WorldWideScience

Sample records for radiological safety concerns

  1. Radiation safety concerns during interventional radiology

    International Nuclear Information System (INIS)

    Victor Raj, D.; Livingstone, Roshan Samuel

    2001-01-01

    Interventional radiological procedures are on the increase by virtue of the fact that these procedures replace highly invasive surgical and other procedures. Radiation dose to patients and hospital workers are of significance since these procedures tend to impart large dose to them. Moreover, long term risk from radiation absorbed by patients is of concern since the life expectancy of major fraction of patients is long after undergoing the procedure. This study intends to measure radiation dose imparted to patients as well as personnel- radiologists, technologists, nurses, etc. and estimate the risk factor involved

  2. Annual report 1996 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland. figs., tabs., refs.

  3. Annual Report 1998 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland.

  4. Annual Report 1998 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    International Nuclear Information System (INIS)

    1999-05-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland

  5. Annual Report 1999 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    International Nuclear Information System (INIS)

    2000-08-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland

  6. Annual Report 1999 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-08-15

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland.

  7. Annual report 1996 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    International Nuclear Information System (INIS)

    1997-05-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland. figs., tabs., refs

  8. Safety aspects in radiology

    International Nuclear Information System (INIS)

    Silva, D.C. da.

    1991-05-01

    The development of a program for the evaluation of the physical installations and operational procedures in diagnostic radiology with respect to radiation-safety is described. In addition, a proposal for the quality analysis of X-ray equipment and film-processing is presented. The purpose is both to ensure quality and safety of the radiology service, as well as to aid in the initial and in-service training of the staff. Interviews with patients, staff practicing radiology at a wide range of levels and the controlling authorities were carried out in the State of Rio de Janeiro in order to investigate the existence and the effective use of personal radioprotection equipment as well as user's and staff's concern for radiation safety. Additionally physical measurements were carried out in University Hospitals in Rio de Janeiro to assess the quality of equipment in day-to-day use. It was found that in the locations which did not have routine maintenance the equipment was generally in a poor state which lead to a high incidence of repetition of examinations and the consequent financial loss. (author)

  9. Radiological safety by design

    International Nuclear Information System (INIS)

    Gundaker, W.E.

    1977-01-01

    Under the Radiation Control for Health and Safety Act enacted by the U.S. Congress in 1968, the Food and Drug Administration's Bureau of Radiological Health may prescribe performance standards for products that emit radiation. A description is given of the development of these standards and outlines the administrative procedures by which they are enforced. (author)

  10. Radiological safety and control

    International Nuclear Information System (INIS)

    Kim, Jang Hee; Kim, Ki Sub

    1995-01-01

    The practical objective of radiological safety control is intended for achievement and maintenance of appropreately safe condition in environmental control for activities involving exposure from the use of radiation. In order to establish these objectives, we should be to prevent deterministic effects and to limit the occurrence stochastic effects to level deemed to be acceptable by the application of general principles of radiation protection and systems of dose limitation based on ICRP recommendations. 34 tabs., 19 figs., 11 refs. (Author) .new

  11. Radiological safety and control

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Sea Young; Yoo, Y S; Lee, J C; Lee, T Y; Lee, J L; Kim, B W; Lee, B J; Chung, K K; Chung, R I; Kim, J S; Lee, H S; Han, Y D; Lee, J I; Lee, K C; Yoon, J H; Sul, C W; Kim, C K; Yoon, K S; Seo, K W; Yoon, Y C [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-01-01

    This report describes the annual results of radiological safety and control program of 1995. This program consists of working area monitoring including HANARO, personnel radiation monitoring, education for radiation protection. As a result, the objectives of radiation protection have been achieved satisfactorily through the activities mentioned above. Also, the calibration services were provided to insure accurate radiation measurement in the radiation working places. 21 figs., 39 tabs., 5 refs. (Author) .new.

  12. Food Safety Concerns

    Institute of Scientific and Technical Information of China (English)

    HUYONG

    2004-01-01

    In China, there is an old saying:food is the first necessity of humans. The main concern of the Chinese used to be the security of the food supply rather than the safety of the food itself. However,after a long time fighting food shortages,China became self-sufficient in food in 1995. At this time, the country began for the first time to regulate food safety. Yet China has still not established a legal systern efficient in ensuring this safety. Many problems are rooted in the administration regime and China's priority of economic development.

  13. Guideline concerning specialist knowledge of radiological protection

    International Nuclear Information System (INIS)

    1991-09-01

    The regulation is to be applied to licenses according to paragraphs 3, 15, 16, 20, 20a of the Radiation Protection Law, paragraphs 6, 7, 9 of the Atomic Law, to notices according to paragraphs 4, 17 of the Radiation Protection Law as well as in the prospecting, mining and processing of radioactive minerals. It regulates the extent and evidence of the special knowledge required for radiation protection of radiological safety officers and personnel responsible for radiation protection. (UK)

  14. Safety concerns us all

    CERN Multimedia

    SC/GS/S

    2004-01-01

    In spite of periodic safety inspections, risks can never be entirely excluded. The Safety Commission invites you to inform your supervisor or Territorial Safety Officer (TSO) of any hazardous situations you may be aware of. Actions to be taken following the fall of two windowpanes A few weeks ago, a windowpane fell from the third floor of an office building, causing minor damage to a car parked outside. No one was hurt in the incident. The putty holding the window in place had gradually deteriorated over time, and strong winds undoubtedly triggered the incident. A few weeks later, a sudden draft caused a window on the fifth floor of the same building to shatter and fall to the ground below. No one was hurt and there was no material damage. The incident was caused by a fan set into the opening window: as the window slammed shut, the weight of the fan caused the glass to break. What can we do to improve safety? examine the windows of our offices and workshops and report any problems or faults, such as dam...

  15. Radiological safety and risk assessment

    International Nuclear Information System (INIS)

    Hunter, P.H.; Barg, D.C.; Baird, R.D.; Card, D.H.; de Souza, F.; Elder, J.; Felthauser, K.; Jensen, C.; Winkler, V.

    1982-02-01

    A brief radiological safety and risk assessment of a nuclear power generation center with an adjacent on-site waste disposal facility at a specific site in the State of Utah is presented. The assessment was conducted to assist in determining the feasibility and practicality of developing a nuclear energy center (NEC) in Utah consisting of nine 1250 MWe nuclear pressurized water reactor (PWR) electrical generating units arranged in 3 clusters of 3 units each known as triads. The site selected for this conceptual study is in the Horse Bench area about 15 miles directly south of the town of Green River, Utah. The radiological issues included direct radiation exposures to on-site workers and the off-site population, release of radioactive material, and effects of these releases for both normal operations and accidental occurrences. The basic finding of this study is that the concept of an NEC in the Green River area, specifically at the Horse Bench site, is radiologically feasible

  16. School Safety Concerns All Students.

    Science.gov (United States)

    Henderson, Megan

    1999-01-01

    Suggests that school safety is an issue that concerns all students. Discusses how the staff of the Rockwood South (Missouri) "RAMpage" covered the shootings at Columbine High School in a 14-page issue and in follow-up issues. Suggests that the student newspaper covered the controversial topic in an appropriate, tasteful manner. (RS)

  17. Implementation of a Radiological Safety Coach program

    Energy Technology Data Exchange (ETDEWEB)

    Konzen, K.K. [Safe Sites of Colorado, Golden, CO (United States). Rocky Flats Environmental Technology Site; Langsted, J.M. [M.H. Chew and Associates, Golden, CO (United States)

    1998-02-01

    The Safe Sites of Colorado Radiological Safety program has implemented a Safety Coach position, responsible for mentoring workers and line management by providing effective on-the-job radiological skills training and explanation of the rational for radiological safety requirements. This position is significantly different from a traditional classroom instructor or a facility health physicist, and provides workers with a level of radiological safety guidance not routinely provided by typical training programs. Implementation of this position presents a challenge in providing effective instruction, requiring rapport with the radiological worker not typically developed in the routine radiological training environment. The value of this unique training is discussed in perspective with cost-savings through better radiological control. Measures of success were developed to quantify program performance and providing a realistic picture of the benefits of providing one-on-one or small group training. This paper provides a description of the unique features of the program, measures of success for the program, a formula for implementing this program at other facilities, and a strong argument for the success (or failure) of the program in a time of increased radiological safety emphasis and reduced radiological safety budgets.

