)

    Emery, Robert J; Rios, Janelle

    2016-02-01

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

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

    International Nuclear Information System (INIS)

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the facilities (INBs no. 78, 89 (NPPs in operation), 465 (NPP under deconstruction), 102 (fuel storage facility), and 173 (radioactive waste conditioning and storage facility under construction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities 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 any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  3. Nuclear safety and radiation protection report of the Bugey nuclear facilities - 2013

    International Nuclear Information System (INIS)

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the facilities (INBs no. 78, 89 (NPPs in operation), 465 (NPP under deconstruction), 102 (fuel storage facility), and 173 (radioactive waste conditioning and storage facility under construction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities 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 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

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

    International Nuclear Information System (INIS)

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the facilities (INBs no. 94 (irradiated materials workshop), 99 (fuel storage facility), 107 and 132 (NPPs in operation), 133, 153 and 161 (NPPs under deconstruction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities 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 any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

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

    Science.gov (United States)

    Song, H C

    2016-06-01

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

  6. CMEA country-members cooperation in radiation safety during 1976-1981

    International Nuclear Information System (INIS)

    A summary of nuclear power plant radiation safety activities within 1976-80 is presented. Major results of scientific and engineering cooperation between CMEA country-members in this field are reviewed. A number of radiation safety tasks is suggested to be added to the list approved in 1978 by the CMEA permanent commission Atomenergo, as follows: development of the environment protection requirements both under normal operation conditions and during accidents on Nuclear power plants, Nuclear heat supply plants, Nuclear heat-electricity supply plants; development of technical and organizational measures for the personnel exposure reduction during repair and fuel reloading operations at NPP; estimates of radiation conditions at the NPP site location both under normal operation conditions and during accidents

  7. Approaches to enhancing radiation safety in cardiovascular imaging: a scientific statement from the American Heart Association.

    Science.gov (United States)

    Fazel, Reza; Gerber, Thomas C; Balter, Stephen; Brenner, David J; Carr, J Jeffrey; Cerqueira, Manuel D; Chen, Jersey; Einstein, Andrew J; Krumholz, Harlan M; Mahesh, Mahadevappa; McCollough, Cynthia H; Min, James K; Morin, Richard L; Nallamothu, Brahmajee K; Nasir, Khurram; Redberg, Rita F; Shaw, Leslee J

    2014-11-01

    Education, justification, and optimization are the cornerstones to enhancing the radiation safety of medical imaging. Education regarding the benefits and risks of imaging and the principles of radiation safety is required for all clinicians in order for them to be able to use imaging optimally. Empowering patients with knowledge of the benefits and risks of imaging will facilitate their meaningful participation in decisions related to their health care, which is necessary to achieve patient-centered care. Limiting the use of imaging to appropriate clinical indications can ensure that the benefits of imaging outweigh any potential risks. Finally, the continually expanding repertoire of techniques that allow high-quality imaging with lower radiation exposure should be used when available to achieve safer imaging. The implementation of these strategies in practice is necessary to achieve high-quality, patient-centered imaging and will require a shared effort and investment by all stakeholders, including physicians, patients, national scientific and educational organizations, politicians, and industry.

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

    Science.gov (United States)

    Vaz, Pedro

    2015-11-01

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

  9. Annual report of the Chief Executive Officer of the Australian Radiation Protection and Nuclear Safety Agency 2005-06

    International Nuclear Information System (INIS)

    This report satisfies the annual reporting requirements of the ARPANS Act in addition to the Department of Prime Minister and Cabinet requirements for annual reporting by Agencies. The report includes: details of the operations of the CEO and details of directions given by the Minister under section 16 at Part 1; details of the operations of ARPANSA at Part 3; details of the operations of the Radiation Health Advisory Council, the Radiation Health Committee and the Nuclear Safety Committee and details of all reports received from the Radiation Health and Safety Advisory Council on matters related to radiation protection and nuclear safety or the Nuclear Safety Committee on matters related to nuclear safety and the safety of controlled facilities at Part 4; details of any breach of licence conditions by a licensee at Appendix 4; an index of compliance with the annual reporting requirements at Appendix 8

  10. Monte Carlo method of radiative transfer applied to a turbulent flame modeling with LES

    Science.gov (United States)

    Zhang, Jin; Gicquel, Olivier; Veynante, Denis; Taine, Jean

    2009-06-01

    Radiative transfer plays an important role in the numerical simulation of turbulent combustion. However, for the reason that combustion and radiation are characterized by different time scales and different spatial and chemical treatments, the radiation effect is often neglected or roughly modelled. The coupling of a large eddy simulation combustion solver and a radiation solver through a dedicated language, CORBA, is investigated. Two formulations of Monte Carlo method (Forward Method and Emission Reciprocity Method) employed to resolve RTE have been compared in a one-dimensional flame test case using three-dimensional calculation grids with absorbing and emitting media in order to validate the Monte Carlo radiative solver and to choose the most efficient model for coupling. Then the results obtained using two different RTE solvers (Reciprocity Monte Carlo method and Discrete Ordinate Method) applied on a three-dimensional flame holder set-up with a correlated-k distribution model describing the real gas medium spectral radiative properties are compared not only in terms of the physical behavior of the flame, but also in computational performance (storage requirement, CPU time and parallelization efficiency). To cite this article: J. Zhang et al., C. R. Mecanique 337 (2009).

  11. Analysis of characteristics and radiation safety situation of uranium mining and metallurgy facilities in north area of China

    International Nuclear Information System (INIS)

    According to the radiation safety management of uranium mining and metallurgy facilities in north area of China, features and radiation safety conditions of uranium mining and metallurgy facilities in north area of China were analyzed based on summarizing the inspection data for 2011-2013. So the main problems of radiation environment security on uranium mine were studied. The relevant management measures and recommendations were put forward, and the basis for environmental radiation safety management decision making of uranium mining and metallurgy facilities in future was provided. (authors)

  12. Radiation safety of handheld mobile phones and base stations

    International Nuclear Information System (INIS)

    The recent expansion of personal telecommunications has led to a rapid increase in the exposure of people to the radio-frequency (RF) radiation. Although the mobile phones are low power devices, the antenna is so close to the head that the local exposure may slightly exceed 2 W/kg, the current exposure limit for the local specific absorption rate SAR for the general public. The increase in the temperature is, however, too small to have any physiological significance. On the basis of experiments with cell cultures it is possible that other biological effects caused by some unknown non-thermal mechanism exist, but thus far there is no conclusive biological or epidemiological evidence to suggest any diseases or adverse physiological changes below the thermal threshold. The use of a mobile phone by a person wearing a pace-maker, is not recommended, if the immunity of the pace-maker has not been assured. The exposure caused by the base stations is in all practical cases well below the power density limits for general public. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Trinoskey, P.A.

    1994-10-01

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

  14. Radiation safety of handheld mobile phones and base stations

    Energy Technology Data Exchange (ETDEWEB)

    Jokela, K.; Leszczynski, D.; Paile, W.; Salomaa, S.; Puranen, L.; Hyysalo, P

    1999-01-01

    The recent expansion of personal telecommunications has led to a rapid increase in the exposure of people to the radio-frequency (RF) radiation. Although the mobile phones are low power devices, the antenna is so close to the head that the local exposure may slightly exceed 2 W/kg, the current exposure limit for the local specific absorption rate SAR for the general public. The increase in the temperature is, however, too small to have any physiological significance. On the basis of experiments with cell cultures it is possible that other biological effects caused by some unknown non-thermal mechanism exist, but thus far there is no conclusive biological or epidemiological evidence to suggest any diseases or adverse physiological changes below the thermal threshold. The use of a mobile phone by a person wearing a pace-maker, is not recommended, if the immunity of the pace-maker has not been assured. The exposure caused by the base stations is in all practical cases well below the power density limits for general public. (author) 118 refs.

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

    International Nuclear Information System (INIS)

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

  16. 36 CFR 1234.12 - What are the fire safety requirements that apply to records storage facilities?

    Science.gov (United States)

    2010-07-01

    ... requirements that apply to records storage facilities? 1234.12 Section 1234.12 Parks, Forests, and Public... STORAGE FACILITIES Facility Standards § 1234.12 What are the fire safety requirements that apply to... reference, see § 1234.3). (e) The fire resistive rating of the roof must be a minimum of 1/2 hour for...

  17. Recommendation of the working group commissioned by the French nuclear safety authority on stereotactic radiation therapy

    International Nuclear Information System (INIS)

    Purpose. - At the request of the French nuclear safety authority (Autorite de Surete Nucleaire, ASN) a working party of multidisciplinary experts was initiated to elaborate a report regarding propositions for the clinical practice of stereotactic radiation therapy and the related medical physics. Material and methods. - Several stereotactic radiation therapy experts were audited by the working party, especially neurosurgeons and neuro-radiologists, as well as radiation oncologists, medical physicists and radiation technologists. An international survey was conducted looking at legal requirements and guidelines concerning stereotactic radiation therapy. A national survey was conducted in France among 29 departments performing stereotactic radiation therapy. The working party report was submitted for advice to the permanent group of medical experts of ASN. Results. - Among the 13 countries who responded, very few have legal documents. Some of them are stating that stereotactic radiation therapy must be performed in a radiotherapy department and only by well-trained professionals. Guidelines describing the role of each participant have been published in the USA. In France, stereotactic radiation therapy is performed with dedicated machines or adapted linear accelerators. In 2009, within the 29 departments, 4247 patients were treated with stereotactic radiation therapy representing 4% of the patients treated with external beam radiation therapy. Intracranial lesions were: 3383 and extracranial: 864. The working party of multidisciplinary experts made 7 recommendations. The first one saying that stereotactic radiation therapy must be considered as a radiotherapy. The permanent group of medical experts is asking to modify the 'decret du 19 mars 2007' regarding 'radiosurgery'. Conclusion. - The medical benefit of stereotactic radiation therapy is well admitted and it is an increasingly used technique. This work through practical guidelines and legal propositions intends

  18. GPU-based Monte Carlo dust radiative transfer scheme applied to AGN

    CERN Document Server

    Heymann, Frank

    2012-01-01

    A three dimensional parallel Monte Carlo (MC) dust radiative transfer code is presented. To overcome the huge computing time requirements of MC treatments, the computational power of vectorized hardware is used, utilizing either multi-core computer power or graphics processing units. The approach is a self-consistent way to solve the radiative transfer equation in arbitrary dust configurations. The code calculates the equilibrium temperatures of two populations of large grains and stochastic heated polycyclic aromatic hydrocarbons (PAH). Anisotropic scattering is treated applying the Heney-Greenstein phase function. The spectral energy distribution (SED) of the object is derived at low spatial resolution by a photon counting procedure and at high spatial resolution by a vectorized ray-tracer. The latter allows computation of high signal-to-noise images of the objects at any frequencies and arbitrary viewing angles. We test the robustness of our approach against other radiative transfer codes. The SED and dust...

  19. A study on the radiation and environmental safety -Development of radiation protection and measurement technology-

    Energy Technology Data Exchange (ETDEWEB)

    Jang, See Yung; Lee, Tae Yung; Lee, Hyung Sub; Kim, Jan Ryul; Kim, Chang Kyung; Kim, Bong Hwan; Yoon, Kyung Soo; Jung, Kyung Kee; Jung, Duk Yun; Lee, Bong Jae; Yoon Suk Chul; Lee, Kee Chang; Yoon, Yu Chang; Jung, Rae Ik; Lee, Sang Yoon; Han, Yung Dae; Kim, Jong Soo, I; Kim, Jong Soo, II; Suh, Kyung Won [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Kim, Jong Kyung [Han Yang Univ., Seoul (Korea, Republic of)

    1995-07-01

    Reference X- and neutron radiation fields have been established and evaluated to support the national radiation protection programme under which performance evaluation test for domestic personal dosimetry will be implemented by the ministerial ordinance 1992-15, and to provide a basic technical support in radiation protection dosimetry. Personal dose evaluation algorithm has been developed with the KAERI reference radiation fields which comply well with those in the new ANSI N13.11(1993) to evaluate accurate personal dose equivalents. A personal internal dosimetry algorithm which can estimate the intakes of radionuclides from the results of whole body direct bioassay and the resulting internal doses has been also developed and evaluated to be equally excellent compared with those being used in foreign countries. A BOMAB phantom for precise WBC calibration has also designed, fabricated and test-evaluated. A principal method for estimating the cost for radiation protection which is important in performing a cost-benefit analysis for the radiation protection optimization study based on the ALARA principle has been preliminarily investigated and suggested. 49 figs, 67 tabs, 50 refs. (Author).

  20. Report on administrative work at radiation safety center in fiscal year 2001

    Energy Technology Data Exchange (ETDEWEB)

    Uda, Tatsuhiko; Asakura, Yamato; Sakuma, Yoichi; Kawano, Takao; Yamanishi, Hirokuni; Sugiyama, Takahiko; Miyake, Hitoshi

    2003-03-01

    National Institute for Fusion Science constructed Large Helical Device (LHD) which is the largest magnetic confinement plasma experimental device using super conductive magnet coils. It took eight years to construct and the first plasma shot had been carried out on March 1998. In the experiments high plasma temperature and improved plasma confinement have been achieved. This is the report of administrative work at the radiation safety center considering radiation protection for workers at the LHD and related devices, and radiation monitoring in the site. Major scope is as follows. (1) Radiation measurement and dose monitoring in the radiation controlled area and in the site using particularly developed monitoring system named as Radiation Monitoring System Applicable to Fusion Experiments (RMSAFE). (2) Establishment of education and registration system for radiation workers and access control system for the LHD controlled area. I hope that as like the published reports of fiscal year 1999 and 2000, the present report will be helpful for management of future radiation protection in the research institute. (author)

  1. Are we failing to communicate? Internet-based patient education materials and radiation safety

    International Nuclear Information System (INIS)

    Introduction: Patients frequently turn to the Internet when seeking answers to healthcare related inquiries including questions about the effects of radiation when undergoing radiologic studies. We investigate the readability of online patient education materials concerning radiation safety from multiple Internet resources. Methods: Patient education material regarding radiation safety was downloaded from 8 different websites encompassing: (1) the Centers for Disease Control and Prevention, (2) the Environmental Protection Agency, (3) the European Society of Radiology, (4) the Food and Drug Administration, (5) the Mayo Clinic, (6) MedlinePlus, (7) the Nuclear Regulatory Commission, and (8) the Society of Pediatric Radiology. From these 8 resources, a total of 45 articles were analyzed for their level of readability using 10 different readability scales. Results: The 45 articles had a level of readability ranging from 9.4 to the 17.2 grade level. Only 3/45 (6.7%) were written below the 10th grade level. No statistical difference was seen between the readability level of the 8 different websites. Conclusions: All 45 articles from all 8 websites failed to meet the recommendations set forth by the National Institutes of Health and American Medical Association that patient education resources be written between the 3rd and 7th grade level. Rewriting the patient education resources on radiation safety from each of these 8 websites would help many consumers of healthcare information adequately comprehend such material

  2. Education and Training in Radiation, Transport and Waste Safety Newsletter, No. 4, August 2014

    International Nuclear Information System (INIS)

    IAEA’s Division of Radiation, Transport and Waste Safety is assisting Member States to develop national strategies for education and training in radiation, transport and waste safety via the regional projects on “Strengthening Education and Training Infrastructure, and Building Competence in Radiation Safety” (RAF/9/04, RAS/9/066, RER/9/109 and RLA/9/070). The regional workshops conducted in 2012 in this area and the results achieved were presented in the previous issues of this newsletter focussing specifically on each region of the Technical Cooperation Programme (Africa, Asia and the Pacific, Europe and Latin America). In the course of 2013, a new cycle of Regional Workshops was conducted. The workshops held in the regions of Africa, Asia and the Pacific, and Europe mainly focussed on Sharing Experience and Progress made in establishing a National Strategy for Education and Training in Radiation, Transport and Waste Safety (pages 2-5). The workshop held in the region of Latin America mainly focussed on Developing and Implementing Education and Training programmes. An overview on the results achieved by participating Member States for the period 2012-2013 is provided

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

    Science.gov (United States)

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

    2016-08-01

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

  4. Are we failing to communicate? Internet-based patient education materials and radiation safety

    Energy Technology Data Exchange (ETDEWEB)

    Hansberry, David R., E-mail: hansbedr@njms.rutgers.edu; Ramchand, Tekchand, E-mail: ramchate@njms.rutgers.edu; Patel, Shyam, E-mail: patel288@njms.rutgers.edu; Kraus, Carl, E-mail: krauscf@njms.rutgers.edu; Jung, Jin, E-mail: jungjk@njms.rutgers.edu; Agarwal, Nitin, E-mail: nitin.agarwal@rutgers.edu; Gonzales, Sharon F., E-mail: gonzalsh@njms.rutgers.edu; Baker, Stephen R., E-mail: bakersr@njms.rutgers.edu

    2014-09-15

    Introduction: Patients frequently turn to the Internet when seeking answers to healthcare related inquiries including questions about the effects of radiation when undergoing radiologic studies. We investigate the readability of online patient education materials concerning radiation safety from multiple Internet resources. Methods: Patient education material regarding radiation safety was downloaded from 8 different websites encompassing: (1) the Centers for Disease Control and Prevention, (2) the Environmental Protection Agency, (3) the European Society of Radiology, (4) the Food and Drug Administration, (5) the Mayo Clinic, (6) MedlinePlus, (7) the Nuclear Regulatory Commission, and (8) the Society of Pediatric Radiology. From these 8 resources, a total of 45 articles were analyzed for their level of readability using 10 different readability scales. Results: The 45 articles had a level of readability ranging from 9.4 to the 17.2 grade level. Only 3/45 (6.7%) were written below the 10th grade level. No statistical difference was seen between the readability level of the 8 different websites. Conclusions: All 45 articles from all 8 websites failed to meet the recommendations set forth by the National Institutes of Health and American Medical Association that patient education resources be written between the 3rd and 7th grade level. Rewriting the patient education resources on radiation safety from each of these 8 websites would help many consumers of healthcare information adequately comprehend such material.

  5. The regulatory infrastructure for radiation protection, the safety of radiation sources and security of radioactive materials in Ethiopia

    International Nuclear Information System (INIS)

    demonstrated local commitment have immensely contributed to the transformation process and the current status of achievement in building a sound and credible National Infrastructure for Radiation Safety. (author)

  6. Feasibility-Seeking and Superiorization Algorithms Applied to Inverse Treatment Planning in Radiation Therapy

    OpenAIRE

    Davidi, R; Censor, Y.; Schulte, R. W.; Geneser, S.; Xing, L

    2014-01-01

    We apply the recently proposed superiorization methodology (SM) to the inverse planning problem in radiation therapy. The inverse planning problem is represented here as a constrained minimization problem of the total variation (TV) of the intensity vector over a large system of linear two-sided inequalities. The SM can be viewed conceptually as lying between feasibility-seeking for the constraints and full-fledged constrained minimization of the objective function subject to these constraint...

  7. Education and Training in Radiation, Transport and Waste Safety Newsletter, No. 1, August 2012

    International Nuclear Information System (INIS)

    The IAEA has a statutory function to establish standards for the protection of health, life and property against ionizing radiation and to provide for the application of these standards to peaceful nuclear activities. Education and training (E and T) is one of the main mechanisms to provide support to Member States in the application of the standards. In 2000, an internal evaluation of the overall education and training programme was undertaken. The conclusions were that the provision of and support for E and T in Member States tended to be on a reactive rather than proactive basis, contributing to a culture of dependency rather than sustainability. On the basis of this evaluation, a strategic approach to education and training in radiation and waste safety was developed that outlined the objectives and outcomes to be achieved over a ten year period (2001-2010). General Conference Resolutions have underlined or emphasized the importance of sustainable programmes for education and training in radiation, transport and waste safety, and have also welcomed the ongoing commitment of the Secretariat and Member States to the implementation of the strategy. A Steering Committee for Education and Training in Radiation Protection and Waste Safety was established in 2002, with the mission of advising the IAEA on the implementation of the strategy and making recommendations as appropriate. In 2010, the Steering Committee analysed the overall achievement of the strategic approach 2011-2010, refined the vision of the original strategy and redefined the related objectives. The Strategic Approach to Education and Training in Radiation, Transport and Waste Safety (2011-2020) was submitted to the IAEA's policy-making organs and was noted by its Board of Governors in September 2010.

  8. Safety Culture in activities involving ionising radiation-education project

    Energy Technology Data Exchange (ETDEWEB)

    Sahyun, A.; Sordi, G. M.; Sanches, M. P.; Levy, P. J.; Levy, D. S.

    2004-07-01

    The Brazilian National Commission of Nuclear Energy (CNEN) requires a Radiological Protection Plan for all installations authorized to work with radioactive material and a qualified Radiological Protection Supervisor. The CNEN requires the certification of practical experience in the area plus a qualification exam, applied by them. ATOMO, has opted to develop on-line courses, using multimedia resources, available at the time this congress takes place. OMICCRON, a multimedia enterprise, is in charge of the program and design. First, the research and brochures have to be adapted for the electronic language, through links, hot words and icons, especially developed for additional information. Besides the images and graphs from the original brochures, Omiccron developed, in graphic computing, specific animation explaining the procedures in more details, illustrating and simplifying the comprehension of the more complex subjects. The CD ROM presentation was enhanced with some slide displays, automatically changing the pictures, as the explanations are given. For practical visualization of these complex and important procedures, the CD also shows some technical videos. At the end of each unit covering a specific subject, the students will be submitted to self-evaluation tests, for more profitable results. This CD is not only an electronic brochure, but mainly an on-line course with weekly Internet support via e-mail or chat site, where the learners will access the instructors and a frequent questions database, useful links and related sites, permanently upgraded. Before going to the following module, the learner has to pass a written test prepared by ATOMO, via Internet. At the end of the course, a certificate will be given. The control will be made through the use of a password, provided for the authorized company and /or users. The instructors will evaluate the learners' advancement by Internet. In the case of companies, this tool will be equally offered, by using

  9. Assessment by peer review of the effectiveness of a regulatory programme for radiation safety. Interim report for comment

    International Nuclear Information System (INIS)

    This document covers assessment of those aspects of a radiation protection and safety infrastructure that are implemented by the Regulatory Authority for radiation sources and practices using such sources and necessarily includes those ancillary technical services, such as dosimetry services, which directly affect the ability of the Regulatory Authority to discharge its responsibilities. The focus of the guidance in this TECDOC is on assessment of a regulatory programme intended to implement the BSS. The BSS address transportation and waste safety mainly by reference to other IAEA documents. When conducting an assessment, the Review Team members should be aware of the latest IAEA documents (or similar national documents) concerning transportation and waste safety and, if appropriate, nuclear safety, and take them into account to the extent applicable when assessing the effectiveness of the regulatory programme governing radiation protection and safety of radiation source practices in a particular State

  10. Proceedings of the 6th annual meeting of Japanese Society of Radiation Safety Management 2007 Sendai

    International Nuclear Information System (INIS)

    This is the program and the proceedings of the 6th annual meeting of Japanese Society of Radiation Safety Management held from December 5th through the 7th of 2007. The sessions held were: (1) Radiation Measurement 1 to 3, (2) Radioactive Waste, (3) Radiation Safety Control 1 to 3, (4) Education Training, (5) Accelerator 1 and 2, and (6) Standardization and Future of Operation Environment Measurement. The number of poster presentations was 39. The topic of one symposium held was 'Influence of Low-dose Radiation'. This year, there were more keynote lectures than usual. Four keynote lectures by domestic researchers were: (1) 'Cutting Edge Medical Treatment Using Accelerator and Nuclear Reactor', (2) 'ICRO Recommendation and Concept of Dose Level', (3) 'Current Situation and Challenges of Radiation Regulation', and (4) 'Current Situation of Radioactive Waste Handling'. Including two keynote lectures by the international researchers from the United States and Croatia, six keynote lectures were held in total. (S.K.)

  11. Historical Role of Lauriston S. Taylor in American Radiation Safety and Protection

    OpenAIRE

    Yamashita, Shunichi

    2005-01-01

    What do we need to know about radiation, especially 60 years after the Atomic Bombing in Hiroshima and Nagasaki? It is a great honor and pleasure for me to introduce Dr. Lauriston Sale Taylor on this special occasion, who was a leader in American radiation safety and health protection before and after the Second World War. We can learn a lot from Dr. Taylor as well as from our own experience and knowledge on Atomic Bomb Survivors (Hibakusha): how to protect ourselves, how to protect our famil...

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

    Science.gov (United States)

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

    2015-04-01

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

  13. A contribution from fundamental and applied technetium chemistry to the nuclear waste disposal safety case

    Energy Technology Data Exchange (ETDEWEB)

    Totskiy, Yury; Yalcintas, Ezgi; Huber, Florian; Gaona, Xavier; Schaefer, Thorsten; Altmaier, Marcus; Geckeis, Horst [Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen (Germany). Inst. for Nuclear Waste Disposal; Kalmykov, Stepan [Lomonosov Moscow State Univ. (Russian Federation)

    2015-07-01

    concentrated solutions over the entire pH range. Complete and improved chemical, thermodynamic and activity (SIT, Pitzer) models were derived. The second part of this work focuses on applied Tc chemistry in near-natural systems. Interaction of Tc(VII) with crystalline rock material from a prospective repository site (Nizhnekansky massif, Russia) and from an underground research laboratory (AespoeHRL, Sweden) were studied. Drilling of the Aespoecores were performed under anoxic conditions. Part of the material was artificially oxidized to test the importance of sample preservation. Batch sorption studies under variation of the Tc(VII) concentration were performed in synthetic groundwater simulate to estimate the retention kinetics and R{sub s} values. For better understanding of the retention mechanisms, advanced surface sensitive analytics (XPS, XANES) were carried out and the data compared to reference systems. Tc migration behavior was further investigated by injections of Tc(VII)-containing groundwater simulant into the natural fracture in the unoxidized Aespoediorite core. The data obtained are compared with the results of batch sorption studies and will be used for subsequent geochemical reactive transport modeling. This work highlights the importance of combining fundamental Tc chemistry and applied studies in order to derive a comprehensive assessment of Tc mobilization and retention processes in support of the nuclear waste disposal Safety Case.

  14. A contribution from fundamental and applied technetium chemistry to the nuclear waste disposal safety case

    International Nuclear Information System (INIS)

    . Complete and improved chemical, thermodynamic and activity (SIT, Pitzer) models were derived. The second part of this work focuses on applied Tc chemistry in near-natural systems. Interaction of Tc(VII) with crystalline rock material from a prospective repository site (Nizhnekansky massif, Russia) and from an underground research laboratory (AespoeHRL, Sweden) were studied. Drilling of the Aespoecores were performed under anoxic conditions. Part of the material was artificially oxidized to test the importance of sample preservation. Batch sorption studies under variation of the Tc(VII) concentration were performed in synthetic groundwater simulate to estimate the retention kinetics and Rs values. For better understanding of the retention mechanisms, advanced surface sensitive analytics (XPS, XANES) were carried out and the data compared to reference systems. Tc migration behavior was further investigated by injections of Tc(VII)-containing groundwater simulant into the natural fracture in the unoxidized Aespoediorite core. The data obtained are compared with the results of batch sorption studies and will be used for subsequent geochemical reactive transport modeling. This work highlights the importance of combining fundamental Tc chemistry and applied studies in order to derive a comprehensive assessment of Tc mobilization and retention processes in support of the nuclear waste disposal Safety Case.

  15. Integrated software for imaging data analysis applied to edge plasma physic and operational safety

    Energy Technology Data Exchange (ETDEWEB)

    Martin, V.; Moncada, V. [CEA, IRFM, F-13108 Saint Paul-lez-Durance (France); Dunand, G. [Sophia Conseil Company, F-06560 Sophia Antipolis (France); Corre, Y.; Delchambre, E. [CEA, IRFM, F-13108 Saint Paul-lez-Durance (France); Travere, J.M., E-mail: jean-marcel.travere@cea.fr [CEA, IRFM, F-13108 Saint Paul-lez-Durance (France)

    2011-06-15

    Fusion tokamaks are complex devices requiring many diagnostics for real time control of the plasma and off-line physical analysis. In current tokamaks, imaging diagnostics have become increasingly used for these two purposes. Such systems produce a lot of data encouraging physicists to use shared tools and codes for data access and analysis. If general purpose software programs for data display and analysis are widely spread, a need exists in developing similar applications for quantitative imaging data analysis applied to plasma physic. In this paper, we introduce a new integrated software program, named WOLFF, dedicated to this task. The main contribution of this software is to gather under the same framework different functionalities for (1) data access and display, (2) signal, image, and video processing, and (3) quantitative analysis based on physical models. After an overview of existing solutions for data processing in the field of plasma data, we present the WOLFF architecture and its currently implemented features. The capabilities of the software are then demonstrated through three applications in the field of physical analysis (heat and particle flux calculations) and tokamak operational safety.