  18. Implementation of a Radiological Safety Coach program

    International Nuclear Information System (INIS)

    Konzen, K.K.

    1998-01-01

    The Safe Sites of Colorado Radiological Safety program has implemented a Safety Coach position, responsible for mentoring workers and line management by providing effective on-the-job radiological skills training and explanation of the rational for radiological safety requirements. This position is significantly different from a traditional classroom instructor or a facility health physicist, and provides workers with a level of radiological safety guidance not routinely provided by typical training programs. Implementation of this position presents a challenge in providing effective instruction, requiring rapport with the radiological worker not typically developed in the routine radiological training environment. The value of this unique training is discussed in perspective with cost-savings through better radiological control. Measures of success were developed to quantify program performance and providing a realistic picture of the benefits of providing one-on-one or small group training. This paper provides a description of the unique features of the program, measures of success for the program, a formula for implementing this program at other facilities, and a strong argument for the success (or failure) of the program in a time of increased radiological safety emphasis and reduced radiological safety budgets

  19. Investigation of the radiological safety concerns and medical history of the late Joseph T. Harding, former employee of the Paducah Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    Vallario, E.J.; Wolfe, H.R.

    1981-03-01

    An ex-employee's claims that inadequate enforcement of radiation safety regulations allowed excess radiation exposure thereby causing his deteriorating health was not substantiated by a thorough investigation

  20. Investigation of the radiological safety concerns and medical history of the late Joseph T. Harding, former employee of the Paducah Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    Vallario, E.J.; Wolfe, H.R.

    1981-01-01

    An ex-employee's claims that inadequate enforcement of radiation safety regulations allowed excess radiation exposure thereby causing his deteriorating health was not substantiated by a thorough investigation

  1. Investigation of the radiological safety concerns and medical history of the late Joseph T. Harding, former employee of the Paducah Gaseous Diffusion Plant

    CERN Document Server

    Vallario, E J

    1981-01-01

    An ex-employee's claims that inadequate enforcement of radiation safety regulations allowed excess radiation exposure thereby causing his deteriorating health was not substantiated by a thorough investigation.

  2. Investigation of the radiological safety concerns and medical history of the late Joseph T. Harding, former employee of the Paducah Gaseous Diffusion Plant

    Energy Technology Data Exchange (ETDEWEB)

    Vallario, E.J.; Wolfe, H.R.

    1981-03-01

    An ex-employee's claims that inadequate enforcement of radiation safety regulations allowed excess radiation exposure thereby causing his deteriorating health was not substantiated by a thorough investigation.

  3. A Checklist to Improve Patient Safety in Interventional Radiology

    International Nuclear Information System (INIS)

    Koetser, Inge C. J.; Vries, Eefje N. de; Delden, Otto M. van; Smorenburg, Susanne M.; Boermeester, Marja A.; Lienden, Krijn P. van

    2013-01-01

    To develop a specific RADiological Patient Safety System (RADPASS) checklist for interventional radiology and to assess the effect of this checklist on health care processes of radiological interventions. On the basis of available literature and expert opinion, a prototype checklist was developed. The checklist was adapted on the basis of observation of daily practice in a tertiary referral centre and evaluation by users. To assess the effect of RADPASS, in a series of radiological interventions, all deviations from optimal care were registered before and after implementation of the checklist. In addition, the checklist and its use were evaluated by interviewing all users. The RADPASS checklist has two parts: A (Planning and Preparation) and B (Procedure). The latter part comprises checks just before starting a procedure (B1) and checks concerning the postprocedural care immediately after completion of the procedure (B2). Two cohorts of, respectively, 94 and 101 radiological interventions were observed; the mean percentage of deviations of the optimal process per intervention decreased from 24 % before implementation to 5 % after implementation (p < 0.001). Postponements and cancellations of interventions decreased from 10 % before implementation to 0 % after implementation. Most users agreed that the checklist was user-friendly and increased patient safety awareness and efficiency. The first validated patient safety checklist for interventional radiology was developed. The use of the RADPASS checklist reduced deviations from the optimal process by three quarters and was associated with less procedure postponements.

  4. Standards of diagnostic radiological safety

    International Nuclear Information System (INIS)

    Yacovenco, A.; Ferreira, R.

    1996-01-01

    Brazil as well as many other countries are characterized for the access differentiated from the society to the products of the development. The lacking in specifications tolerance and mainly requirements of security and they of protection have induced to the inadequate utilization of the procedures technical and products in the area of radiology. We in this context are proposing a new mode of relationships between the diverse levels of intervention and responsibility

  5. Radiological Safety Officer (RSO): role and responsibilities

    International Nuclear Information System (INIS)

    Joshi, M.L.; Yadav, J.S.; Gopalakrishnan, R.K.; Ansari, I.A.

    2017-01-01

    The fundamental safety objective in a radiological facility (RF) is to protect people and the environment from harmful effects of ionising radiation. The radiation risks to people and the environment that may arise from the use of radiation and radioactive material must be assessed and must be controlled by means of the application of the relevant standards of safety. Thus, all facilities handling radioactive material must have experts, who are responsible for assisting the plant management in radiation protection programme

  6. Nordic projects concerning nuclear safety

    International Nuclear Information System (INIS)

    Soerensen, H.C.

    1988-11-01

    The report describes the nature of the work done in the first half of 1988 within the field of nuclear safety (1985-89) under the Nordic program for 1985-89. Five programmes and their documentation, are described and complete lists of addresses and of persons involved is given. (AB)

  7. Radiological protection and safety in medicine

    International Nuclear Information System (INIS)

    Anon.

    1998-01-01

    Here is presented a book published by ICRP ( International Commission Radiological Protection) that exposes the base principles of radiation protection, especially in medical sector. The exposure to ionizing radiations in medicine concerns the persons that profit by a diagnosis or a treatment but also the medical personnel, the patients family and the public. This publication 'CIPR 73' is more particularly adapted to the physicists and physicians implied in radiotherapy, medical imaging, in nuclear medicine and dentistry. It is also useful for the hospital establishments managers and to concerned national authorities. (N.C.)

  8. Radiological protection and nuclear safety postgraduate course

    International Nuclear Information System (INIS)

    Segado, R.C.; Menossi, C.A.

    1998-01-01

    Full text: The first Radiation Protection and Nuclear Safety Postgraduate Course was held in 1977, when the former Radioprotection and Nuclear Safety Branch of the National Atomic Energy Commission decided implement that course for the qualification of its professionals. After then, in 1980, by agreement between the CNEA, the National University of Buenos Aires and the Ministry of Health and Social Welfare got its present academic qualification as a Post-Graduate Course. Since then, it was sponsored by the IAEA. This Organization annually grants fellowships to fifteen students from different countries. Up to now, twenty consecutive courses have been delivered and more than five hundredth graduated, more than half of them coming from abroad. The aim of the course is the qualification and training in Radiological Protection and Nuclear Safety of those professionals involved in the design, construction, operation and decommissioning of Nuclear and Radioactive Installation and their related regulatory issues. (author) [es

  9. Safety studies concerning nuclear power reactors

    International Nuclear Information System (INIS)

    Bailly, Jean; Pelce, Jacques

    1980-01-01

    The safety of nuclear installations poses different technical problems, whether concerning pressurized water reactors or fast reactors. But investigating methods are closely related and concern, on the one hand, the behavior of shields placed between fuel and outside and, on the other, analysis of accidents. The article is therefore in two parts based on the same plan. Concerning light water reactors, the programme of studies undertaken in France accounts for the research carried out in countries where collaboration agreements exist. Concerning fast reactors, France has the initiative of their studies owing to her technical advance, which explains the great importance of the programmes under way [fr

  10. Circles of quality in radiological safety

    International Nuclear Information System (INIS)

    Gonzalez F, J.A.

    1991-01-01

    The concept of Circles of quality arose in Japan like an option to capitalize the enormous potential that the workers had developed as a result of its training in the statistical tools of quality. There are presented a series of steps that could be given with the purpose of implementing a program of ALARA circles. The radiological safety is in it finishes instance responsibility of each hard-working one and there won't be a protection program that can work among apathetic people, it is in this sense where the ALARA circles can provide its maximum contribution creating a conscience of responsibility and participation

  11. Aviation safety : FAA and DOD response to similar safety concerns

    Science.gov (United States)

    2002-01-01

    Report to the Honorable Norman Y. Mineta, Secretary of Transportation, and the Honorable Donald H. Rumsfeld, Secretary of Defense. : Safety of aircraft is a paramount concern in both civilian and military aviation. The Federal Aviation Administration...

  12. Problems with radiation protection concerning volunteers accompanying radiological patients

    International Nuclear Information System (INIS)

    Adrian Daoud

    2008-01-01

    Full text: The purpose of this work is to point out, within the framework of the Radiation Protection guidelines, the irregular situation of the 'volunteer' or 'accompanying person' who accompanies anyone requiring medical treatment with ionising radiation, as well as to suggest a possible justification for such role. It should be noted that most of these persons are subject to ionising radiation without knowing anything about the effects that it could cause on them, so that their condition could be hardly considered as 'voluntary'. There are several circumstances under which the presence of accompanying persons is required, being different among them. Several examples could be mentioned such as: those who are accompanying a direct relative (family bonds), those who are acting in service during their normal work (social workers, policemen) and even those who are forced by unusual under an accidental situation. The qualitative classification that radiological protection established in society concerning radiation risks for people in general enables to set mechanisms of justification, optimisation and dose limitation for each category, being perfectly identified which of them each person belongs to. But the figure of 'accompanying person' has been excluded from such characterisation. They are subject to radiation exposure without knowing it, or without having any information concerning the potential risks. For them, no balance between the net benefit of an adequate medical treatment versus potential health detriment may be applied as for the case of a patient. Thus, their exposure could be not justified. It is not the purpose of this work to question radiological medicine or its practices, but to clarify certain aspects involving members of the public in general, patients and members of the radiological community, as well as to propose lines of action concerning this subject. We conclude that it is not the volunteer who should decide about medical actions, a role

  13. Design aspects of radiological safety in nuclear facilities

    International Nuclear Information System (INIS)

    Patkulkar, D.S.; Purohit, R.G.; Tripathi, R.M.

    2014-01-01

    In order to keep operational performance of a nuclear facility high and to keep occupational and public exposure ALARA, radiological safety provisions must be reviewed at the time of facility design. Deficiency in design culminates in deteriorated system performance and non adherence to safety standards and could sometimes result in radiological incident. Important radiological aspects relevant to safety were compiled based on operating experiences, design deficiencies brought out from past nuclear incidents, experience gained during maintenance, participation in design review of upcoming nuclear facilities and radiological emergency preparedness

  14. IRSN research programs concerning reactor safety

    International Nuclear Information System (INIS)

    Bardelay, J.

    2005-01-01

    This paper is made up of 3 parts. The first part briefly presents the missions of IRSN (French research institute on nuclear safety), the second part reviews the research works currently led by IRSN in the following fields : -) the assessment of safety computer codes, -) thermohydraulics, -) reactor ageing, -) reactivity accidents, -) loss of coolant, -) reactor pool dewatering, -) core meltdown, -) vapor explosion, and -) fission product release. In the third part, IRSN is shown to give a major importance to experimental programs led on research or test reactors for collecting valid data because of the complexity of the physical processes that are involved. IRSN plans to develop a research program concerning the safety of high or very high temperature reactors. (A.C.)

  15. Safety and regulatory aspects of radiological laboratories

    International Nuclear Information System (INIS)

    Kumar, N.; Saxena, M.K.; Kannan, S.; Pujari, P.K.; Tomar, B.S.

    2017-01-01

    The erstwhile Radiochemistry Division (RCD) at Radiological Laboratories (RLG) was mainly concerned with the basic research and development work related to actinide chemistry and studies involving nuclear fission. The various activities of the different divisions are development of Non Destructive Assay (NDA) methods for the determination of actinides, characterization of advanced Pu based fuels using latest spectroscopic methods, development of sol-gel route for fabrication of different type of fuels, studies on high temperature thermodynamics of actinide compounds, development of methods for recovery and recycling of fuel scrap, mass spectrometric analysis of nuclear fuels and structural characterization of various uranium and plutonium compounds using X-ray diffraction and fluorescence techniques, trace elements analysis, need-based developmental work, inventory information and control of nuclear materials

  16. International Cooperation of the Republic of Croatia in the Field of Radiological and Nuclear Safety

    International Nuclear Information System (INIS)

    Novosel, N.

    2011-01-01

    International cooperation of the Republic of Croatia in the field of radiological and nuclear safety can be divided in two parts - political part, for which the Ministry of Foreign Affairs and European Integration is responsible, and technical part, for which the State Office for Radiological and Nuclear Safety is responsible. According to the Radiological and Nuclear Safety Act (OG 28/10) the State Office for Radiological and Nuclear Safety: ''coordinates technical cooperation with the International Atomic Energy Agency for all participants from the Republic of Croatia''; ''fulfils the obligations which the Republic of Croatia has assumed through international conventions and bilateral agreements concerning protection against ionising radiation, nuclear safety and the application of protective measures aimed at the non-proliferation of nuclear weapons'' and ''cooperates with international and domestic organisations and associations in the area of protection against ionising radiation and nuclear safety, and appoints its own expert representatives to take part in the work of such organisations and associations or to monitor their work''. In this paper various aspects of the technical cooperation with the International Atomic Energy Agency, as well as international conventions and bilateral agreements in the field of radiological and nuclear safety, are presented. Also, cooperation with other international organizations and associations in the area of radiological and nuclear safety, such as Nuclear Suppliers Group, the Zangger Committee, the Wassenaar Arrangement, Comprehensive Nuclear-Test-Ban Treaty Organization, Euratom and certain civil expert groups of NATO, is described. (author)

  17. Survey of radiological safety in dental practice

    Energy Technology Data Exchange (ETDEWEB)

    Gill, J R [UKAEA Health and Safety Branch, London; Hudson, A P

    1977-01-01

    A pilot survey of radiological protection in dental practice in Great Britain has been requested by the Health and Safety Executive and is now in progress. The survey should provide more precise data on the use of X-ray equipment. There are approximately 13,000 dentists in Great Britain using X-ray apparatus, and some 600 of these have been selected, on a statistical basis, to be invited to make use of a postal survey over a six month period. The postal survey technique to be used has already been developed as a service following requests from individual dentists. The dentist receives a questionnaire and three initial films to test the timer, then two special cassettes incorporating film and filters. Film badges are worn over a 12 week period by the dentist and by any staff who assist in radiography. Follow-up visits to discuss the survey will be made to one in ten of the selected dentists. The results will give the individual dentists, without cost, assurance of the efficient functioning of their equipment, and advice, should any remedial measures be necessary. Concurrently, the resulting statistics will give an indication of how many, if any, practices fall short of the recommendations of the Code of Practice for the Protection of Persons against Ionizing Radiations arising from Medical and Dental Use. Further action in respect of the Health and Safety at Work Act will be determined in the light of the survey.

  18. Aviation Safety Concerns for the Future

    Science.gov (United States)

    Smith, Brian E.; Roelen, Alfred L. C.; den Hertog, Rudi

    2016-01-01

    The Future Aviation Safety Team (FAST) is a multidisciplinary international group of aviation professionals that was established to identify possible future aviation safety hazards. The principle was adopted that future hazards are undesirable consequences of changes, and a primary activity of FAST became identification and prioritization of possible future changes affecting aviation. Since 2004, FAST has been maintaining a catalogue of "Areas of Change" (AoC) that could potentially influence aviation safety. The horizon for such changes is between 5 to 20 years. In this context, changes must be understood as broadly as possible. An AoC is a description of the change, not an identification of the hazards that result from the change. An ex-post analysis of the AoCs identified in 2004 demonstrates that changes catalogued many years previous were directly implicated in the majority of fatal aviation accidents over the past ten years. This paper presents an overview of the current content of the AoC catalogue and a subsequent discussion of aviation safety concerns related to these possible changes. Interactions among these future changes may weaken critical functions that must be maintained to ensure safe operations. Safety assessments that do not appreciate or reflect the consequences of significant interaction complexity will not be fully informative and can lead to inappropriate trade-offs and increases in other risks. The FAST strongly encourages a system-wide approach to safety risk assessment across the global aviation system, not just within the domain for which future technologies or operational concepts are being considered. The FAST advocates the use of the "Areas of Change" concept, considering that several possible future phenomena may interact with a technology or operational concept under study producing unanticipated hazards.