  16. Public information and education on radiation safety and protection in Indonesia

    Energy Technology Data Exchange (ETDEWEB)

    Djaloeis, Azhar [National Atomic Energy Agency, Jalan KH Abdul Rohim, Mampang Prapatan, Jakarta (Indonesia)

    1999-09-01

    This paper presents a brief overview of public information and education concerning nuclear science and technology in general and radiation safety and protection in particular in Indonesia from the perspective of promoting the development and utilization of nuclear science and technology in the country. The role of nuclear science and technology in Indonesia is first introduced, followed by an overview of the nuclear activities in the country. Basic considerations, major objectives of the public information and education program on radiation safety and protection as well as basic and operational strategies to achieve those objectives are then presented. Major programs including highlights of the past and present activities as well as prospect on future course of actions are discussed. (author)

  17. Public information and education on radiation safety and protection in Indonesia

    International Nuclear Information System (INIS)

    This paper presents a brief overview of public information and education concerning nuclear science and technology in general and radiation safety and protection in particular in Indonesia from the perspective of promoting the development and utilization of nuclear science and technology in the country. The role of nuclear science and technology in Indonesia is first introduced, followed by an overview of the nuclear activities in the country. Basic considerations, major objectives of the public information and education program on radiation safety and protection as well as basic and operational strategies to achieve those objectives are then presented. Major programs including highlights of the past and present activities as well as prospect on future course of actions are discussed. (author)

  18. Safety and radiation protection at the swedish nuclear power plants 1993-94

    International Nuclear Information System (INIS)

    Operational experiences from the fiscal year 1993/94 and safety analyses of the 12 swedish power reactors (9 BWRs and 3 PWRs) are reviewed in this report. The availability of the reactors has been high, except for three of the oldest reactors, which underwent major repair and renovation work. The occupational collective radiation dose amounted to 2.8 manSv per installed GW electric power, which is markedly above the target level of 2 manSv set by the Radiation Protection Institute. More than 70 percent of this dose originated in the repair of the old BWRs. Seven events of safety interest are reported, six of which have been classified as level 1 incidents on the INES-scale. 6 figs

  19. Communication with the public in radiation protection or nuclear safety and security

    International Nuclear Information System (INIS)

    Traditionally, the public perceives any peaceful application of atomic and nuclear physics as something very dangerous. It is not easy to eliminate the public's memories of nuclear bombings in Japan towards the end of World War II and subsequent nuclear weapons tests which resulted in spreading radioactive fallout across the globe. The current use of radiation and nuclear technologies in industry, medicine, science and other fields is known to meet very strict international safety standards ensuring the adequate protection of people's health and the minimization of threat to the environment. The paper summarizes the current problems in communicating radiation and nuclear safety to members of the public and focuses on the importance of using appropriate approaches as well as relevant terminology, including quantities and units for the realistic assessment of radiological exposure. (authors)

  20. Level of knowledge among the population of radiation safety basic issues

    Directory of Open Access Journals (Sweden)

    S. A. Zelencova

    2015-01-01

    Full Text Available The goal of research was to determine the level of knowledge among the population on issues like sources of ionising radiation, methods of ionising radiation measurement, measures of self-protection in case of threating or actual radioactive pollution in the district, and to study self-estimation by the population of their knowledge of radiation safety issues. Research was carried out using the method of questioning of population groups in three regions close to the places of previous peaceful nuclear explosions (Arkhangelsk, Murmansk and Tyumen regions, and in five Far East regions of the Russian Federation (Kamchatka, Khabarovsk, Primorsky, Magadan and South-Sakhalin regions after radiation accident in Japan at "Fukushima-1" NPP. This research included processing of 243 questionnaires from the regions close to places of previous peaceful nuclear explosions and 216 questionnaires from the Far East regions.The analysis of obtained questioning results enabled to make the following conclusions: the level of knowledge among the population about the basic concepts of radiation safety appeared to be generally low among respondents of all eight territories. Considerable number of respondents in seven groups correctly mentioned the x-ray device as a source of ionising radiation (from 71 to 88 % of answers. In Murmansk region – only 52 % of the answers. Respondents of the same seven groups often correctly answered the question on how to detect ionising radiation (only with devices – from 68 to 98 % in different groups. The smallest number of correct answers to this question (42 % is also noted among respondents from the Murmansk region.Level of knowledge on self-protection measures at threating or actual radioactive pollution of the places of residence appeared a little higher among the Far East region population, who had actual concerns regarding the threat of radioactive pollution at the present time. However, in all eight investigated groups

  1. Safety of radiation sources and the security of radioactive materials in Saudi Arabia

    International Nuclear Information System (INIS)

    The present status of the safety of radiation sources and the security of radioactive materials in Saudi Arabia is reviewed in details. Hazards and potential threat, material control and responsible parties, in addition to management and the technical requirements, are the main topics that are discussed. Some interest is given to the responsibilities of the regulatory authority, with special emphasis on the role of King Abdulaziz city for Science and Technology as a national competent authority. (author)

  2. Sweden's Co-operation with Eastern Europe in Radiation Safety 2011

    International Nuclear Information System (INIS)

    In 2011, the Swedish Radiation Safety Authority implemented co-operation projects in Russia, Ukraine, Georgia, Lithuania and Moldova, based on instructions from the Swedish Government and agreements with the European Union and the Swedish International Development Co-operation Agency, SIDA. The projects aim at achieving a net contribution to radiation safety (including nuclear safety, nuclear security, waste management, nonproliferation as well as radiation protection and emergency preparedness) for the benefit of the host countries and the international community as well as Sweden. This report gives an overview of all the projects implemented in 2011. The project managers from SSM are the cornerstones of our successful work, but all the efforts and dedication by staff members of the facilities and authorities in the mentioned countries are indispensable for the long-term positive outcomes. This report is meant to serve as a detailed account regarding SSM's efforts as part of the Swedish international activities, on which Sweden will report to the Nuclear Security Summit in Seoul. The parties to the G-8 Global Partnership have in June 2011 extended the Global Partnership for ten more years, till 2022. Other international frameworks, such as the UNSC Resolution 1540, remain a vibrant instrument by which UN Member States can exchange information on security concerns and request assistance from each other. The projects that SSM implements in Moldova and Georgia have a reference to the aims and purposes of the UNSC Resolution 1540. Much work has been done in the fields of nuclear security and safety, but there are still lots of issues that need to be taken care of. As such, SSM will continue to do its part for nuclear safety and security at the international level, along the lines and priorities set by our Government

  3. Sweden's Co-operation with Eastern Europe in Radiation Safety 2011

    Energy Technology Data Exchange (ETDEWEB)

    Dassen, Lars van; Andersson, Sarmite; Bejarano, Gabriela; Chirman, Inessa; Delalic, Zlatan; Ekblad, Christer; Karlberg, Olof; Klasen, Haakan; Olsson, Kjell; Sandberg, Viviana; Stenberg, Tor; Turner, Roland; Wickman, Barbro

    2012-11-01

    In 2011, the Swedish Radiation Safety Authority implemented co-operation projects in Russia, Ukraine, Georgia, Lithuania and Moldova, based on instructions from the Swedish Government and agreements with the European Union and the Swedish International Development Co-operation Agency, SIDA. The projects aim at achieving a net contribution to radiation safety (including nuclear safety, nuclear security, waste management, nonproliferation as well as radiation protection and emergency preparedness) for the benefit of the host countries and the international community as well as Sweden. This report gives an overview of all the projects implemented in 2011. The project managers from SSM are the cornerstones of our successful work, but all the efforts and dedication by staff members of the facilities and authorities in the mentioned countries are indispensable for the long-term positive outcomes. This report is meant to serve as a detailed account regarding SSM's efforts as part of the Swedish international activities, on which Sweden will report to the Nuclear Security Summit in Seoul. The parties to the G-8 Global Partnership have in June 2011 extended the Global Partnership for ten more years, till 2022. Other international frameworks, such as the UNSC Resolution 1540, remain a vibrant instrument by which UN Member States can exchange information on security concerns and request assistance from each other. The projects that SSM implements in Moldova and Georgia have a reference to the aims and purposes of the UNSC Resolution 1540. Much work has been done in the fields of nuclear security and safety, but there are still lots of issues that need to be taken care of. As such, SSM will continue to do its part for nuclear safety and security at the international level, along the lines and priorities set by our Government.

  4. Topical issues in nuclear, radiation and radioactive waste safety. Proceedings of an international conference

    International Nuclear Information System (INIS)

    The objective of the conference was 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 current status of these issues, priorities for future work and the need for strengthening international co-operation, including recommendations for the IAEA's future activities. The topical issues were grouped under the following six major headings: safety management; occupational radiation protection - trends and developments; backfitting, upgrading and modernization of nuclear power plants; situations of chronic exposure to residual radioactive materials - decommissioning and rehabilitation and reclamation of land; radiation safety in the distant future - the issue of long tern waste disposal; regulatory strategies. This volume contains the topical issue papers, the keynote presentations, the current issue presentations, the conclusions of the six technical sessions, and the conference chairperson's summary of findings and conclusions. Each of these papers has been provided with an abstract and indexed separately. Individual contributions to this conference have been published separately in the IAEA-TECDOC-1031. A CD-ROM containing contributed papers is attached to this book

  5. Proceedings of the national workshop on radiation safety and the Nigerian legal system

    International Nuclear Information System (INIS)

    This volume is the proceedings of the National Workshop on Radiation Safety and the Nigeria Legal System held at The Centre for Energy Research and Training, Ahmadu Bello University Zaria from 7 - 9 June, 1995. The Sole aim of the workshop was to encourage the Federal Government of Nigeria to promulgate the Decree on Nuclear Safety and Radiation Protection. The focal point of the workshop was the presentation of the various peaceful applications of nuclear energy in the national economy, albeit without any legal backing. Thus there were presentations from legal practitioners. Particular consideration was given to contribution from the Agency which dealt in great details with both the legal and infra structural requirements for nuclear safety and radiation protection. Presentation by the ministry of Foreign Affairs, Federal Ministry of Health and the Federal Environmental Protection Agency underscored the multi-sectoral and multi-dimensional nature of the concern. This volume contains the full text of 11 technical papers and also speeches by invited dignitaries presented at the workshop. The papers were fully discussed during the workshop. The organizing committee wishes to thank all authors for their presentation and cooperation in submitting manuscript promptly and the participants for there excellent contribution during the workshop

  6. Information report on nuclear safety and radiation protection of the Romans site - Issue 2014

    International Nuclear Information System (INIS)

    In compliance with the French Code of the Environment, this annual document describes the arrangements regarding nuclear safety and radiation protection, reports incidents and accidents of nuclear safety and radiation protection which must be declared according to this Code and which occurred within the installation, as well as the actions undertaken to limit their development and the consequences for people health for the environment, describes the nature and results of measurements of radioactive and not radioactive releases by the installation in the environment, describes the nature and quantities of radioactive wastes which are warehoused on the installation site as well as measures to limit their volume and their impact on health and on the environment, notably in soils and waters. After a presentation of the AREVA plant located in Romans-sur-Isere which comprises two basic nuclear installations (INB) and where fuel assemblies are manufactured, the different parts of this report address the measures regarding nuclear safety and radiation protection, nuclear events according to the INES scale, the management of releases by the different installations of this site and the control of the environment, the management of radioactive wastes, and the actions undertaken regarding information and transparency. Recommendations of the CHSCT are also reported

  7. Information report on nuclear safety and radiation protection of the Romans site - Issue 2013

    International Nuclear Information System (INIS)

    In compliance with the French Code of the Environment, this annual document describes the arrangements regarding nuclear safety and radiation protection, reports incidents and accidents of nuclear safety and radiation protection which must be declared according to this Code and which occurred within the installation, as well as the actions undertaken to limit their development and the consequences for people health for the environment, describes the nature and results of measurements of radioactive and not radioactive releases by the installation in the environment, describes the nature and quantities of radioactive wastes which are warehoused on the installation site as well as measures to limit their volume and their impact on health and on the environment, notably in soils and waters. After a presentation of the AREVA plant located in Romans-sur-Isere which comprises two basic nuclear installations (INB) and where fuel assemblies are manufactured, the different parts of this report address the measures regarding nuclear safety and radiation protection, nuclear events according to the INES scale, the management of releases by the different installations of this site and the control of the environment, the management of radioactive wastes, and the actions undertaken regarding information and transparency. Recommendations of the CHSCT are also reported

  8. Radiation-chemical concepts applied to the wholesomeness evaluation of irradiated foods

    International Nuclear Information System (INIS)

    Food irradiation has anomalously been classified as a food additive rather than as a processing method. The justification for this is that chemical changes take place during the process. However, most foodstuffs consist of a large number of constituents, most of which are present in small concentrations. As a result, the amounts of radiolysis products which may be formed are far too low for identification and measurement, even by conventional analytical methods. Radiation-chemical knowledge is applied to determine the probable nature and concentration of reaction products produced in fruits. Fruits consist mainly of water and carbohydrates, with small amounts of protein, fat, inorganic material and vitamins as 'contaminants'. The real situation is exceedingly complex, but, using this simple model as a first approximation, predictions which may be verified in a relatively simple experimental scheme are made on the radiation stability of a typical fruit. Calculations using known radiation-chemical data show that, in the case of the mango, only carbohydrates are present in sufficient concentration and of sufficient sensitivity to merit attention from a toxicological viewpoint. Experimentally, the radiation sensitivity of numerous constituents of the fruit has been compared with that of glucose and, apart from a few exceptions whose concentrations are minimal, results obtained agree well with predicted values

  9. Reporting nuclear power plant operation to the Finnish Centre for Radiation and Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    The Finnish Centre for Radiation and Nuclear safety (STUK) is the authority in Finland responsible for controlling the safety of the use of nuclear energy. The control includes, among other things, inspection of documents, reports and other clarification submitted to the STUK, and also independent safety analyses and inspections at the plant site. The guide presents what reports and notifications of the operation of the nuclear facilities are required and how they shall be submitted to the STUK. The guide does not cover reports to be submitted on nuclear material safeguards addressed in the guide YVL 6.10. Guide YVL 6.11 presents reporting related to the physical protection of nuclear power plants. Monitoring and reporting of occupational exposure at nuclear power plants is presented in the guide YVL 7.10 and reporting on radiological control in the environment of nuclear power plants in the guide YVL 7.8.

  10. Developing and implementing safety culture in the uses of radiation sources

    International Nuclear Information System (INIS)

    This paper presents an approach to develop and implement safety culture in the uses of radiation sources in medicine, industry, agriculture, research and teaching, and makes reference to the experience gained by the industries where that culture has been developed and improved, i.e. the nuclear industry. Suggestions to assist progress toward safety culture are here described for regulators, organisations using those sources, and professional associations. Even though emphasis is given to small organisations or teams of workers, this approach may be also useful to greater organisations like industrial irradiation companies or governmental research laboratories. In each case, parties being the principal focus of the learning process toward a progressive safety culture should be identified. (author)

  11. EDF - The Inspector General's report on Nuclear Safety and Radiation Protection 2009

    International Nuclear Information System (INIS)

    After a first chapter in which the Inspector General states his own vision of facts and results regarding nuclear safety and radiation protection for 2009, the relationship with the ASN (Nuclear safety authority), and also gives his own impression on the whole EDF nuclear system, the next chapters more particularly address the following topics: safety management, radiation protection of interveners, abilities and education for new challenges, the exploitation quality, the implementation of new regulatory arrangements, the extension of exploitation duration, the EPR project, the doctors as actors of safety management, service providing or subcontracting companies and fleet performance, prevention and struggle against fire, the activity of British Energy which is part of the EDF group, events which occurred within the EDF group (exposure of an intervener, incidents involving fuel components, biases in work monitoring, a fire on a turbo generator, an incident in Dungeness), lessons drawn from other industrial events (in a Russian hydroelectric station and in a refinery in Texas), and visits in China and in Japan

  12. EICT Based Diagnostic Tool and Monitoring System for EMF Radiation to Sustain Environmental Safety

    Directory of Open Access Journals (Sweden)

    K Parandham

    2013-10-01

    Full Text Available the adverse effects of electromagnetic radiation from mobile phones and communication towers on health issues are being well documented today. However, exact correlation between radiation of communication towers and their radiation levels, are not monitored. Aim of this paper is to study, analyze, apply networking and data mining technologies to develop an EICT based Diagnostic tool and Monitoring system for electromagnetic radiation levels into environment. This system is to network all mobile towers of each service provider as a single entity and then connect all service providers to a central monitoring agency online for continuous monitoring. Since very large numbers of mobile towers exist in India, each state can have its own regional network which is further networked with national central network. This can be enlarged to entire world for monitoring the EMF radiation levels near every mobile tower. For these regional national and international networks the connectivity is to be instituted by the respective service provider. In this paper an attempt is made to logically apply Data Mining and networking technologies to develop a central EICT based diagnostic tool and monitoring system for EMF radiation from each transmission tower. With this system regional, national and international agencies/authorities can monitor the EMF radiation at each and every transmission tower area continuously and verify them with exposure standards. It is proposed to display this information using Integrated Display System in front of monitoring authority at appropriate levels.

  13. Analysis of technologies and experiences for reducing occupational radiation dose and study for applying to regulations

    Energy Technology Data Exchange (ETDEWEB)

    Moon, Joo Hyun; Park, Moon Soo; Lee, Un Jang; Song, Jae Hyuk; Kim, Byeong Soo; Kim, Chong Uk [Seoul National Univ., Seoul (Korea, Republic of)

    2003-01-15

    To reduce Occupational Radiation Dose (ORD) effectively and enhance the radiological safety, the comprehensive assessment of the experiences to reduce ORD should be made by regulatory body as well as utilities. Hence, the objective of this study is to assess the experiences for reducing ORD from the regulatory viewpoint. With the research objective, the followings are performed in this research; analysis of occupational dose trends at domestic and foreign NPPs, identification of the effective technologies for reducing ORD, examination of the effects of the technologies for reducing ORD, derivation of the regulatory means for implementing he research results. From this study, the regulatory means for effective reduction of ORD are derived. Hence, the results can be utilized as a basic materials for ALARA requirements.

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

    Science.gov (United States)

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

    2016-06-01

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

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

    International Nuclear Information System (INIS)

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

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

    Science.gov (United States)

    Lopez, Richard Daniel

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

  17. Design of the EURISOL multi-MW target assembly: radiation and safety issues

    CERN Document Server

    Felcini, M; Kadi, Y; Otto, T; Tecchio, L; Otto, Th.

    2006-01-01

    The multi-MW target proposed for the EURISOL facility will be based on fission of uranium (or thorium) compounds to produce rare isotopes far from stability. A two-step process is used for the isotope production. First, neutrons are generated in a liquid mercury target, irradiated by the 1 GeV proton or deuteron beam, provided by the EURISOL linac driver. Then, the neutrons induce fission in a surrounding assembly of uranium carbide. R&D projects on several aspects of the target assembly are ongoing. Key criteria for the target design are a maximum beam power capability of 4 MW, a remote handling system with minimum downtime and maximum reliability, as well as radiation safety, minimization of hazards and the classification of the facility. In the framework of the ongoing radiation characterization and safety studies, radiation transport simulations have been performed to calculate the prompt radiation dose in the target and surrounding materials, as well as to determine shielding material and angle-depen...

  18. Design of the EURISOL multi-MW target assembly radiation and safety issues

    CERN Document Server

    Felcini, Marta; Kadi, Yacine; Otto, Thomas; Tecchio, L

    2006-01-01

    The multi-MW target proposed for the EURISOL facility will be based on fission of uranium (or thorium) compounds to produce rare isotopes far from stability. A two-step process is used for the isotope production. First, neutrons are generated in a liquid mercury target, irradiated by the 1 GeV proton or deuteron beam, provided by the EURISOL linac driver. Then, the neutrons induce fission in a surrounding assembly of uranium carbide. R&D projects on several aspects of the target assembly are ongoing. Key criteria for the target design are a maximum beam power capability of 4 MW, a remote handling system with minimum downtime and maximum reliability, as well as radiation safety, minimization of hazards and the classification of the facility. In the framework of the ongoing radiation characterization and safety studies, radiation transport simulations have been performed to calculate the prompt radiation dose in the target and surrounding materials, as well as to determine shielding material and angle-depen...

  19. Protection and safety of the application of radiation sources in medicine

    International Nuclear Information System (INIS)

    Creating working conditions that are safe and do not endanger health in connection with the application of ionizing radiation in health care means quite complicated tasks and obligations to the employees whose main orders concerning the application of radiation sources and radiation protection are determined in the Workplace Radiation Protection Regulation. At the same time, almost all internal regulations of health and security at work have a chapter on radiation (regulations of occupational safety, fire protection, etc.) The well-co-ordinated work of several experts and special fields is needed for taking protective measures and a far-reaching authority and supervising system takes care of keeping the rules and making the realization easier. Naturally, what has been written down here is only of summarising character. Its aim is to call the attention to the requirements in a form within the understanding of everybody with a high-level knowledge of the given technology and the professional requirements of radiation protection, and the widespread application of the legal and standard rules redownloaded in this writing are necessary for realising complex protection. (author)

  20. Nuclear data for radiation damage assessment and related safety aspects 1989

    International Nuclear Information System (INIS)

    The first Advisory Group Meeting on Nuclear Data for Radiation Damage Assessment and Related Safety Aspects was convened by NDS eight years ago in October 1981. The present meeting was a second one on this topic and it was intended to summarize the progress and status of nuclear data for radiation damage assessment since the first meeting. The participants have emphasized that since the first meeting a number of spallation neutron sources were put into operation and many material radiation damage studies are conducted now at these facilities. The distinguishing feature of spallation neutron sources is that the neutron energy spectra which they produce in most cases have a high energy component which may give a significant contribution to radiation damage. The proper understanding of radiation damage experiments in these neutron fields requires a better knowledge of nuclear data at high neutron energies. These ideas were formulated in detail in the conclusions and recommendations of the participants which are contained in this report. Another new issue was the need for activation cross-section data of long-lived isotopes. This topic is also considered in the conclusions below. The 14 presentations published in this proceedings were subdivided into three sessions: Characterization of neutron reactor environment, surveillance and nuclear data (5 papers); High energy neutron dosimetry and radiation damage calculations (6 papers); REAL-88 results and prospects (3 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

  1. The cohort of the atomic bomb survivors major basis of radiation safety regulations

    CERN Document Server

    Rühm, W; Nekolla, E A

    2006-01-01

    Since 1950 about 87 000 A-bomb survivors from Hiroshima and Nagasaki have been monitored within the framework of the Life Span Study, to quantify radiation-induced late effects. In terms of incidence and mortality, a statistically significant excess was found for leukemia and solid tumors. In another major international effort, neutron and gamma radiation doses were estimated, for those survivors (Dosimetry System DS02). Both studies combined allow the deduction of risk coefficients that serve as a basis for international safety regulations. As an example, current results on all solid tumors combined suggest an excess relative risk of 0.47 per Sievert for an attained age of 70 years, for those who were exposed at an age of 30 years. After exposure to an effective dose of one Sievert the solid tumor mortality would thus be about 50% larger than that expected for a similar cohort not exposed to any ionizing radiation from the bombs.

  2. A novel safety assessment strategy applied to non-selective extracts

    NARCIS (Netherlands)

    Koster, S.; Leeman, W.R.; Verheij, E.R.; Dutman, A.E.; Stee, L.L.P. van; Munch Nielsen, L.; Ronsmans, S.; Noteborn, H.; Krul, L.

    2015-01-01

    A main challenge in food safety research is to demonstrate that processing of foodstuffs does not lead to the formation of substances for which the safety upon consumption might be questioned. This is especially so since food is a complex matrix in which the analytical detection of substances, and c

  3. 77 FR 26287 - Cooperative Agreement To Support the Joint Institute for Food Safety and Applied Nutrition...

    Science.gov (United States)

    2012-05-03

    ... HUMAN SERVICES Food and Drug Administration Cooperative Agreement To Support the Joint Institute for... resources that focus on existing and emerging complex food/feed safety and public health issues. Continue... multidisciplinary and multi-institutional research programs and internationally- recognized food safety training...

  4. Present status of education for radiation safety during clinical examinations and the role of the radiological technologist

    International Nuclear Information System (INIS)

    The applications of radiation to the medical field are increasing steadily, along with advances in radiation technology and development of new medical equipment. Medical applications of radiation differ from applications in other fields, because the patient is exposed to radiation during examination and radiotherapy. Consequently, it is important that training courses in radiation safety for radiological technologists, medical doctors and nurses be periodically carried out to ensure a more effective and safe utilization of radiation. Furthermore, it is important that such training be based on a practical education curriculum, including basic knowledge, technical training, and safe habits. In this paper, we discuss the appropriate role and attitudes of the radiological technologist in radiation safety education. (author)

  5. International Expert Team Concludes IAEA Peer Review of Bulgaria's Regulatory Framework for Nuclear and Radiation Safety

    International Nuclear Information System (INIS)

    Full text: An international team of senior nuclear safety and radiation protection experts today concluded a 12-day mission to review the regulatory framework for nuclear and radiation safety in Bulgaria. The Integrated Regulatory Review Service (IRRS) mission, conducted at the request of the Government of Bulgaria, identified a series of good practices and made recommendations to help enhance the overall performance of the regulatory system. IRRS missions, which were initiated in 2006, are peer reviews based on the IAEA Safety Standards; they are not inspections or audits. ''Bulgaria has a clear national policy and strategy for safety, which are well in line with international standards and practices and contribute to a high level of nuclear safety,'' said Mission Team Leader Marta Ziakova, Chairperson of the Nuclear Regulatory Authority of the Slovak Republic. The mission team, which conducted the review from 8 to 19 April, was made up of 16 senior regulatory experts from 16 nations, and six IAEA staff. ''The results of the IRRS mission will be valuable for the future development and reinforcement of the Bulgarian Nuclear Safety Agency (BNRA). The use of international standards and good practices helps to improve global harmonization in all areas of nuclear safety and radiation protection,'' said Sergey Tzotchev, Chairman of the BNRA. Among the main observations in its preliminary report, the IRRS mission team found that BNRA operates as an independent regulatory body and conducts its regulatory processes in an open and transparent manner. In line with the IAEA Action Plan on Nuclear Safety, the mission reviewed the regulatory implications for Bulgaria of the March 2011 accident at TEPCO's Fukushima Daiichi Nuclear Power Station in Japan. It found that the BNRA's response to the lessons learned from that accident was both prompt and effective. Strengths and good practices identified by the IRRS team include the following: A no-blame policy is enshrined in law for

  6. Annual report of the Chief Executive Officer of Australian Radiation Protection And Nuclear Safety Agency, 2001-200

    International Nuclear Information System (INIS)

    In the period analysed ARPANSA contributed to the (then) Health and Aged Care portfolio's 'Outcome 1: Population Health and Safety'. The objective of this outcome was the promotion and protection of the health of all Australians and minimising the incidence of preventable mortality, illness, injury and disability. The main outcomes, as outlined in the reports are: regulation of Commonwealth activities involving radiation sources and nuclear facilities; progress towards the development of a National Directory for Radiation Protection; quality assurance programs in medical radiation and conduct evaluations of individual and population doses; health impact assessment of radiation exposure and methodologies for this assessment, recommendations and guidelines for limiting radiation exposure; progress towards third-party quality assurance certification for the personal radiation monitoring service, radionuclide analysis of gamma ray emitting nuclides, Ultraviolet Protection Factor; assessing radiopharmaceutical testing and the protection dosimeter calibration service; maintenance of a network for monitoring radionuclides in the atmosphere; safety standards and guidance in support of the work of the Radiation Health and Safety Advisory Council, the Radiation Health Committee and the Nuclear Safety Committee. The major priorities for ARPANSA in the reporting year, included the assessment of an application to construct the replacement research reactor at ANSTO, implementation of a process for public consultation and participation in the licensing of nuclear facilities and the development of national standards and codes of practice, including a standard for radiofrequency radiation

  7. Radiation safety criteria for mercury vapor lamps: proposed recommendations and notice of intent to develop performance standards

    International Nuclear Information System (INIS)

    Recommendations for mercury-vapor discharge-lamp radiation-safety criteria are proposed with an announcement of intent to develop a radiation safety performance standard for these lamps. Interested persons may submit comments until December 7. Such action is necessary due to the high efficiency and long life of mercury vapor lamps and their energy-saving role in illumination. They are widely used for lighting, including streets, school gyms, sports arenas, commercial stores and industrial facilities

  8. Investigation on the radiation induced conductivity of space-applied polyimide under cyclic electron irradiation

    Science.gov (United States)

    Yue, Long; Wu, Yiyong; Sun, Chengyue; Xiao, Jingdong; Shi, Yaping; Ma, Guoliang; He, Shiyu

    2012-11-01

    Radiation induced conductivity (RIC) is an important property of dielectric materials to evaluate the charge/discharge effect in orbit-service spacecraft. RIC of space-applied polyimide film was in situ measured and studied under continuous and cyclic electron irradiation in this paper. The results indicate that, for cyclic electron irradiation, there is a similar increasing-mode of RIC to those for continuous irradiation with the electron irradiation time. However, under the cyclic electron irradiation, the RIC of polyimide shows an obvious irradiation-history characteristic, namely preliminary irradiation dose effect (PIDE). In this case, the steady RIC value presents an "overshoot" behavior in the first few irradiation cycles and then decrease to a stable one as that under continuous irradiation. Prolonging the initial irradiation duration may avoid occurrence of overshoot phenomenon. The behaviors of irradiation-induced free radicals in polyimide could be applied to explain the RIC evolution processes.

  9. 75 FR 35366 - Pipeline Safety: Applying Safety Regulation to All Rural Onshore Hazardous Liquid Low-Stress Lines

    Science.gov (United States)

    2010-06-22

    ... potential environmental damage a release from these lines could pose, in 2006, PHMSA issued a NPRM (71 FR... of proposed rulemaking (SNPRM) (72 FR 28008) that proposed to apply all Part 195 requirements to any... two. PHMSA published the final rule on June 3, 2008 (73 FR 31634), which finalized the...

  10. How Can Synchrotron Radiation Techniques Be Applied for Detecting Microstructures in Amorphous Alloys?

    Directory of Open Access Journals (Sweden)

    Gu-Qing Guo

    2015-11-01

    Full Text Available In this work, how synchrotron radiation techniques can be applied for detecting the microstructure in metallic glass (MG is studied. The unit cells are the basic structural units in crystals, though it has been suggested that the co-existence of various clusters may be the universal structural feature in MG. Therefore, it is a challenge to detect microstructures of MG even at the short-range scale by directly using synchrotron radiation techniques, such as X-ray diffraction and X-ray absorption methods. Here, a feasible scheme is developed where some state-of-the-art synchrotron radiation-based experiments can be combined with simulations to investigate the microstructure in MG. By studying a typical MG composition (Zr70Pd30, it is found that various clusters do co-exist in its microstructure, and icosahedral-like clusters are the popular structural units. This is the structural origin where there is precipitation of an icosahedral quasicrystalline phase prior to phase transformation from glass to crystal when heating Zr70Pd30 MG.