  19. Improving patient safety in radiology: a work in progress

    International Nuclear Information System (INIS)

    Sze, Raymond W.

    2008-01-01

    The purpose of this paper is to share the experiences, including successes and failures, as well as the ongoing process of developing and implementing a safety program in a large pediatric radiology department. Building a multidisciplinary pediatric radiology safety team requires successful recruitment of team members, selection of a team leader, and proper and ongoing training and tools, and protected time. Challenges, including thorough examples, are presented on improving pediatric radiology safety intradepartmentally, interdepartmentally, and institutionally. Finally, some major challenges to improving safety in pediatric radiology, and healthcare in general, are presented along with strategies to overcome these challenges. Our safety program is a work in progress; this article is a personal account and the reader is asked for tolerance of its occasional subjective tone and contents. (orig.)

  20. Safety concerns in composite manufacturing and machining

    Science.gov (United States)

    Asmatulu, Eylem; Alonayni, Abdullah; Alamir, Mohammed

    2018-03-01

    Because of the superior properties, composites have been used in many industrial applications, including aerospace, wind turbines, ships, cars, fishing rods, storage tanks, swimming pool panels, and baseball bats. Each application may require different combinations of reinforcements and matrices, which make the manufacturing safety even more challenging while working on these substances. In this study, safety issues in composite manufacturing and machining were investigated in detail, and latest developments were provided for workers. The materials most frequently used in composite manufacturing, such as matrix (polyester, vinylester, phenolic, epoxies, methyl ethyl ketone peroxide, benzoil peroxide, hardeners, and solvents), and reinforcement materials (carbon, glass and Kevlar fibers, honeycomb and foams) can be highly toxic to human body. These materials can also be very toxic to the environment when dumped out uncontrollably, creating major future health and environmental concerns. Throughout the manufacturing process, workers inhale vapors of the liquid matrix, hardeners and solvents / thinners, as well as reinforcement materials (chopped fibers and particles) in airborne. Milling, cutting and machining of the composites can further increase the toxic inhalations of airborne composite particles, resulting in major rashes, irritation, skin disorders, coughing, severe eye and lung injury and other serious illnesses. The major portions of these hazardous materials can be controlled using appropriate personal protective equipment for the chemicals and materials used in composite manufacturing and machining. This study provides best possible safety practices utilized in composite manufacturing facilities for workers, engineers and other participants.

  1. Radiological safety research for nuclear excavation projects - Interoceanic canal studies

    International Nuclear Information System (INIS)

    Klement, A.W. Jr.

    1969-01-01

    The general radiological problems encountered in nuclear cratering and nuclear excavation projects are discussed. Procedures for assessing radiological problems in such projects are outlined. Included in the discussions are source term, meteorology, fallout prediction and ecological factors. Continuing research requirements as well as pre- and post-excavation studies are important considerations. The procedures followed in the current interoceanic canal feasibility studies provide examples of radiological safety problems, current solutions and needed research. (author)

  2. Radiological safety research for nuclear excavation projects - Interoceanic canal studies

    Energy Technology Data Exchange (ETDEWEB)

    Klement, Jr, A W [U.S. Atomic Energy Commission, Las Vegas, NV (United States)

    1969-07-01

    The general radiological problems encountered in nuclear cratering and nuclear excavation projects are discussed. Procedures for assessing radiological problems in such projects are outlined. Included in the discussions are source term, meteorology, fallout prediction and ecological factors. Continuing research requirements as well as pre- and post-excavation studies are important considerations. The procedures followed in the current interoceanic canal feasibility studies provide examples of radiological safety problems, current solutions and needed research. (author)

  3. Patient Safety in Interventional Radiology: A CIRSE IR Checklist

    NARCIS (Netherlands)

    Lee, M. J.; Fanelli, F.; Haage, P.; Hausegger, K.; van Lienden, K. P.

    2012-01-01

    Interventional radiology (IR) is an invasive speciality with the potential for complications as with other invasive specialities. The World Health Organization (WHO) produced a surgical safety checklist to decrease the morbidity and mortality associated with surgery. The Cardiovascular and

  4. Accelerator driven systems from the radiological safety point of view

    Indian Academy of Sciences (India)

    application of the probabilistic safety analysis technique by assessing the probability and ... Technological and theoretical developments necessary for more precise .... Monte Carlo-based) to enable quick estimation of radiological hazards.

  5. Radiological safety aspects of handling plutonium

    International Nuclear Information System (INIS)

    Sundararajan, A.R.

    2016-01-01

    Department of Atomic Energy in its scheme of harnessing the nuclear energy for electrical power generation and strategic applications has given a huge role to utilization of plutonium. In the power production programme, fast reactors with plutonium as fuel are expected to play a major role. This would require establishing fuel reprocessing plants to handle both thermal and fast reactor fuels. So in the nuclear fuel cycle facilities variety of chemical, metallurgical, mechanical operations have to be carried out involving significant inventories of "2"3"9 Pu and associated radionuclides. Plutonium is the most radiotoxic radionuclide and therefore any facility handling it has to be designed and operated with utmost care. Two problems of major concern in the protection of persons working in plutonium handling facilities are the internal exposure to the operating personnel from uptake of plutonium and transplutonic nuclides as they are highly radiotoxic and the radiation exposure of hands and eye lens during fuel fabrication operations especially while handling recycled high burn up plutonium. In view of the fact that annual limit for intake is very small for "2"3"9Pu and its radiation emission characteristics are such that it is a huge challenge for the health physicists to detect Pu in air and in workers. This paper discusses the principles and practices followed in providing radiological surveillance to workers in plutonium handling areas. The challenges in protecting the workers from receiving exposures to hands and eye lens in handling high burn up plutonium are also discussed. The sites having Pu fuel cycle facilities should have trained medical staff to handle cases involving excessive intake of plutonium. (author)

  6. Radiological safety training for uranium facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-02-01

    This handbook contains recommended training materials consistent with DOE standardized core radiological training material. These materials consist of a program management guide, instructor`s guide, student guide, and overhead transparencies.

  7. Poor collimation in digital radiology: A growing concern

    African Journals Online (AJOL)

    Arun Kumar Agnihotri

    Recommendations for radiation protection origin from the fact that the x-rays can produce genetic and somatic mutations9, especially in pediatric radiology due to their high radiation sensitivity and susceptibility to radiation-induced cancers such as childhood leukemia5,10. Digital radiography was introduced in the 1980s11 ...

  8. Barriers to Safety Event Reporting in an Academic Radiology Department: Authority Gradients and Other Human Factors.

    Science.gov (United States)

    Siewert, Bettina; Swedeen, Suzanne; Brook, Olga R; Eisenberg, Ronald L; Hochman, Mary

    2018-05-15

    Purpose To investigate barriers to reporting safety concerns in an academic radiology department and to evaluate the role of human factors, including authority gradients, as potential barriers to safety concern reporting. Materials and Methods In this institutional review board-approved, HIPAA-compliant retrospective study, an online questionnaire link was emailed four times to all radiology department staff members (n = 648) at a tertiary care institution. Survey questions included frequency of speaking up about safety concerns, perceived barriers to speaking up, and the annual number of safety concerns that respondents were unsuccessful in reporting. Respondents' sex, role in the department, and length of employment were recorded. Statistical analysis was performed with the Fisher exact test. Results The survey was completed by 363 of the 648 employees (56%). Of those 363 employees, 182 (50%) reported always speaking up about safety concerns, 134 (37%) reported speaking up most of the time, 36 (10%) reported speaking up sometimes, seven (2%) reported rarely speaking up, and four (1%) reported never speaking up. Thus, 50% of employees spoke up about safety concerns less than 100% of the time. The most frequently reported barriers to speaking up included high reporting threshold (69%), reluctance to challenge someone in authority (67%), fear of disrespect (53%), and lack of listening (52%). Conclusion Of employees in a large academic radiology department, 50% do not attain 100% reporting of safety events. The most common human barriers to speaking up are high reporting threshold, reluctance to challenge authority, fear of disrespect, and lack of listening, which suggests that existing authority gradients interfere with full reporting of safety concerns. © RSNA, 2018.

  9. Effective radiological safety program for electron linear accelerators

    International Nuclear Information System (INIS)

    Swanson, W.P.

    1980-10-01

    An outline is presented of some of the main elements of an electron accelerator radiological safety program. The discussion includes types of accelerator facilities, types of radiations to be anticipated, activity induced in components, air and water, and production of toxic gases. Concepts of radiation shielding design are briefly discussed and organizational aspects are considered as an integral part of the overall safety program

  10. Radiological protection. Responsibility of the Safety Engineering Company

    International Nuclear Information System (INIS)

    Netto, A.L.

    1987-01-01

    This subject takes care of the Safety Engineering at the Radiologic Protection area on the X and Gama Rays Services. It mainly emphasis the case of that companies that, due do not have proper X and Gama Rays Services utilize partime task force on this area, but answer themselves for the safety of their employees in case of any accident occurence. (author) [pt

  11. Preliminary report of radiological safety to hydrology 1993 campaign

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  12. Radiology

    International Nuclear Information System (INIS)

    Sykora, A.

    2006-01-01

    In this text-book basic knowledge about radiology, biomedical diagnostic methods (radiography, computer tomography), nuclear medicine and safety and radiation protection of personnel on the radiodiagnostic place of work are presented

  13. Radiological safety evaluation report for NUWAX-79 exercise

    International Nuclear Information System (INIS)

    King, W.C.

    1979-03-01

    An analysis of the radiological safety of the NUWAX-79 exercise to be conducted on the Nevada Test Site in April 1979 is given. An evaluation of the radiological safety to the participants is made using depleted uranium (D-38) in mock weapons parts, and 223 Ra and its daughters as a radioactive contaminant of equipment and terrain. The radiological impact to offsite persons is also discussed, particularly for people living at Lathrop Wells, Nevada, which is located 7 miles south of the site proposed for the exercise. It is the conclusion of this evaluation that the potential radiological risk of this exercise is very low, and that no individual should receive exposure to radioactivity greater than one-tenth of the level permitted under current federal radiation exposure guidelines

  14. Effectively managing public concerns about immunization safety

    Directory of Open Access Journals (Sweden)

    2002-01-01

    Full Text Available Los beneficios de la vacunación frente a las enfermedades prevenibles de este modo son muy superiores a sus mínimos riesgos. Con el fin de mantener o fortalecer los programas nacionales de vacunación, los trabajadores de todos los niveles de la salud pública deberían recibir formación sobre los temas relacionados con la vacunación y estar preparados para responder a las dudas planteadas por el público. Una respuesta rápida y franca a los temores del público acerca de las vacunas podría garantizar la integridad de los programas de vacunación en todo el continente americano, según el documento "Directrices para enfrentarse a los temores sobre la seguridad de las vacunaciones" (Guidelines for Managing Immunization Safety Concerns, elaborado por la División de Vacunas e Inmunización de la Organización Panamericana de la Salud (OPS y resumido aquí. Todo acontecimiento médico que se considere posiblemente relacionado con una vacuna debe ser investigado en el ámbito local. Si su distribución temporal y los síntomas respaldan la sospecha de que pueda estar relacionado con una vacuna, se debe iniciar una investigación más formal y, una vez finalizada, el acontecimiento debe ser clasificado en una de las cuatro categorías siguientes: 1 relacionado con el programa, 2 relacionado con la vacuna, 3 no relacionado, o 4 desconocido (investigación no concluyente. Dependiendo de la categoría a la que haya sido asignado el acontecimiento, las acciones posteriores pueden consistir en tranquilizar a los padres, a los cuidadores y a otros adultos; comunicarse con el público y con otros trabajadores de la salud; instaurar tratamiento; corregir los errores del programa, como pueden ser la manipulación de la vacuna, su almacenamiento, su administration o los problemas relacionados con la jeringuilla; comentar con los fabricantes problemas relacionados con la calidad y eficacia de la vacuna; retirar la vacuna del mercado, o iniciar nuevas

  15. Safety of Conscious Sedation In Interventional Radiology

    International Nuclear Information System (INIS)

    Arepally, Aravind; Oechsle, Denise; Kirkwood, Sharon; Savader, Scott J.

    2001-01-01

    Purpose: To identify rates of adverse events associated with the use of conscious sedation in interventional radiology.Methods: In a 5-month period, prospective data were collected on patients undergoing conscious sedation for interventional radiology procedures (n = 594). Adverse events were categorized as respiratory, sedative, or major adverse events. Respiratory adverse events were those that required oral airway placement, ambu bag, or jaw thrust. Sedation adverse events were unresponsiveness, oxygen saturation less than 90%, use of flumazenil/naloxone, or agitation. Major adverse events were hypotension, intubation, CPR, or cardiac arrest. The frequency of adverse events for the five most common radiology procedures were determined.Results: The five most common procedures (total n = 541) were biliary tube placement/exchange (n = 182), tunneled catheter placement (n 135), diagnostic arteriography (n = 125), vascular interventions (n = 52), and other catheter insertions (n = 46). Rates for respiratory, sedation, and major adverse events were 4.7%, 4.2%, and 2.0%, respectively. The most frequent major adverse event was hypotension (2.0%). Biliary procedures had the highest rate of total adverse events (p < .05) and respiratory adverse events (p < .05).Conclusion: The frequency of adverse events is low with the use of conscious sedation during interventional procedures. The highest rates occurred during biliary interventions

  16. HTGR safety research concerns at NRC

    International Nuclear Information System (INIS)

    Minogue, R.B.

    1982-01-01

    A general discussion of HTGR technical and safety-related problems is given. The broad areas of current research programs specific to the Fort St. Vrain reactor and applicable to HTGR technology are summarized

  17. Rassyn: National radiological safety data management system

    International Nuclear Information System (INIS)

    Domenech Nieves, Haydee; Valdez Ramso, Maryzury; Jova Sed, Luis; De la Fuente, Andres

    1996-01-01

    The paper describes the menu, screens data files, programs and classifications of the systems, for keeping a record of their institutions, inspection and authorization, the personal register of incidents and accidents, and the national inventory of radiation protection sources and equipment. By making use of it, a comparison can be made of existing data of a practice with its requirements and a questionnaire of the inspection, (Checking list), the development and results of the inspection can be reported on, the program and notification of the inspection can be prepared and the information on the radiological situation- whether at a national or at a territorial level- can be evaluated

  18. Radiological safety aspects of industrial radiography

    International Nuclear Information System (INIS)

    Hanekom, A.P.

    1983-01-01

    Industrial radiography and especially gamma-radiography, has established itself as a very powerful tool in non-destructive testing. Unfortunately there is an amount of risk attached to the use of industrial radiography. The primary causes of radiography accidents include: working conditions, equipment failure and lack of supervisory control. To alleviate the radiological risks involved with gamma-radiography, the Atomic Energy Corporation (AEC) has imposed various conditions for the possession, use, and conveyance of radioactive material. This includes personnel training and equipment specifications

  19. Nuclear and radiological safety, 1980-1993

    International Nuclear Information System (INIS)

    1994-06-01

    This document lists all sales publications of the International Atomic Energy Agency dealing with Nuclear Safety, issued during the period 1980-1993. It gives an abstract of these publications along with contents and prices in Austrian Schillings

  20. Concerns in assessing radiological releases to a major estuary

    International Nuclear Information System (INIS)

    Foldesi, Leslie P.