  11. The opinion of the IRSN on the safety and radiation protection of the French electronuclear fleet in 2011

    International Nuclear Information System (INIS)

    In its first part, this annual report proposes a global assessment of safety and radiation protection in the exploited electronuclear fleet (trends noticed in 2011 in the field of safety and radiation protection). The second part discusses the various events, incidents and anomalies which occurred in 2011: anomalies in studies for safety demonstration, rate unbalance between safety injection lines in 900 MWe reactors, defects in a penetration at the bottom of a vessel of reactor nr 1 of the Gravelines power station, anomalies concerning pipe supports, incident of the 4 May 2011 on the reactor nr 1 of the Tricastin power station, human and organisational failures in reactor control. The last part comments significant evolutions: EDF approach for a continuous safety improvement, control of reactor ageing effects, high room temperature for safety injection pumps, hybrid cores, boil-over risk at the vicinity of Gravelines

  12. National infrastructures for radiation safety: Towards effective and sustainable systems. Proceedings of an international conference

    International Nuclear Information System (INIS)

    The use of ionizing radiation is widespread and virtually indispensable to modern society. For example, over 2.5 billion X ray examinations are conducted annually in the world. About 7000 electron accelerators are used for medical applications and materials enhancement; about 7000 ion accelerators are used for ion implantation; and hundreds of ion accelerators are used for applications, such as medical isotope production and medical therapy. About 12,000 industrial radiography sources are supplied annually; more than 10,000 medical radiotherapy units are in use; and about 300 irradiator facilities containing powerful radioactive sources are used for industrial applications. In addition to the many benefits afforded by the beneficial uses of radiation, there are also associated hazards, such as industrial accidents, medical overexposures, disposal of radioactive waste, environmental radioactivity, accidents from 'orphan' sources, and malevolent uses. For example, 'orphaned' radioactive sources have been melted accidentally into recycled metals on about 60 occasions in 20 countries, and accidental exposures to orphan sources have caused many accidents worldwide involving serious injury and loss of life. Even where there is a good infrastructure, such as in the United States of America and the European Union, hundreds of sources have been lost. Customs officials, border guards and police forces have detected numerous attempts to smuggle and illegally sell stolen sources. For example, the IAEA Illicit Trafficking Database includes over 280 confirmed incidents since 1993 that involved radioactive sources. In today's global societies, a problem in one country can have repercussions in many other countries. Therefore, it is essential for every country to have adequate infrastructures to ensure the safety and security of all radiation sources, including X ray machines, accelerators, sealed radioactive sources, radioactive waste and environmental radioactivity. A balance

  13. Researches in radiation protection and safety at Moscow engineering physics institute

    International Nuclear Information System (INIS)

    Department of Radiation Physics of Moscow Engineering Physics Institute is a research and teaching institution in the field of radiation protection, dosimetry, shielding and in radioecology. The scientific activity which has been doing at the department for many years includes the following directions: 1. Development of mathematical models and computational methods for an evaluation of external and internal exposure of people living on contaminated areas. Recently the computational model for forecast of internal irradiation via food chains was linked with computer geographical information systems. 2. Development of techniques and instruments for the measurements of radioactive contamination of soil, air, water and agricultural products. Department has special laboratory for this. 3. Application of computational methods to the problem of nuclear medicine. The whole body spectrometry and radiation 'coding' are used as an efficient methods of obtaining information on the radionuclides location in the human body. 4. Application of computational methods to the problem of radiation safety at nuclear power plants. It allows one to calculate radiation fields in shielding and the characteristics of nuclear wastes. (author)

  14. Information report on nuclear safety and radiation protection of the SOMANU site - Issue 2012

    International Nuclear Information System (INIS)

    Published in compliance with the French code of the environment, this report first presents different aspects of the SOMANU plant which is dedicated to the maintenance of materials and equipment from nuclear installations: location and environment, history, description of activities, regulatory framework. It describes the various measures regarding nuclear safety and radiation protection: general principles of nuclear safety, organization, presentation of the Areva's nuclear safety Charter, inspections and controls, measures regarding radiation protection. The next part addresses nuclear events which occurred on this site and had to be declared. The report gives an overview of activities and measures regarding the management of releases and the control of the environment. The next part addresses waste management: generalities on radioactive waste management in France, description and classification of radioactive wastes present in the INB, management of conventional wastes. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

  15. Information report on nuclear safety and radiation protection of the SOMANU site - Issue 2014

    International Nuclear Information System (INIS)

    Published in compliance with the French code of the environment, this report first presents different aspects of the SOMANU plant which is dedicated to the maintenance of materials and equipment from nuclear installations: location and environment, history, description of activities, regulatory framework. It describes the various measures regarding nuclear safety and radiation protection: general principles of nuclear safety, organization, presentation of the Areva's nuclear safety Charter, inspections and controls, measures regarding radiation protection. The next part addresses nuclear events which occurred on this site and had to be declared. The report gives an overview of activities and measures regarding the management of releases and the control of the environment. The next part addresses waste management: general considerations on radioactive waste management in France, description and classification of radioactive wastes present in the INB, management of conventional wastes. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

  16. GPU-based Monte Carlo Dust Radiative Transfer Scheme Applied to Active Galactic Nuclei

    Science.gov (United States)

    Heymann, Frank; Siebenmorgen, Ralf

    2012-05-01

    A three-dimensional parallel Monte Carlo (MC) dust radiative transfer code is presented. To overcome the huge computing-time requirements of MC treatments, the computational power of vectorized hardware is used, utilizing either multi-core computer power or graphics processing units. The approach is a self-consistent way to solve the radiative transfer equation in arbitrary dust configurations. The code calculates the equilibrium temperatures of two populations of large grains and stochastic heated polycyclic aromatic hydrocarbons. Anisotropic scattering is treated applying the Heney-Greenstein phase function. The spectral energy distribution (SED) of the object is derived at low spatial resolution by a photon counting procedure and at high spatial resolution by a vectorized ray tracer. The latter allows computation of high signal-to-noise images of the objects at any frequencies and arbitrary viewing angles. We test the robustness of our approach against other radiative transfer codes. The SED and dust temperatures of one- and two-dimensional benchmarks are reproduced at high precision. The parallelization capability of various MC algorithms is analyzed and included in our treatment. We utilize the Lucy algorithm for the optical thin case where the Poisson noise is high, the iteration-free Bjorkman & Wood method to reduce the calculation time, and the Fleck & Canfield diffusion approximation for extreme optical thick cells. The code is applied to model the appearance of active galactic nuclei (AGNs) at optical and infrared wavelengths. The AGN torus is clumpy and includes fluffy composite grains of various sizes made up of silicates and carbon. The dependence of the SED on the number of clumps in the torus and the viewing angle is studied. The appearance of the 10 μm silicate features in absorption or emission is discussed. The SED of the radio-loud quasar 3C 249.1 is fit by the AGN model and a cirrus component to account for the far-infrared emission.

  17. Safety, reliability, risk management and human factors: an integrated engineering approach applied to nuclear facilities

    International Nuclear Information System (INIS)

    Nuclear energy has an important engineering legacy to share with the conventional industry. Much of the development of the tools related to safety, reliability, risk management, and human factors are associated with nuclear plant processes, mainly because the public concern about nuclear power generation. Despite the close association between these subjects, there are some important different approaches. The reliability engineering approach uses several techniques to minimize the component failures that cause the failure of the complex systems. These techniques include, for instance, redundancy, diversity, standby sparing, safety factors, and reliability centered maintenance. On the other hand system safety is primarily concerned with hazard management, that is, the identification, evaluation and control of hazards. Rather than just look at failure rates or engineering strengths, system safety would examine the interactions among system components. The events that cause accidents may be complex combinations of component failures, faulty maintenance, design errors, human actions, or actuation of instrumentation and control. Then, system safety deals with a broader spectrum of risk management, including: ergonomics, legal requirements, quality control, public acceptance, political considerations, and many other non-technical influences. Taking care of these subjects individually can compromise the completeness of the analysis and the measures associated with both risk reduction, and safety and reliability increasing. Analyzing together the engineering systems and controls of a nuclear facility, their management systems and operational procedures, and the human factors engineering, many benefits can be realized. This paper proposes an integration of these issues based on the application of systems theory. (author)

  18. Radiation safety aspects of production of commercial levels of medical radioisotopes

    Science.gov (United States)

    Boothe, T. E.; McLeod, T. F.; Fernandez-Rubio, F.

    1993-06-01

    The first step toward efficient radiation safety in a facility that intends to produce commercial levels of radionuclides is to nticipate the scope of the facility during the design stages of the physical plant and during formulation of operating procedures. The design and operation must include flexibility to accommodate changing needs of production and research and development while providing radiation safety. A recently proposed licensing guide from the Bureau of Radiation Control, Texas Department of Health, while providing for safe operation, would severely limit flexibility and development. For example, engineering controls and procedures should be specified for generic systems as opposed to each specific radionuclide and by-products. Operator training is critical for reduced exposure and should be addressed, but requiring prior training for all operators is not reasonably achievable and would result in loss of proprietary information. Procedures to reduce exposure should include experimentally determined "cooldown" times, "problem indexes" for specific jobs related to particular cyclotrons, and proper management and administrative structures.

  19. International conference on national infrastructures for radiation safety: Towards effective and sustainable systems. Contributed papers

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA), in co-operation with the World Health Organization (WHO), the International Labour Office (ILO), the European Commission (EC), and the OECD Nuclear Energy Agency (NEA), organized the International Conference on National Infrastructures for Radiation Safety: Towards Effective and Sustainable Systems. This book contains contributed papers submitted on pertinent issues, including stakeholder involvement, IAEA Model Projects on Upgrading Radiation Protection Infrastructure, Quality Assurance, education and training, regulatory activities, performance evaluation, source security, and emergency preparedness. The material in this book has not been edited by the IAEA. These contributed papers will be published on a CD ROM as part of the Proceedings of the Conference, along with the invited papers and discussions. The papers are grouped by topical sessions: Stakeholder Involvement in Building and Maintaining National Radiation Safety Infrastructure (National and International); Implementation Experience with The Model Projects (Views From The Countries, Positive and Negative Experiences); Resources and Services (Systematic Approach), Quality Assurance, International Support Of Services; Sustainable Education And Training: Developing Skills (National Systems And Regional Solutions); Needs for Education And Training at The International Level (Including IAEA Programmes Assisting in Establishing Adequate Infrastructures); Authorization, Inspection and Enforcement (Effectiveness and Efficiency Of The Activities Of The Regulatory Bodies), Independence of Regulatory Authorities; Performance Evaluation; Source Security and Emergency Preparedness (Infrastructure Requirements at the International, National And User's Level)

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

    Science.gov (United States)

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

    2015-01-01

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

  1. A note on the net radiation method applied to a system composed of a semitransparent film between two glazings

    NARCIS (Netherlands)

    Zeegers, J.; Dijk, van H.A.L.

    1994-01-01

    The net radiation method is applied to obtain an expression for the thermal radiation heat transfer between a double glazed window unit which contains a semitransparent grey film in the cavity. The results are interpreted in terms of network modelling equations. The total heat transfer equals the re

  2. SAFETY

    CERN Multimedia

    C. Schaefer and N. Dupont

    2013-01-01

      “Safety is the highest priority”: this statement from CERN is endorsed by the CMS management. An interpretation of this statement may bring you to the conclusion that you should stop working in order to avoid risks. If the safety is the priority, work is not! This would be a misunderstanding and misinterpretation. One should understand that “working safely” or “operating safely” is the priority at CERN. CERN personnel are exposed to different hazards on many levels on a daily basis. However, risk analyses and assessments are done in order to limit the number and the gravity of accidents. For example, this process takes place each time you cross the road. The hazard is the moving vehicle, the stake is you and the risk might be the risk of collision between both. The same principle has to be applied during our daily work. In particular, keeping in mind the general principles of prevention defined in the late 1980s. These principles wer...

  3. Incident learning and failure-mode-and-effects-analysis guided safety initiatives in radiation medicine

    Directory of Open Access Journals (Sweden)

    Ajay eKapur

    2013-12-01

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

  4. Safety verification of radiation shielding and heat transfer for a model for dry

    Energy Technology Data Exchange (ETDEWEB)

    Yu, Haiyan, E-mail: yuhaiyan@nuaa.edu.cn [Department of Nuclear Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016 (China); Jiangsu Key Laboratory of Nuclear Energy Equipment Materials Engineering, Nanjing 210016 (China); Tang, Xiaobin, E-mail: tangxiaobin@nuaa.edu.cn [Department of Nuclear Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016 (China); Jiangsu Key Laboratory of Nuclear Energy Equipment Materials Engineering, Nanjing 210016 (China); Wang, Peng, E-mail: wp739130046@nuaa.edu.cn [Department of Nuclear Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016 (China); Jiangsu Key Laboratory of Nuclear Energy Equipment Materials Engineering, Nanjing 210016 (China); Chen, Feida, E-mail: fdchen@nuaa.edu.cn [Department of Nuclear Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016 (China); Jiangsu Key Laboratory of Nuclear Energy Equipment Materials Engineering, Nanjing 210016 (China); Chai, Hao, E-mail: chaihao@nuaa.edu.cn [Department of Nuclear Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016 (China); Jiangsu Key Laboratory of Nuclear Energy Equipment Materials Engineering, Nanjing 210016 (China); Chen, Da, E-mail: chenda@nuaa.edu.cn [Department of Nuclear Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016 (China); Jiangsu Key Laboratory of Nuclear Energy Equipment Materials Engineering, Nanjing 210016 (China)

    2015-09-15

    Highlights: • New type of dry spent fuel storage was designed. • MC method and FEM were used to verify the reliability of new storage. • Radiation shield and heat transfer both meet IAEA standards: 2 mSv/h, 0.1 mSv/h and 190 °C, 85 °C. • Provided possibilities for future implementation of this type of dry storage. - Abstract: The goal of this research is to develop a type of dry spent fuel storage called CHN-24 container, which could contain an equivalent load of 45 GWD/MTU of spent fuel after 10 years cooling. Basically, radiation shielding performance and safe removal of decay heat, which play important roles in the safety performance, were checked and validated using the Monte Carlo method and finite element analysis to establish the radiation dose rate calculation model and three-dimensional heat transfer model for the CHN-24 container. The dose rates at the surface of the container and at a distance of 1 m from the surface were 0.42 mSv/h and 0.06 mSv/h, respectively. These conform to the International Atomic Energy Agency (IAEA) radioactive material transportation safety standards 2 mSv/h and 0.1 mSv/h. The results shows that the CHN-24 container maintains its structural and material integrity under the condition of normal thermal steady-state heat transfer as well as in case of extreme fire as evinced by transient-state analysis. The temperature inside and on the surface of the container were 150.91 °C and 80 °C under normal storage conditions, which indicated that the design also conform to IAEA heat transfer safety standards of 190 °C and 85 °C.

  5. Safety verification of radiation shielding and heat transfer for a model for dry

    International Nuclear Information System (INIS)

    Highlights: • New type of dry spent fuel storage was designed. • MC method and FEM were used to verify the reliability of new storage. • Radiation shield and heat transfer both meet IAEA standards: 2 mSv/h, 0.1 mSv/h and 190 °C, 85 °C. • Provided possibilities for future implementation of this type of dry storage. - Abstract: The goal of this research is to develop a type of dry spent fuel storage called CHN-24 container, which could contain an equivalent load of 45 GWD/MTU of spent fuel after 10 years cooling. Basically, radiation shielding performance and safe removal of decay heat, which play important roles in the safety performance, were checked and validated using the Monte Carlo method and finite element analysis to establish the radiation dose rate calculation model and three-dimensional heat transfer model for the CHN-24 container. The dose rates at the surface of the container and at a distance of 1 m from the surface were 0.42 mSv/h and 0.06 mSv/h, respectively. These conform to the International Atomic Energy Agency (IAEA) radioactive material transportation safety standards 2 mSv/h and 0.1 mSv/h. The results shows that the CHN-24 container maintains its structural and material integrity under the condition of normal thermal steady-state heat transfer as well as in case of extreme fire as evinced by transient-state analysis. The temperature inside and on the surface of the container were 150.91 °C and 80 °C under normal storage conditions, which indicated that the design also conform to IAEA heat transfer safety standards of 190 °C and 85 °C

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Ford, E [University of Washington, Seattle, WA (United States); Ezzell, G [Mayo Clinic Arizona, Phoenix, AZ (United States); Miller, B [Henry Ford Health System, Clinton Township, MI (United States); Yorke, E [Memorial Sloan-Kettering Cancer Center, New York, NY (United States)

    2014-06-15

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

  8. Research projects of the Finnish Centre for Radiation and Nuclear Safety 1996-1997; Saeteilyturvakeskuksen tutkimushankkeet 1996-1997

    Energy Technology Data Exchange (ETDEWEB)

    Mustonen, R.; Koponen, H. [eds.

    1996-02-01

    The research activities of the Finnish Centre for Radiation and Nuclear Safety (STUK) are based on the Centre`s primary task of preventing and restricting adverse effects of radiation. As a rule, studies concerning nuclear safety (part 1 of the publication) are studies originating from the regulatory function of STUK; these are directed and funded by the Centre but the Centre does not carry them out itself. In contrast, studies dealing with radiation exposure and health risks (part 2 of the publication) are conducted by the Centre itself, often in cooperation with some other research institute or university. Results of these studies are published in open scientific literature.