    1989-01-01

    Full text: In the State of Virginia, the James River flows into the Chesapeake Bay and from the mouth of the James River to the fall line the river is under the influence of tidal forces. There are several centers of commerce along the river including an international port of call at the mouth of the James. Associated with the centers of commerce are potential sources of radioactive materials for being released to the river. Two hundred miles inland, the Babcock and Wilcox nuclear fuels processing plants are situated along-side the James River, which has been known to flood its banks quickly in the mountainous regions of Virginia. Storage tanks have been swept downstream from this facility in a previous flood. Fortunately, the tanks were not destroyed. Another source of a possible release is the Suny Nuclear Power Station located on the James River about fifty miles from the Chesapeake Bay. In the cities of Norfolk and Newport News, shipyards are fueling and defueling the Navy's nuclear powered fleet. In addition, many of the Navy's ships are carrying nuclear weapons. These activities may also result in an inadvertent release. In assessing the radiological release from any one of the previously mentioned activities, it is obvious that dilution of the material released into the river is a major factor in dose assessment, as well as the fact that the water is brackish and not suitable as a source of potable water. However, dilution in this case may not be the simple solution. We also have to remember that this estuary is under tidal effects, which means that the materials may not be going out to sea to be further diluted as quickly as we would like to think. It may be possible that the material will be carried up river as far as the fall line and deposited, or deposited along the river's banks. From Virginia's experience with the pesticide, Kepone, materials may be deposited along the estuary and enter the food chain thereby necessitating the limitation of taking

  1. Concerns in assessing radiological releases to a major estuary

    Energy Technology Data Exchange (ETDEWEB)

    Foldesi, Leslie P [Virginia Department of Health, Bureau of Radiological Health, Richmond, VA (United States)

    1989-09-01

    Full text: In the State of Virginia, the James River flows into the Chesapeake Bay and from the mouth of the James River to the fall line the river is under the influence of tidal forces. There are several centers of commerce along the river including an international port of call at the mouth of the James. Associated with the centers of commerce are potential sources of radioactive materials for being released to the river. Two hundred miles inland, the Babcock and Wilcox nuclear fuels processing plants are situated along-side the James River, which has been known to flood its banks quickly in the mountainous regions of Virginia. Storage tanks have been swept downstream from this facility in a previous flood. Fortunately, the tanks were not destroyed. Another source of a possible release is the Suny Nuclear Power Station located on the James River about fifty miles from the Chesapeake Bay. In the cities of Norfolk and Newport News, shipyards are fueling and defueling the Navy's nuclear powered fleet. In addition, many of the Navy's ships are carrying nuclear weapons. These activities may also result in an inadvertent release. In assessing the radiological release from any one of the previously mentioned activities, it is obvious that dilution of the material released into the river is a major factor in dose assessment, as well as the fact that the water is brackish and not suitable as a source of potable water. However, dilution in this case may not be the simple solution. We also have to remember that this estuary is under tidal effects, which means that the materials may not be going out to sea to be further diluted as quickly as we would like to think. It may be possible that the material will be carried up river as far as the fall line and deposited, or deposited along the river's banks. From Virginia's experience with the pesticide, Kepone, materials may be deposited along the estuary and enter the food chain thereby necessitating the limitation of taking

  2. Nuclear and radiological safety in Slovenia in 1995

    International Nuclear Information System (INIS)

    Lovincic, D.

    1996-01-01

    The Slovenian Nuclear Safety Administration (SNSA) in cooperation with the Health Inspectorate of the Republic of Slovenia and the Administration for Rescue and Disaster Relief (URSZR) has prepared a Report on Nuclear and Radiological Safety in the Republic of Slovenia for 1995. The report is presenting: the activities of the SNSA; the operation of nuclear facilities; monitoring of radioactivity; control of ionizing radiation and nuclear electricity generation. (author)

  3. Nuclear and radiological safety in Slovenia in 1998, Annual report

    International Nuclear Information System (INIS)

    Lovincic, D.

    1999-09-01

    The Slovenian Nuclear Safety Administration (SNSA), in cooperation with Health Inspectorate of the Republic of Slovenia and the Administration for Civil Protection and Disaster Relief, has prepared a Report of Nuclear and Radiological Safety in the Republic of Slovenia for 1998. The report presents activities of the SNSA, operation of nuclear facilities, activities of the Agency of Radwaste Management, work of international missions, emergency plan, authorized organizations, monitoring of radioactivity, control of ionizing radiation and nuclear electricity generation

  4. Nuclear and Radiological Safety in Slovenia. Annual Report 1996

    International Nuclear Information System (INIS)

    Lovincic, D.

    1997-08-01

    The Slovenian Nuclear Safety Administration (SNSA), in cooperation with 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 Radiological Safety in the Republic of Slovenia for 1996. The report presents activities of the SNSA; operation of nuclear facilities; activities of the Agency for Radwaste Management; work of international missions; emergency plan; authorized organizations; monitoring of radioactivity; control of ionizing radiation and nuclear electricity generation

  5. Report on nuclear and radiological safety in 1995

    International Nuclear Information System (INIS)

    Lovincic, D.

    1996-07-01

    The Slovenian Nuclear Safety Administration (SNSA) in cooperation with the Health Inspectorate of the Republic of Slovenia and the Administration for Rescue and Disaster Relief (URSZR) has prepared a Report on Nuclear and Radiological Safety in the Republic of Slovenia for 1995. The report is presenting: the activities of the SNSA; the operation of nuclear facilities; monitoring of radioactivity; control of ionizing radiation and nuclear electricity generation.

  6. Implementation of the new regulation on radiological safety in Peru

    International Nuclear Information System (INIS)

    Medina Gironzini, E.

    1997-01-01

    Since its creation in 1975, the Peruvian Institute of Nuclear Energy (IPEN) has enacted three regulations of national importance on the norms of protection against ionizing radiation. The first regulation, which is called regulation of radiological protection (1980) approved by a resolution of IPEN, is the result of the work of a committee constituted by IPEN and the Ministry of Health. Its implementation caused some problems as result of which, in 1989, a new regulation on radiological protection was enacted through a supreme decree. Taking into account the new recommendation of the International Commission on Radiological Protection and the International Basic Safety Standard for Protection against Ionizing Radiation and for the Safety of Radiation Sources, approved in May 1997, the regulation of radiological safety also considers evolving aspects in the Project ARCAL XVII/IAEA. This regulation includes various topics such as exclusions, requirements of protection (medical exposure, occupational exposure, public exposure, chronic exposure), requirements of source safety, interventions and emergencies, control of sources and practices (exemptions, authorizations, inspections) etc. The implementation of this regulation at the national level falls to IPEN, the unique authority commissioned to control nuclear installations, radioactivity and x ray facilities in medicine, industry and research

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

    International Nuclear Information System (INIS)

    Gonzalez F, J.A.

    1991-01-01

    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

  8. College Rampage Renews School Safety Concerns

    Science.gov (United States)

    Maxwell, Lesli A.

    2007-01-01

    Coming just four days before the anniversary of the Columbine school shootings, the mass slayings by a student gunman at Virginia Polytechnic Institute last week revived vexing questions and raised familiar fears for educators across the country who grapple daily with ensuring the safety of their students and staffs. The April 16 killings provoked…

  9. Considerations about radiological safety in industrial gammagraphy

    International Nuclear Information System (INIS)

    Sajaroff, P.M.

    1988-01-01

    Gammagraphy is the most dangerous practice out of the commonly employed with radioactive materials or radiation sources in industry, medicine, research and training. The amount of accidents which took place in different countries and their radiological consequences oblige to take extreme precautions in order to reduce their happening to the maximum. The principal cause of the accidents is the human error, the most common of which are described. Safe operation depends on the quality of the equipment and the human factors, thus it is mandatory to accomplish a series of requirements, the most important of which are presented. The solution of the problem mainly requires the application of an adequate programme of quality warranty to the design, construction, testing and operation. Furthermore, the radiation sources must be identified by unnoticed persons. Finally a brief description of some accidents which took place in different countries are presented. (M.E.L.) [es

  10. Chinese consumers concerns about food safety: Case of Tianjin

    NARCIS (Netherlands)

    Zhang XiaoYong, Xiaoyong

    2005-01-01

    The objective of this study is to gain an insight to Chinese consumers' knowledge and concerns over food safety from a case study in Tianjin city. The results indicate that Chinese consumers are very much concerned about food safety, particularly with regard to vegetables and dairy products. Chinese

  11. Radiological Emergency Response Health and Safety Manual

    Energy Technology Data Exchange (ETDEWEB)

    D. R. Bowman

    2001-05-01

    This manual was created to provide health and safety (H&S) guidance for emergency response operations. The manual is organized in sections that define each aspect of H and S Management for emergency responses. The sections are as follows: Responsibilities; Health Physics; Industrial Hygiene; Safety; Environmental Compliance; Medical; and Record Maintenance. Each section gives guidance on the types of training expected for managers and responders, safety processes and procedures to be followed when performing work, and what is expected of managers and participants. Also included are generic forms that will be used to facilitate or document activities during an emergency response. These ensure consistency in creating useful real-time and archival records and help to prevent the loss or omission of information.

  12. New safety valve addresses environmental concerns

    International Nuclear Information System (INIS)

    Taylor, J.; Austin, R.

    1992-01-01

    This paper reports that Conoco Pipeline is using a unique relief valve to reduce costs while improving environmental protection at its facilities. Conoco Pipeline Co. Inc. began testing new relief valves in 1987 to present over-pressuring its pipelines while enhancing the safety, environmental integrity and profitability of its pipelines. Conoco worked jointly with Rupture Pin Technology Inc., Oklahoma City, to seek a solution to a series of safety, environmental, and operational risks in the transportation of crude oil and refined products through pipelines. Several of the identified problems were traced to a single equipment source: the reliability of rupture discs used at pipeline stations to relieve pressure by diverting flow to tanks during over-pressure conditions. Conoco's corporate safety and environmental policies requires solving problems that deal with exposure to hydrocarbon vapors, chemical spills or the atmospheric release of fugitive emissions, such as during rupture disc maintenance. The company had used rupture pin valves as vent relief devices in conjunction with development by Rick Austin of inert gas methods to protect the inner casing wall and outer carrier pipeline wall in pipeline road crossings. The design relies on rupture pin valves set at 5 psi to isolate vent openings from the atmosphere prior to purging the annular space between the pipeline and casing with inert gas to prevent corrosion. Speciality Pipeline Inspection and Engineering Inc., Houston, is licensed to distribute the equipment for the new cased-crossing procedure

  13. Radiological protection. Textbook for radiographers and reference book for radiological safety officers

    International Nuclear Information System (INIS)

    Stieve, F.E.; Stargardt, A.; Stender, H.S.

    1996-01-01

    The textbook is primarily intended for radiologic staff and radiologic safety officers and gives information on the current regulatory provisions of the German X-ray Ordinance, applications of X-rays, quality assurance, organisational aspects of film processing and quality requirements of X-rays. An annex lists the guidelines of the Bundesaerztekammer (German National Chamber of Physicians) relating to quality assurance aspects, and further useful information on commercially available film-screen systems, the various associations of physicians in Germany, and requirements and performance of radiation surveys. (vhe) [de

  14. Industrial radiography in the Philippines: safety concerns

    International Nuclear Information System (INIS)

    David, Jocelyn L.; Artificio, Thelma P.; Cerbolles, Justina S.; Caseria, Estrella S.; Agron, Inocencio A.

    2005-01-01

    Industrial radiography utilizes the highest activity (5.55 tera becquerel (TBq) to 7.4 TBq) among the various mobile application of radioisotopes. It is highly possible that radiographers exceed the annual dose limits for workers occupationally exposed to radiation (as prescribed in the Code of PNRI Regulations part 3) if they do not give cautious consideration to the factors that determine the radiation dose, namely: the gamma source dose rates, time distance and shielding. To enhance the safety culture among radiographers, various strategies are recommended to be undertaken by the Philippine Nuclear Research Institute as well as the licensed companies undertaking activities in industrial radiography. (Authors)

  15. Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety. Radiological protection in Latin America and the Caribbean. Vol. 1,2

    International Nuclear Information System (INIS)

    1996-08-01

    Two volumes contain more than 183 complete papers presented during the Third Regional Meeting on Radiological Protection and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin american specialist 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

  16. 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)

    1995-10-01

    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

  17. Nuclear and radiological safety in Slovenia in 1994

    Energy Technology Data Exchange (ETDEWEB)

    Lovincic, D [Slovenian Nuclear Safety Administration, Ljubljana (Slovenia)

    1995-07-01

    The Slovenian Nuclear Safety Administration (SNSA) in cooperation with the Health Inspectorate, prepared the Report on Nuclear and Radiological Safety in the Republic of Slovenia for 1994 as part of its regular practice of reporting on its activities to the Government and the Parliament of the Republic of Slovenia. The report is divided into seven thematic chapters covering the activities of the SNSA, the operation of nuclear facilities in Slovenia, the activities of the Agency for Radwaste Management (ARAO), the activities of international safety missions in Slovenia, environmental radioactivity monitoring in Slovenia, ionizing radiation sources control by Slovenian Health Inspectorate and review of the operation of nuclear facilities around the world. (author)

  18. Report on nuclear and radiological safety in 1994

    International Nuclear Information System (INIS)

    Lovincic, D.

    1995-01-01

    The Slovenian Nuclear Safety Administration (SNSA) in cooperation with the Health Inspectorate, prepared the Report on Nuclear and Radiological Safety in the Republic of Slovenia for 1994 as part of its regular practice of reporting on its activities to the Government and the Parliament of the Republic of Slovenia. The report is divided into seven thematic chapters covering the activities of the SNSA, the operation of nuclear facilities in Slovenia, the activities of the Agency for Radwaste Management (ARAO), the activities of international safety missions in Slovenia, environmental radioactivity monitoring in Slovenia, ionizing radiation sources control by Slovenian Health Inspectorate and review of the operation of nuclear facilities around the world.

  19. Nuclear and radiological safety in Slovenia in 1994

    International Nuclear Information System (INIS)

    Lovincic, D.

    1995-01-01

    The Slovenian Nuclear Safety Administration (SNSA) in cooperation with the Health Inspectorate, prepared the Report on Nuclear and Radiological Safety in the Republic of Slovenia for 1994 as part of its regular practice of reporting on its activities to the Government and the Parliament of the Republic of Slovenia. The report is divided into seven thematic chapters covering the activities of the SNSA, the operation of nuclear facilities in Slovenia, the activities of the Agency for Radwaste Management (ARAO), the activities of international safety missions in Slovenia, environmental radioactivity monitoring in Slovenia, ionizing radiation sources control by Slovenian Health Inspectorate and review of the operation of nuclear facilities around the world. (author)

  20. Protection and radiological safety in medicine

    International Nuclear Information System (INIS)

    Nenot, J.C.; Lochard, J.; Aubert, B.; Aurengo, A.; Cosset, J.M.; Kalifa, G.

    1996-01-01

    The present publication put the base principles of radiation protection by dwelling on these ones that take the lead of medicine. It is a reference text. The exposure to ionizing radiations in medicine, concerns essentially the persons that need a diagnosis or a treatment but also the medical personnel, the family of the patients and the public: the protection have to take into account all these situations. (N.C.)

  1. Losing nuclear expertise - A safety concern

    International Nuclear Information System (INIS)

    Ziakova, M.

    2002-01-01

    Full text: Since the mid of eighties several important changes in human beings behaviour, which influence nuclear field, can be observed - the loss of interest in studying technical disciplines (namely nuclear), strong pressure of environmental movements, stagnation of electricity consumption and deregulation of electric markets. All these factors create conditions which are leading to the decrease of job positions related to the nuclear field connected particularly with research, design and engineering. Loss of interest in studying nuclear disciplines together with the decrease of number of job positions has led to the declining of university enrolments, closing of university departments and research reactors. In this manner just a very small number of appropriately educated new experts are brought In the same moment the additional internal factor - the relative ageing of the human workforce on both sites operators of nuclear facilities and research and engineering organisations can be observed. All these factors, if not addressed properly, could lead to the loss of nuclear expertise and the loss of nuclear expertise represents the direct thread to the nuclear safety. The latest studies have shown that at present NPPs cannot be replaced by other kinds of electric sources and in no case by renewable ones in an efficient manner. Therefore it is necessary to carefully manage knowledge gathered in the nuclear field during the years and to keep on the nuclear safety research, education and training to ensure and upgrade safe and reliable operation of existing and future nuclear facilities. This is responsibility of both the governments of the states using nuclear applications and owners of nuclear facilities. (author)

  2. Probabilistic safety analysis and radiological protection

    International Nuclear Information System (INIS)

    Guimaraes, A.C.F.; Goes, A.G.A.