  9. Annual Report 2003 on the Radiation and Nuclear Safety in the Republic of Slovenia

    International Nuclear Information System (INIS)

    This report is a continuation of a practice which was introduced a year ago. This short report provides in a condensed form the essential data on the situation in the country in the areas of radiation protection and nuclear safety, and is aimed at a wider group of interested public. In parallel, an extended report was prepared consisting of all the details and data which would be of interest to a narrower group of professionals. It is available in electronic form on CD or at the home page of the SNSA.

  10. Graphs of neutron cross sections in JSD1000 for radiation shielding safety analysis

    International Nuclear Information System (INIS)

    Graphs of neutron cross sections and self-shielding factors in the JSD1000 library are presented for radiation shielding safety analysis. The compilation contains various reaction cross sections for 42 nuclides from 1H to 241Am in the energy range from 3.51 x 10-4 eV to 16.5 MeV. The Bondarenko-type self-shielding factors of each reaction are given by the background cross sections from σ0 = 0 to σ0 = 10000. (author)

  11. WINRE '92 - 3rd workshop on information management in nuclear safety, radiation protection, and environmental protection

    International Nuclear Information System (INIS)

    The workshop puts much emphasis on the exchange of experience between experts from the West and from the Central and Eastern European countries. The representatives from the various countries and organisations are going to introduce their respective data banks, products, or services. The combination of papers and practical presentations will provide all with a qualified and comprehensive insight into the tried and tested as well as the new information management technologies in the specialist areas of nuclear safety, radiation protection, and environmental protection. Furthermore, it should also contribute to the promotion of the transfer of know-how between experts throughout the whole of Europe. (orig./DG)

  12. Annual report 2003 on the radiation and nuclear safety in the Republic of Slovenia

    International Nuclear Information System (INIS)

    This report is a continuation of a practice which was introduced a year ago. This short report provides in a condensed form the essential data on the situation in the country in the areas of radiation protection and nuclear safety, and is aimed at a wider group of interested public. In parallel, an extended report was prepared consisting of all the details and data which would be of interest to a narrower group of professionals. It is available in electronic form on CD or at the home page of the SNSA. (author)

  13. Annual report 2004 on the radiation and nuclear safety in the Republic of Slovenia

    International Nuclear Information System (INIS)

    This short report is a continuation of the practice introduced two years ago. It provides in a condensed form the essential data on the status in the areas of radiation protection and nuclear safety in the country, and is aimed at a wider group of interested public. In parallel, an extended report was prepared consisting of all the details and data which would be of interest to a narrower group of professionals. It is available in electronic form on a CD-ROM or at the home page of the SNSA. (author)

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

    Science.gov (United States)

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

    2016-09-01

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

  15. Improving health, safety and energy efficiency in New Zealand through measuring and applying basic housing standards.

    Science.gov (United States)

    Gillespie-Bennett, Julie; Keall, Michael; Howden-Chapman, Philippa; Baker, Michael G

    2013-08-01

    Substandard housing is a problem in New Zealand. Historically there has been little recognition of the important aspects of housing quality that affect people's health and safety. In this viewpoint article we outline the importance of assessing these factors as an essential step to improving the health and safety of New Zealanders and household energy efficiency. A practical risk assessment tool adapted to New Zealand conditions, the Healthy Housing Index (HHI), measures the physical characteristics of houses that affect the health and safety of the occupants. This instrument is also the only tool that has been validated against health and safety outcomes and reported in the international peer-reviewed literature. The HHI provides a framework on which a housing warrant of fitness (WOF) can be based. The HHI inspection takes about one hour to conduct and is performed by a trained building inspector. To maximise the effectiveness of this housing quality assessment we envisage the output having two parts. The first would be a pass/fail WOF assessment showing whether or not the house meets basic health, safety and energy efficiency standards. The second component would rate each main assessment area (health, safety and energy efficiency), potentially on a five-point scale. This WOF system would establish a good minimum standard for rental accommodation as well encouraging improved housing performance over time. In this article we argue that the HHI is an important, validated, housing assessment tool that will improve housing quality, leading to better health of the occupants, reduced home injuries, and greater energy efficiency. If required, this tool could be extended to also cover resilience to natural hazards, broader aspects of sustainability, and the suitability of the dwelling for occupants with particular needs.

  16. Distance-Based Access Modifiers Applied to Safety in Home Networks

    DEFF Research Database (Denmark)

    Mortensen, Kjeld Høyer; Schougaard, Kari Rye; Schultz, Ulrik Pagh

    2004-01-01

    be performed within a physical proximity that ensures safety. We use a declarative approach integrated with an IDL language to express location-based restrictions on operations. This model has been implemented in a middleware for home audio-video devices, using infrared communication and a local-area network......Home networks and the interconnection of home appliances is a classical theme in ubiquitous computing research. Security is a recurring concern, but there is a lack of awareness of safety: preventing the computerized house from harming the inhabitants, even in a worst-case scenario where...

  17. Implementation of national radiation safety regulations in Sri Lanka: A beginning to conform to international standards

    International Nuclear Information System (INIS)

    The Atomic Energy Authority (AEA) of Sri Lanka was established in 1970 by the legislation Atomic Energy Authority Act No.19 of 1969. Since the act was enacted 03 decades ago, the recent advances and needs were not identified. The AEA was empowered to carry out promotional activities of nuclear technology as well as regulatory activities. Under the provisions made in the act the Atomic Energy Regulations of 1975 were promulgated to regulate the activities related to radiation in the country until year 2000. Having realized that these regulations are not sufficient to meet the current international requirements with the technological advances in the fields 'Ionizing Radiation Protection Regulations' which conforms to the IAEA's Basic Safety Standards-115 were promulgated in year 2000. Even though the new regulations were made under the same act, the AEA could achieve a positive improvement in regulatory activities in use of ionizing radiation in the country by establishing a good system for implementation of a notification, licensing, and inspection programmes to conform to the International requirements. Three codes of practices have been drafted and are under review and few manuals have been printed for distribution among the radiation users. Two regulations on safe transport of radioactive material and radioactive waste management have to be promulgated and steps have been initiated in this regard. Assistance from the IAEA was received to strengthen the regulatory infrastructure in Sri Lanka under the model project in radiation protection. Also IAEA has carried out several missions to assess the regulatory effectiveness in Sri Lanka. These missions state the successful achievement of milestones I and II of the IAEA model project on Strengthening and Harmonization of Radiation Protection. However it is identified that amendment of the act is a timely requirement for the effective independence of the regulatory activities carried out by the AEA. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-12-17

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

  19. Features, events, processes, and safety factor analysis applied to a near-surface low-level radioactive waste disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    Stephens, M.E.; Dolinar, G.M.; Lange, B.A. [Atomic Energy of Canada Limited, Ontario (Canada)] [and others

    1995-12-31

    An analysis of features, events, processes (FEPs) and other safety factors was applied to AECL`s proposed IRUS (Intrusion Resistant Underground Structure) near-surface LLRW disposal facility. The FEP analysis process which had been developed for and applied to high-level and transuranic disposal concepts was adapted for application to a low-level facility for which significant efforts in developing a safety case had already been made. The starting point for this process was a series of meetings of the project team to identify and briefly describe FEPs or safety factors which they thought should be considered. At this early stage participants were specifically asked not to screen ideas. This initial list was supplemented by selecting FEPs documented in other programs and comments received from an initial regulatory review. The entire list was then sorted by topic and common issues were grouped, and issues were classified in three priority categories and assigned to individuals for resolution. In this paper, the issue identification and resolution process will be described, from the initial description of an issue to its resolution and inclusion in the various levels of the safety case documentation.

  20. Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety, Regional Meeting on International Radiation Protection Association (IRPA)and 3. Peruvian Meeting on Radiological Protection

    International Nuclear Information System (INIS)

    There we show works of the Third Regional Meeting on Radiological and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin americans specialists talk about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. Also we deal with subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation. More than 225 works were presented on the meeting

  1. Multidisciplinary training program to create new breed of radiation monitor: the health and safety technician

    International Nuclear Information System (INIS)

    A multidiscipline training program established to create a new monitor, theHealth and Safety Technician, is described. The training program includes instruction in fire safety, explosives safety, industrial hygiene, industrial safety, health physics, and general safety practices

  2. Multigroup Albedo Method applied to coupled neutron-gamma radiations shielding

    International Nuclear Information System (INIS)

    Shielding calculations for neutron-gamma radiation are usually done by using the full Theory of Transport or the Monte Carlo Techniques. After some works based on the Albedo Method, the shielding calculations for neutron-gamma radiation have a reliable tool with great didactical value which shows its clarity and simplicity for the resolution of cases that involve neutrons and photon shielding in nonmultiplying media. The excellent results of these works have motivated the elaboration and the development of this study that will be presented in this dissertation. The balance of a neutronic current entering a shield of two layers considering the coupling neutron-gamma will be determined by the Albedo Method. The shield will be composed of a layer of iron and another one of manganese with 10 cm of thickness each. The arrays of the materials coefficients will be obtained from the ANISN code. ANISN is a one dimensional deterministic code that is based on transport equation. The final results obtained by the Albedo Method will be compared with the ANISN results for an order of angular quadrature S2. The angular quadrature S2 admits that the radiation has two routes in the same direction what better describes the Albedo Method behavior. The results obtained by using the Albedo Method show an excellent agreement with the values predicted by the adopted deterministic code ANISN. Due to the excellent results, the multigroup Albedo Method should be applied to the shielding calculations with multiple layers. In conclusion the multigroup Albedo Method has the great ability in solving shielding problems concerning to the Nuclear Engineering. (author)

  3. Applying the Food Safety Objective and related concepts to thermal inactivation of Salmonella in poultry meat

    NARCIS (Netherlands)

    Membré, J.M.; Bassett, J.; Gorris, L.G.M.

    2007-01-01

    The objective of this study was to investigate the practicality of designing a heat treatment process in a food manufacturing operation for a product governed by a Food Safety Objective (FSO). Salmonella in cooked poultry meat was taken as the working example. Although there is no FSO for this produ

  4. Feasibility-Seeking and Superiorization Algorithms Applied to Inverse Treatment Planning in Radiation Therapy

    CERN Document Server

    Davidi, R; Schulte, R W; Geneser, S; Xing, L

    2014-01-01

    We apply the recently proposed superiorization methodology (SM) to the inverse planning problem in radiation therapy. The inverse planning problem is represented here as a constrained minimization problem of the total variation (TV) of the intensity vector over a large system of linear two-sided inequalities. The SM can be viewed conceptually as lying between feasibility-seeking for the constraints and full-fledged constrained minimization of the objective function subject to these constraints. It is based on the discovery that many feasibility-seeking algorithms (of the projection methods variety) are perturbation-resilient, and can be proactively steered toward a feasible solution of the constraints with a reduced, thus superiorized, but not necessarily minimal, objective function value.

  5. Effects of applied strain on radiation damage generation in body-centered cubic iron

    Energy Technology Data Exchange (ETDEWEB)

    Beeler, Benjamin, E-mail: bwbeeler@ucdavis.edu [Department of Mechanical and Aerospace Engineering, University of California, Davis, CA 95616 (United States); Department of Materials Science, University of California, Berkeley, CA 94720 (United States); Asta, Mark [Department of Materials Science, University of California, Berkeley, CA 94720 (United States); Hosemann, Peter [Department of Nuclear Engineering, University of California, Berkeley, CA 94720 (United States); Grønbech-Jensen, Niels [Department of Mechanical and Aerospace Engineering, University of California, Davis, CA 95616 (United States); Department of Mathematics, University of California, Davis, CA 95616 (United States)

    2015-04-15

    Radiation damage in body-centered cubic (BCC) Fe has been extensively studied by computer simulations to quantify effects of temperature, impinging particle energy, and the presence of extrinsic particles. However, limited investigation has been conducted into the effects of mechanical stresses and strain. In a reactor environment, structural materials are often mechanically strained, and an expanded understanding of how this strain affects the generation of defects may be important for predicting microstructural evolution and damage accumulation under such conditions. In this study, we have performed molecular dynamics simulations in which various types of homogeneous strains are applied to BCC Fe and the effect on defect generation is examined. It is found that volume-conserving shear strains yield no statistically significant variations in the stable number of defects created via cascades in BCC Fe. However, strains that result in volume changes are found to produce significant effects on defect generation.

  6. Effects of applied strain on radiation damage generation in body-centered cubic iron

    Science.gov (United States)

    Beeler, Benjamin; Asta, Mark; Hosemann, Peter; Grønbech-Jensen, Niels

    2015-04-01

    Radiation damage in body-centered cubic (BCC) Fe has been extensively studied by computer simulations to quantify effects of temperature, impinging particle energy, and the presence of extrinsic particles. However, limited investigation has been conducted into the effects of mechanical stresses and strain. In a reactor environment, structural materials are often mechanically strained, and an expanded understanding of how this strain affects the generation of defects may be important for predicting microstructural evolution and damage accumulation under such conditions. In this study, we have performed molecular dynamics simulations in which various types of homogeneous strains are applied to BCC Fe and the effect on defect generation is examined. It is found that volume-conserving shear strains yield no statistically significant variations in the stable number of defects created via cascades in BCC Fe. However, strains that result in volume changes are found to produce significant effects on defect generation.

  7. International Nuclear and Radiation Safety Experts Conclude IAEA Peer Review of Slovenia's Regulatory System

    International Nuclear Information System (INIS)

    Full text: An international team of senior nuclear safety experts today concluded a 10-day mission to review the regulatory framework for nuclear and radiation safety in Slovenia. The team identified good practices and gave advice on areas for future improvements. The IAEA has conveyed the team's main conclusions to the Government of Slovenia and a final report will be submitted by the end of 2011. At the request of the Slovenian Government, the IAEA assembled a team of 10 senior regulatory experts from nine nations to conduct the Integrated Regulatory Review Service (IRRS) mission involving the Slovenian Nuclear Safety Administration (SNSA). The mission is a peer review based on the IAEA Safety Standards. Andrej Stritar, Director of Slovenian Nuclear Safety Administration, stressed ''how important it is for a small country like Slovenia to tightly follow international standards in the area of nuclear safety.'' He also expressed his gratitude to the IAEA, and the countries from which team members came, for their support and for their intensive work during the last ten days. Mission Team Leader Colin Patchett, Deputy Chief Inspector from the UK's Office for Nuclear Regulation commended ''the Slovenian authorities for their commitment to nuclear and radiation safety regulation and for sharing their experience.'' The IRRS team reviewed Slovenia's current regulatory framework and all SNSA-regulated facilities and activities, as well as the regulatory implications of the TEPCO Fukushima Daiichi accident. The IRRS team identified particular strengths in the Slovenian regulatory system, including: Through its legal framework, the Slovenian government has appointed SNSA to regulate its nuclear safety program and SNSA has in place an effective process for carrying out this responsibility; and Slovenia's response to the accident at the TEPCO Fukushima Daiichi power plant has been prompt and effective. Communications with the public, development of actions for improvement

  8. International Expert Team Concludes IAEA Peer Review of Finland's Regulatory Framework for Nuclear and Radiation Safety

    International Nuclear Information System (INIS)

    Full text: International safety experts today concluded a two-week International Atomic Energy Agency (IAEA) mission to review the regulatory framework for nuclear and radiation safety in Finland. In its preliminary report, the Integrated Regulatory Review Service (IRRS) mission team found that the Radiation and Nuclear Safety Authority of Finland (STUK) is a competent and highly credible regulator that is open and transparent and derives great strength from the technical competence of its staff. ''Finland's comprehensive regulatory framework allows STUK to operate in practice as an independent regulatory body,'' said team leader Philippe Jamet, a commissioner of the French regulatory body ASN. The mission was conducted at the request of the Government of Finland from 15-26 October. The team interviewed members of STUK and officials from various ministries, as well as key players in the Finnish safety framework. Such IRRS missions are peer reviews based on IAEA Safety Standards, not inspections or audits. The team was made up of 18 members from Bulgaria, Canada, the Czech Republic, France, Germany, Iceland, Ireland, Romania, the Russian Federation, South Africa, Slovakia, Slovenia, Spain, Sweden, the United Arab Emirates, the United Kingdom and the United States, as well as six IAEA staff members. 'The IRRS mission and preparation for it was a unique occasion that involved the whole organization, provided motivation for improvement of the safety framework in Finland and assists STUK review its mission', said Tero Varjoranta, Director General of STUK. The IRRS team identified a number of good practices and achievements, including: - STUK's excellence in its safety assessment of nuclear power plants and waste repositories, in particular its demonstration that long-term political commitment is a necessity to sustain the creation of a waste repository as well as its regulatory oversight of medical applications of radiation sources; and - STUK's excellent record in

  9. A Survey of the Ideas of Radiation Safety Officers: A Case Study on Operation Problems

    International Nuclear Information System (INIS)

    Full text: The objectives of this survey research are to study radiation safety operation problems of radiation safety officers (RSOs). The RSOs data were collected and the concerned laws were reviewed to design the questionnaires which composed of general, experiences, operation problems and comments/suggestions. The questionnaires were submitted to RSOs, who were certified from Office of Atoms for Peace (OAP) and who had not been certified yet, and 468 sets of replies were obtained. The results were analyzed by descriptive statistics with SPSS 11.5 software to calculate frequencies, percentages, averages, and standard deviations (S.D.). The maximum responses came from the persons who passed the examination to be certified as medium level RSOs around 72.6%. The results showed that their working experiences were high (50-53.4%) and medium (44.7-50%) with averages of 3.4-3.8 and S.D. of 0.8-0.9. Their operation problems were at medium level (24.1-44.2%) with the averages of 2.9-3.2 and S.D. of 1.3-1.8. In conclusion, most of RSOs have operation experiences but they still have some problems. From their comments/suggestions, some do not agree with examination/certification and need OAP to improve working. These results lead to the improvements of RSOs examination/certification, OAP working systems, and RSO refreshment courses

  10. The basis and safety of food irradiation. Advantages of radiation treatment for food sanitation and storage

    Energy Technology Data Exchange (ETDEWEB)

    Ito, Hitoshi [Japan Atomic Energy Research Inst., Takasaki, Gunma (Japan). Takasaki Radiation Chemistry Research Establishment

    2001-09-01

    The food irradiation has the history of more than 60 years in its development. However, its commercial application has not been promoted well in Japan even though the safety of irradiated foods was confirmed. Recently, relevant authorities in 52 countries have given clearance to many commodities, and irradiated foods are commercially distributed in USA and EU countries. The international situation makes some unavoidable circumstances which can not close the commercialization of food irradiation in Japan. The present report contains the basis and application of food irradiation, and history of development in the World and Japan. Moreover, the safety of irradiated foods are demonstrated from many evidences of researches in animal feeding tests, in analysis of radiolytic products, in nutritional evaluations and in microbiological studies of irradiated foods. Especially, it makes obvious from the results of many researches that unique radiolytic products can not be produced by irradiation of foods. Because main radiation effects are induced by oxidation degradation of food components as similar to natural oxidation by heating or UV light. Radiation engineering for commercial process and identification methods of irradiated foods are also presented. (author)

  11. The basis and safety of food irradiation. Advantages of radiation treatment for food sanitation and storage

    International Nuclear Information System (INIS)

    The food irradiation has the history of more than 60 years in its development. However, its commercial application has not been promoted well in Japan even though the safety of irradiated foods was confirmed. Recently, relevant authorities in 52 countries have given clearance to many commodities, and irradiated foods are commercially distributed in USA and EU countries. The international situation makes some unavoidable circumstances which can not close the commercialization of food irradiation in Japan. The present report contains the basis and application of food irradiation, and history of development in the World and Japan. Moreover, the safety of irradiated foods are demonstrated from many evidences of researches in animal feeding tests, in analysis of radiolytic products, in nutritional evaluations and in microbiological studies of irradiated foods. Especially, it makes obvious from the results of many researches that unique radiolytic products can not be produced by irradiation of foods. Because main radiation effects are induced by oxidation degradation of food components as similar to natural oxidation by heating or UV light. Radiation engineering for commercial process and identification methods of irradiated foods are also presented. (author)

  12. 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)

  13. Management of a comprehensive radiation safety program in a major American University and affiliated academic medical center

    International Nuclear Information System (INIS)

    Duke University, which operates under eight radiation licenses issued by the State of North Carolina, consists of a leading medical center including extensive inpatient and outpatient facilities, a medical school, biomedical research labs, and an academic campus including two major accelerator facilities. The Nuclear Medicine and Radiation Oncology departments handle over 40,000 diagnostic and therapeutic procedures annually, including approximately 160 radioiodine therapeutic cases. In biomedical research labs, about 300 professors are authorized to use radioactive materials. Over 2,000 radiation workers are identified on campus. Over the past two years, we have transformed the existing radiation safety program into a more responsive and more accountable one. Simultaneously, the institutional 'culture' changed, and the Radiation Safety Division came to be viewed as a helpful ally by investigators. The purpose of this paper is to present our experiences that have made this transformation possible. Our initiatives included; (a) defining short-term and long-term goals; (b) establishing a definitive chain of authority; (c) obtaining an external review by a consultant Health Physicist; (d) improving existing radiation safety programs; (e) reorganizing the Radiation Safety Division, with creation of multidisciplinary professional staff positions; (f) implementing campus-wide radiation safety training, (g) increasing technician positions; (h) establishing monthly medical center radiation safety executive meeting. As a result progress made at the Divisional level includes; (a) culture change by recruiting professionals with academic credentials and recent college graduates; (b) implementing weekly staff meetings and monthly quality assurance meetings; (c) achieving academic prominence by publishing and presenting papers in national meetings; (d) senior staff achieving faculty appointments with academic departments; (e) senior staff participating in graduate student

  14. Reliability analysis and safety of digital systems applied to nuclear reactor protection

    International Nuclear Information System (INIS)

    A method for developing digital protection systems based upon reliability and safety requirements has been proposed. Directives for assessing such conditions are suggested. Techniques and the most common tools employed in hardware evaluation and modelling of such architectures have also been shown. In order to estimate the software quality, several mechanisms to control design, specification, and validation and verification (V and V) procedures are suggested. (author). 12 refs., 1 fig

  15. Investigation on the radiation induced conductivity of space-applied polyimide under cyclic electron irradiation

    International Nuclear Information System (INIS)

    Highlights: ► We investigated RIC evolution of polyimide under cyclic and a long-time continuous electron irradiation. ► The evolution RIC of the polyimide under cyclic irradiation presents an “overshoot” characteristic. ► It is found that the “overshoot” can be avoided by prolonging the single cyclic duration. ► Free radicals formed through ionization and trap filled by carriers contribute to the preliminary irradiation dose effects. - Abstract: Radiation induced conductivity (RIC) is an important property of dielectric materials to evaluate the charge/discharge effect in orbit-service spacecraft. RIC of space-applied polyimide film was in situ measured and studied under continuous and cyclic electron irradiation in this paper. The results indicate that, for cyclic electron irradiation, there is a similar increasing-mode of RIC to those for continuous irradiation with the electron irradiation time. However, under the cyclic electron irradiation, the RIC of polyimide shows an obvious irradiation-history characteristic, namely preliminary irradiation dose effect (PIDE). In this case, the steady RIC value presents an “overshoot” behavior in the first few irradiation cycles and then decrease to a stable one as that under continuous irradiation. Prolonging the initial irradiation duration may avoid occurrence of overshoot phenomenon. The behaviors of irradiation-induced free radicals in polyimide could be applied to explain the RIC evolution processes.

  16. Optimization programs of radiation protection applied to post-graduation and encouraging research

    International Nuclear Information System (INIS)

    In 2011 we started the automation and integration of radiological protection optimization programs, in order to offer unified programs and inter-related information in Portuguese, providing Brazilian radioactive facilities a complete repository for research, consultation and information. The authors of this project extended it to postgraduate education, in order to encourage postgraduate students researches, expanding methods for enhancing student learning through the use of different combined resources, such as educational technology, information technology and group dynamics. This new methodology was applied in a postgraduate discipline at Instituto de Pesquisas Energeticas e Nucleares (IPEN), Brazil, in the postgraduate discipline entitled Fundamental Elements of Radiological Protection (TNA-5732). Students have six weeks to assimilate a complex content of optimization, considering national and international standards, guidelines and recommendations published by different organizations over the past decades. Unlike traditional classes, in which students receive prompt responses, this new methodology stimulates discussion, encouraging collective thinking processes and promoting ongoing personal reflection and researches. Case-oriented problem-solving permitted students to play different roles, promoting whole-group discussions and cooperative learning, approaching theory and practical applications. Students discussed different papers, published in international conferences, and their implications according to current standards. The automation of optimization programs was essential as a research tool during the course. The results of this experience were evaluated in two consecutive years. We had excellent results compared to the previous 14 years. The methodology has exceeded expectations and will be also applied in 2013 to ionizing radiation monitoring postgraduate classes. (author)

  17. Information report on nuclear safety and radiation protection of MELOX - Issue 2014

    International Nuclear Information System (INIS)

    Published in compliance with the French code of the environment, this report first presents different aspects of the MELOX plant which produces MOX fuel: location and environment, history of basic nuclear installation or INB 151, presentation of the nuclear operator and of the industrial operator, assets of MOX fuel, MOX customers, regulatory framework of the MELOX plant, policy for sustainable development and continuous progress. It addresses the various measures regarding nuclear safety and radiation protection: general overview of nuclear safety in France, presentation of the Areva's nuclear safety Charter, measures adopted in MELOX, review for 2014 and perspectives for 2015. The next part addresses nuclear events: presentation of the INES scale and of the event declaration procedure, review of events declared in 2014 and regarding MELOX. The report gives an overview of activities and measures regarding protection and control of the environment: environmental management, consumption of natural resources, control of effluent releases, measurement of the impact on the environment, waste management, and perspectives for 2015. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

  18. Report by the ASN on the situation of nuclear safety and radiation protection in France in 2013

    International Nuclear Information System (INIS)

    In its first chapters, this huge report presents the various actions undertaken by the ASN. It proposes a detailed overview of the issue of ionizing radiations and risks for health and for the environment in the field of nuclear activities, presents and comments the principles and actors of the control of nuclear safety and of radiation protection, presents the different elements of the legal framework, describes and comments the control of nuclear activities and of exposures to ionizing radiations. The next chapters address the actions controlled by the ASN: radiological and post-accidental radiological situations, present measures related to public information and transparency, overview of international relationships, regional overview of nuclear safety and radiation protection, medical use of ionizing radiations, industrial, research and veterinary uses and the issue of source safety, the issue of radioactive material transportation. Issues of nuclear safety and radiation protection are then discussed for electronuclear plants, for installations dedicated to the nuclear fuel cycle, for various research and industrial nuclear installations, for the dismantling of base nuclear installations, and for radioactive wastes and polluted sites and soils

  19. WNA's policy document - Sustaining global best practices in uranium mining and processing, principles for managing radiation, health and safety, waste and the environment

    International Nuclear Information System (INIS)

    The worldwide community of uranium mining and processing recognizes that managing radiation, health and safety, waste and the environment is paramount. Such responsible management applies at all stages of planning and activities. Today we are acting to ensure that all parties directly involved in uranium mining and processing strive to achieve the highest levels of excellence in these fields. We are doing so by sustaining a strong safety culture based on a commitment to common, internationally shared principles. This paper sets out principles for the management of radiation, health and safety, waste and the environment applicable to sites throughout the world. In national and regional settings where nuclear fuel cycle activities are well developed, these principles already serve as the underpinning for 'Codes of Practice' that govern uranium mining and processing. In any given setting, a Code of Practice is needed to guide practical implementation of these principles according to the regional, national or site-specific context. We publish these principles in the belief that they hold special relevance for emerging uranium producing countries that do not yet have fully developed regulations for the control of radiation, health and safety, waste and the environment associated with uranium mining and processing. The principles are equally relevant for operators, contractors, and regulators newly engaged in uranium mining and processing. Once national regulations are fully developed, they can be expected to embody these principles. Each principle affirmed here will not apply to the same extent for each party. Ultimately, the precise allocation of responsibilities must be set at the national and local levels. This document holds the status of a policy and ethical declaration by the full WNA membership, which the global nuclear industry. The principles affirmed here are supported by key relevant international organizations, including the IAEA and the global mining

  20. WNA's Policy Document : sustaining global best practices in uranium, mining and processing, principles for managing radiation, health and safety, waste and the environment

    International Nuclear Information System (INIS)

    The worldwide community of uranium mining and processing recognizes that managing radiation, health and safety, waste and the environment is paramount. Such responsible management applies at all stages of planning and activities. Today we are acting to ensure that all parties directly involved in uranium mining and processing strive to achieve the highest levels of excellence in these fields. We are doing so by sustaining a strong safety culture based on a commitment to common, internationally shared principles. This paper sets out principles for the management of radiation, health and safety, waste and the environment applicable to sites throughout the world. In national and regional settings where nuclear fuel cycle activities are well developed, these principles already serve as the underpinning for 'Codes of Practice' that govern uranium mining and processing. In any given setting, a Code of Practice is needed to guide practical implementation of these principles according to the regional, national or site-specific context. These principles are published in the belief that they hold special relevance for emerging uranium producing countries that do not yet have fully developed regulations for the control of radiation, health and safety, waste and the environment associated with uranium mining and processing. The principles are equally relevant for operators, contractors, and regulators newly engaged in uranium mining and processing. Once national regulations are fully developed, they can be expected to embody these principles. Each principle affirmed here will not apply to the same extent for each party. Ultimately, the precise allocation of responsibilities must be set at the national and local levels. This document holds the status of a policy and ethical declaration by the full WNA membership, which the global nuclear industry. The principles affirmed here are supported by key relevant international organizations, including the IAEA and the global mining

  1. Advice of the French institute of radiation protection and nuclear safety about the 'Clay 2005' file

    International Nuclear Information System (INIS)

    The French institute of radiation protection and nuclear safety (IRSN) presents in this document its evaluation of the 'Clay 2005' file made by the ANDRA and which aims at demonstrating the feasibility of a disposal facility for high level and long living rad-wastes in the argillite formation of the Bure site. The critical points of the safety have been considered more thoroughly, together with the uncertainties concerning some important data and phenomena in relation with the confining properties of such a disposal facility. The basic geologic data gathered by the ANDRA about the Callovo-Oxfordian clay formation of the Bure site are sufficient to confirm the favorable intrinsic properties of this formation with respect to the confinement of wastes. The main possible disturbances of internal and external origin (thermal, hydrological, mechanical, chemical, climatic change, earthquakes, erosion..) would have no redhibitory impact on the overall confining capacity of the facility. The design safety principles retained for the exploitation of the facility and the post-closure safety aspects are globally satisfactory. Therefore, the IRSN considers the disposal of rad-wastes in the Callovo-Oxfordian argilite formation as feasible but in the case of a continuation of this project, several complementary informations would have to be supplied in particular concerning: the possible fracturing of the host and surrounding formations, the possibility of localized inhomogeneous fluid flows inside the surrounding formations, the improvement of our knowledge about the changes of the mechanical, physical and chemical properties of the site rocks and of concretes with time, the dimensioning of the metallic components of the facility (shafts, containers..), and the efficiency of the ventilation system with respect to the explosion risks inside B-type waste alveoles. (J.S.)

  2. Safety data from randomized controlled trials: applying models for recurrent events.

    Science.gov (United States)

    Hengelbrock, Johannes; Gillhaus, Johanna; Kloss, Sebastian; Leverkus, Friedhelm

    2016-07-01

    Simple descriptive listings and inference statistics based on 2×2 tables are still the most common way of summarizing and reporting adverse events data from randomized controlled trials, although these methods do not account for differences in observation times between treatment groups. Using standard methods from survival analysis such as the Cox model or Kaplan-Meier estimates would overcome this problem but limit the analysis to the first safety-related event of each subject. As an alternative, we discuss two models for recurrent events data-the Andersen-Gill and Prentice-Williams-Peterson model-regarding their applicability to safety data from randomized controlled trials. We argue that these models can be used to estimate two different quantities: a direct treatment effect on the risk of an event (Prentice-Williams-Peterson) and a total treatment effect as sum of the direct effect and the treatment's indirect effect via the event history (Anderson-Gill). Using simulated data, we illustrate the difference between these treatment effects and analyze the performance of both models in different scenarios. Because both models are limited to the analysis of cause-specific hazards if competing risks are present, we suggest to incorporate estimates of the mean frequency of events in the analysis to additionally allow the comparison of treatment effects on absolute event probabilities. We demonstrate the application of both models and the mean frequency function to safety endpoints with an illustrative analysis of data from a randomized phase-III study. Copyright © 2016 John Wiley & Sons, Ltd. PMID:27291933

  3. Building competence in radiation and nuclear safety through education and training - the approach of a national regulatory authority

    International Nuclear Information System (INIS)

    The Greek Atomic Energy Commission (EEAE) is the national competent authority for radiation and nuclear safety and security as well as for the radiation protection of ionizing and artificially produced non-ionizing radiation. The legal framework determines, inter alia, the responsibilities in education and training issues. The EEAE has a range of activities, in providing postgraduate and continuous education and training on radiation protection, and nuclear safety and security, at the national and international levels. At the national level, and particularly in the medical field, the EEAE is a participant in and a major contributor to the Inter-University Postgraduate Program on Medical Radiation Physics. Since 2003, the EEAE has been the Regional Training Center (RTC) for radiation, transport and waste safety of the International Atomic Energy Agency (IAEA) for the European Region in the English language. Moreover, the EEAE has also been recognized as the IAEA's Regional Training Center (RTC) in nuclear security in the English language since 2013. The EEAE recently proceeded to two significant initiatives: the design of a national program for education and training, and the certification of the Department of Education according to ISO 29990:2010. In this paper, the initiatives taken to enhance the radiation protection system in the country through education and training are presented. (authors)

  4. An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility

    Energy Technology Data Exchange (ETDEWEB)

    P. Calderoni; P. Sharpe; M. Shimada

    2009-09-01

    The Safety, Tritium and Applied Research facility at the Idaho National Laboratory is a US Department of Energy National User Facility engaged in various aspects of materials research for nuclear applications related to fusion and advanced fission systems. Research activities are mainly focused on the interaction of tritium with materials, in particular plasma facing components, liquid breeders, high temperature coolants, fuel cladding, cooling and blanket structures and heat exchangers. Other activities include validation and verification experiments in support of the Fusion Safety Program, such as beryllium dust reactivity and dust transport in vacuum vessels, and support of Advanced Test Reactor irradiation experiments. This paper presents an overview of the programs engaged in the activities, which include the US-Japan TITAN collaboration, the US ITER program, the Next Generation Power Plant program and the tritium production program, and a presentation of ongoing experiments as well as a summary of recent results with emphasis on fusion relevant materials.

  5. EDF - The Inspector General's report on Nuclear Safety and Radiation Protection

    International Nuclear Information System (INIS)

    This report is destined for the President of EDF with the purpose of informing him of the judgement the Inspector General has about the nuclear safety and radiation protection within the EDF Group. It is also intended for all who, in any way, play a role at EDF in improving nuclear safety. It may also prove useful to those outside the company who work in the nuclear field or indeed any branch of industry where there are risks to be managed and who wish to participate in the debate. It also contributes to the pool of information shared with the other nuclear operators under the auspices of WANO. The continuous improvement of nuclear safety results is a fundamental commitment of the EDF Group. This is notably reflected in a policy of transparency, whether in France, Britain, America or China. This document constitutes an example of this, offering an independent view of the operational situation. It is based on facts and findings derived in EDF's contacts with field staff and meetings with the decision makers, managers, medical personnel and players on both sides of this industry as well as outside stakeholders, especially contractor companies. The resulting snapshot of the situation in the field is particularly instructive. This report therefore concentrates more on problems and weaknesses rather than strengths and progress, except as concerns happenings outside France, where the focus is more on good practices than difficulties. Contents: 1 - The view from the Inspector General of EDF about the nuclear safety in the EDF group; 2 - A panorama of 2011: The management, The state of the installations, Maintenance of the French nuclear power plants, Relations with the French nuclear safety authority (ASN), The EPR projects, The players in the fields of health and safety, Radiation protection, Fire prevention and fire fighting, Increasing nuclear power plant security, Decommissioning; 3 - Nuclear safety management; 4 - The Fukushima Daiichi accident; 5 - Training to

  6. Applying decision trial and evaluation laboratory as a decision tool for effective safety management system in aviation transport

    Directory of Open Access Journals (Sweden)

    Ifeanyichukwu Ebubechukwu Onyegiri

    2016-10-01

    Full Text Available In recent years, in the aviation industry, the weak engineering controls and lapses associated with safety management systems (SMSs are responsible for the seemingly unprecedented disasters. A previous study has confirmed the difficulties experienced by safety managers with SMSs and the need to direct research to this area of investigation for more insights and progress in the evaluation and maintenance of SMSs in the aviation industry. The purpose of this work is to examine the application of Decision Trial and Evaluation Laboratory (DEMATEL to the aviation industry in developing countries with illustration using the Nigerian aviation survey data for the validation of the method. The advantage of the procedure over other decision making methods is in its ability to apply feedback in its decision making. It also affords us the opportunity of breaking down the complex aviation SMS components and elements which are multi-variate in nature through the analysis of the contributions of the diverse system criteria from the perspective of cause and effects, which in turn yields easier and yet more effective aviation transportation accident pre-corrective actions. In this work, six revised components of an SMS were identified and DEMATEL was applied to obtain their direct and indirect impacts and influences on the overall SMS performance. Data collection was by the survey questionnaire, which served as the initial direct-relation matrix, coded in Matlab software for establishing the impact relation map (IRM. The IRM was then plotted in MS Excel spread-sheet software. From our results, safety structure and regulation has the highest impact level on an SMS with a corresponding positive relation level value. In conclusion, the results agree with those of previous researchers that used grey relational analysis. Thus, DEMATEL serves as a great tool and resource for the safety manager.

  7. Dismantlement of nuclear facilities decommissioned from the Russian navy: Enhancing regulatory supervision of nuclear and radiation safety

    Energy Technology Data Exchange (ETDEWEB)

    Sneve, M.K.

    2013-03-01

    The availability of up to date regulatory norms and standards for nuclear and radiation safety, relevant to the management of nuclear legacy situations, combined with effective and efficient regulatory procedures for licensing and monitoring compliance, are considered to be extremely important. Accordingly the NRPA has set up regulatory cooperation programs with corresponding authorities in the Russian Federation. Cooperation began with the civilian regulatory authorities and was more recently extended to include the military authority and this joint cooperation supposed to develop the regulatory documents to improve supervision over nuclear and radiation safety while managing the nuclear military legacy facilities in Northwest Russia and other regions of the country. (Author)

  8. Dismantlement of nuclear facilities decommissioned from the Russian navy: Enhancing regulatory supervision of nuclear and radiation safety

    International Nuclear Information System (INIS)

    The availability of up to date regulatory norms and standards for nuclear and radiation safety, relevant to the management of nuclear legacy situations, combined with effective and efficient regulatory procedures for licensing and monitoring compliance, are considered to be extremely important. Accordingly the NRPA has set up regulatory cooperation programs with corresponding authorities in the Russian Federation. Cooperation began with the civilian regulatory authorities and was more recently extended to include the military authority and this joint cooperation supposed to develop the regulatory documents to improve supervision over nuclear and radiation safety while managing the nuclear military legacy facilities in Northwest Russia and other regions of the country. (Author)

  9. Safety

    CERN Multimedia

    2003-01-01

    Please note that the safety codes A9, A10 AND A11 (ex annexes of SAPOCO/42) entitled respectively "Safety responsibilities in the divisions" "The safety policy committee (SAPOCO) and safety officers' committees" and "Administrative procedure following a serious accident or incident" are available on the web at the following URLs: Code A9: http://edms.cern.ch/document/337016/LAST_RELEASED Code A10: http://edms.cern.ch/document/337019/LAST_RELEASED Code A11: http://edms.cern.ch/document/337026/LAST_RELEASED Paper copies can also be obtained from the TIS divisional secretariat, e-mail: tis.secretariat@cern.ch. TIS Secretariat

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

    Science.gov (United States)

    Emery, Robert J; Felknor, S A

    2002-05-01

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

  11. New infrared radiation temperature measurement system applied to the Laser Flash Method

    International Nuclear Information System (INIS)

    The laser flash method is based on measuring the temperature transient. The effect of the thermal inertia of the temperature measurement system is not negligible and cannot be ignored due to the fast dynamics of the measured thermal transient. This paper presents the new infrared radiation temperature measurement system applied to the thermal diffusivity measurements based on the laser flash method. The developed system consists in a detector cooled in liquid nitrogen, collimating lenses and a mathematical modeling developed in LabView. As a result, the generated electrical signal is converted into temperature. A detailed description of this new temperature measurement system is presented, as well as its mathematical model, computational implementation and calibration. For validate the new system, reference samples of homogeneous materials (Pyroceram 9606 and Inconel 600) were tested and the results of thermal diffusivities were compared with its reference certificates. The thermal diffusivity values measured by using the new system are in agreement with reference values, with less than 2 % of relative deviation

  12. An Efficient Computation of Coherent Synchrotron Radiation in a Rectangular Chamber, Applied to Resistive Wall Heating

    CERN Document Server

    Warnock, Robert L

    2016-01-01

    We study coherent synchrotron radiation (CSR) in a perfectly conducting vacuum chamber of rectangular cross section, in a formalism allowing an arbitrary sequence of bends and straight sections. We apply the paraxial method in the frequency domain, with a Fourier development in the vertical coordinate but with no other mode expansions. A line charge source is handled numerically by a new method that rids the equations of singularities through a change of dependent variable. The resulting algorithm is fast compared to earlier methods, works for short bunches with complicated structure, and yields all six field components at any space-time point. As an example we compute the tangential magnetic field at the walls. From that one can make a perturbative treatment of the Poynting flux to estimate the energy deposited in resistive walls. The calculation was motivated by a design issue for LCLS-II, the question of how much wall heating from CSR occurs in the last bend of a bunch compressor and the following straight...

  13. Quantities and Units used in Radiation Safety. Address at the third national course of Radiation Safety in Radiology. May 22-24, 2000 Guatemala

    International Nuclear Information System (INIS)

    The address discusses the following issues: the radiological units, radiation dose units, radiation protection units and operational quantities used for individual monitoring recently introduced by the International Commission of Radiological Units

  14. Information report on nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2012

    International Nuclear Information System (INIS)

    Published in compliance with the French code of the environment, this report first presents different aspects of the Areva's Tricastin site which comprises five basic nuclear installations or INBs, and seven ICPE (installation classified for the protection of the environment). The activities are dedicated to uranium conversion, uranium enrichment, uranium chemistry, industrial services, and fuel manufacturing. The report presents this important industrial site, describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which occurred on this site and had to be declared, reports the management of releases by this site and the control of the environment. The next part addresses the management of the various wastes produced by the different installations present on this site. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information

  15. Improving precision and safety in the use of beam modifying devices in radiation therapy

    International Nuclear Information System (INIS)

    Reliable and safe implementation of beam modifying devices such as wedges and block trays requires careful design and construction. Inappropriate design may pose problems ranging from user-hostile operation to hard-to-track, but significant variations in actual position in a beam. This may cause variation in actual wedge output factors, or variation in the position of a block tray. In case of simple mechanical failure or personnel mistake, design related mechanical conditions may result in injury to either a patient or a staff member. This paper is based on experience with linear accelerators from one manufacturer, but similar conditions are likely to exist with other radiation machines. A simple technical modification is offered which improves both accuracy and reproducibility in the placement of wedge-type filters. For our machines the solution also provides improved safety in the use of both wedge trays and block trays

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

    Science.gov (United States)

    Sarychev, Genrih; Gavrilkina, Galina

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

  17. Radiation technology in finishing process improves health, safety and environment (HSE) in the furniture manufacturing industry

    International Nuclear Information System (INIS)

    In furniture manufacturing, processes like cross cutting, molding, planning, shaping, turning, assembling and finishing are involved. The most significant types of negative impact of these processes are such as dust emission, noise, hazardous work, health risk, emission of organic solvent, toxic chemicals emission and chemical waste. In the finishing process, a number of negative effects that will cause health, safety and environmental (HSE) performance. This article highlights the environmental problems in the furniture finishing processes and how the radiation technology can reduce these negative impacts. The drawbacks that hamper the manufacturers from adopting this technology are also discussed. The objective of the paper is to create the awareness among the industrialist and consumers on the HSE hazardous in furniture finishing and steps can be taken to improve

  18. Information report on nuclear safety and radiation protection of La Hague AREVA site. Issue 2014

    International Nuclear Information System (INIS)

    Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basic nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2014, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

  19. Information report on nuclear safety and radiation protection of La Hague AREVA site. Issue 2013

    International Nuclear Information System (INIS)

    Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basic nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2013, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

  20. Design and implementation of a radiotherapy programme: Clinical, medical physics, radiation protection and safety aspects

    International Nuclear Information System (INIS)

    It is widely acknowledged that the clinical aspects (diagnosis, decision, indication for treatment, follow-up) as well as the procedures related to the physical and technical aspects of patient treatment must be subjected to careful control and planning in order to ensure safe, high quality radiotherapy. Whilst it has long been recognized that the physical aspects of quality assurance in radiotherapy are vital to achieve and effective and safe treatment, it has been increasingly acknowledged only recently that a systematic approach is absolutely necessary to all steps within clinical and technical aspects of a radiotherapy programme as well. The need to establish general guidelines at the IAEA, taking into account clinical medical physics, radiation protection and safety considerations, for designing and implementing radiotherapy programmes in Member States has been identified through the Member States' increased interest in the efficient and safe application of radiation in health care. Several consultants and advisory group meetings were convened to prepare a report providing a basis for establishing a programme in radiotherapy. The present TECDOC is addressed to all professionals and administrators involved in the development, implementation and management of a radiotherapy programme in order to establish a common and consistent framework where all steps and procedures in radiotherapy are taken into account