    1990-05-01

    The author presents a brief description of NUREG-1150 and NUREG-0956, both documents of great importance in the risk area. Based on document's recommendations and following NUREG-1150 similar methodology, a calculation model is proposed in this publication, with the purpose of analyzing the consequences of a severe accident in Angra-I Power Station. The suggested model can be divided in two stages: the first one called front-end considers the power station system safety during the accident, and the second called back-end cares for accident consequences. 9 refs. (B.C.A.)

  3. Do Online Bicycle Routing Portals Adequately Address Prevalent Safety Concerns?

    Directory of Open Access Journals (Sweden)

    Martin Loidl

    2018-03-01

    Full Text Available Safety concerns are among the most prevalent deterrents for bicycling. The provision of adequate bicycling infrastructure is considered as one of the most efficient means to increase cycling safety. However, limited public funding does not always allow agencies to implement cycling infrastructure improvements at the desirable level. Thus, bicycle trip planners can at least partly alleviate the lack of adequate infrastructure by recommending optimal routes in terms of safety. The presented study provides a systematic review of 35 bicycle routing applications and analyses to which degree they promote safe bicycling. The results show that most trip planners lack corresponding routing options and therefore do not sufficiently address safety concerns of bicyclists. Based on these findings, we developed recommendations on how to better address bicycling safety in routing portals. We suggest employing current communication technology and analysis to consider safety concerns more explicitly.

  4. Radiological safety in petroleum industry. Towards prevention culture

    International Nuclear Information System (INIS)

    Truppa, Walter A.

    2007-01-01

    Within the frame of regulatory control of industrial applications the audit of sealed and open radioactive sources in oil uses is one of the most relevant. The handling of radioactive sources, the requirement of procedures and training are just a few examples among all those that make up the radiological safety culture. A number of requirements divided into three main groups: operational safety at the storage area of radioactive sources, during transportation and during the applications (Cementation, well logging and use of radiotracers) are highlighted. Due to the great number of aspects that have to be taken in account as well as the interrelation of all control processes it is highly recommended that aspects of safety culture and quality should be considered and improvements regarding prevention, should be introduced so as to correct deviations that could arise in order to avoid radiological risk situations, emphasizing risk perception situations, attitude training, implementation of audit and level of safety in the facilities and control of duties, involving radiological material handling, described in the present work. (author) [es

  5. Aviation Safety: FAA and DOD Response to Similar Safety Concerns

    National Research Council Canada - National Science Library

    2002-01-01

    .... The Federal Aviation Administration (FAA) and the military services often face common safety issues as they oversee the operation of similar aircraft or even dissimilar aircraft that use common parts and materials...

  6. Human-centred radiological software techniques supporting improved nuclear safety

    International Nuclear Information System (INIS)

    Szoeke, Istvan; Johnsen, Terje

    2013-01-01

    The Institute for Energy Technology (IFE) is an international research foundation for energy and nuclear technology. IFE is also the host for the international OECD Halden Reactor Project. The Software Engineering Department in the Man Technology Organisation at IFE is a leading international centre of competence for the development and evaluation of human-centred technologies, process visualisation, and the lifecycle of high integrity software important to safety. This paper is an attempt to give a general overview of the current, and some of the foreseen, research and development of human-centred radiological software technologies at the Software Engineering department to meet with the need of improved radiological safety for not only nuclear industry but also other industries around the world. (author)

  7. UK legislation on radiological health and safety. Pt. 1

    Energy Technology Data Exchange (ETDEWEB)

    Evans, H D

    1983-02-01

    A brief survey is given of current UK legislation on radiological health and safety in areas in which ''Ionising Radiations Regulations 1982'' do not apply. Such areas in which separate Acts or Regulations for ionising radiations operate include: 1) Factories Act Regulations; 2) the disposal of radioactive wastes; 3) the transport of radioactive materials by air, sea, road, rail and post; 4) nuclear reactors and allied plants; 5) schools and further educational establishments and 6) research laboratories.

  8. Radiological safety assessment of a reference INTOR facility

    International Nuclear Information System (INIS)

    Khan, T.A.; Stasko, R.R.; Watts, R.T.; Shaw, G.; Morrison, C.A.; Russell, S.; Kempe, T.; Zimmerman, R.

    1985-03-01

    This report consists of a number of separate studies all of which were performed in support of INTOR Critical Issue D: Tritium Containment and Personnel Access vs Remote Maintenance. The common thread running through these studies is the radiological safety element in the design and operation of the INTOR facility. The intent is to help establish a firm basis for comparisons between a reactor cell maintenance option which requires personnel access, and one which involves completely remote maintenance

  9. Radiological safety and quality paradigms in leadership and innovation

    CERN Document Server

    Lau, Lawrence

    2013-01-01

    This book is the product of a unique collaboration by experts from leading international, regional and national agencies and professional organizations discussing on the current 'hot' issue on the judicious use and safety of radiation in radiology. There have been several cases involving radiation overexposure that have received international attention. Strategies and solutions to guide readers how to maximize the benefits and minimize the risks when using radiation in medicine are covered.

  10. CP-50 calibration facility radiological safety assessment document

    International Nuclear Information System (INIS)

    Chilton, M.W.; Hill, R.L.; Eubank, B.F.

    1980-03-01

    The CP-50 Calibration Facility Radiological Safety Assessment document, prepared at the request of the Nevada Operations Office of the US Department of Energy to satisfy provisions of ERDA Manual Chapter 0531, presents design features, systems controls, and procedures used in the operation of the calibration facility. Site and facility characteristics and routine and non-routine operations, including hypothetical incidents or accidents are discussed and design factors, source control systems, and radiation monitoring considerations are described

  11. Patient Safety in Interventional Radiology: A CIRSE IR Checklist.

    LENUS (Irish Health Repository)

    2012-02-01

    Interventional radiology (IR) is an invasive speciality with the potential for complications as with other invasive specialities. The World Health Organization (WHO) produced a surgical safety checklist to decrease the morbidity and mortality associated with surgery. The Cardiovascular and Interventional Society of Europe (CIRSE) set up a task force to produce a checklist for IR. Use of the checklist will, we hope, reduce the incidence of complications after IR procedures. It has been modified from the WHO surgical safety checklist and the RAD PASS from Holland.

  12. Nuclear and radiological safety in Slovenia in 1998

    International Nuclear Information System (INIS)

    Lovincic, D.

    1999-09-01

    This is an English version of the Annual Report of Nuclear and Radiological Safety in the Republic of Slovenia for 1998, which was prepared by The Slovenian Nuclear Safety Administration (SNSA), in cooperation with, Health Inspectorate of the Republic of Slovenia and the Administration for Civil Protection and Disaster Relief. The report presents activities of the SNSA, operation of nuclear facilities, activities of the Agency of Radwaste Management, work of international missions, emergency plan, authorized organizations, monitoring of radioactivity, control of ionizing radiation and nuclear electricity generation

  13. Radiological safety aspects of the operation of neutron generators

    International Nuclear Information System (INIS)

    Boggs, R.F.

    1976-01-01

    The purpose of the manual is to provide some basic guidelines to persons with a minimum of training in radiological health or health physics, on some safety aspects of the operation of sealed-tube and Cockcroft-Walton type neutron generators. The manual does not state rules or regulations but presents a description of the most likely hazards. It is relevant to those relatively compact neutron generators which usually operate at less than 150-200 kV for the purpose of producing 14-MeV neutrons. The scope is limited to basic discussions of hazards and measurement techniques. Separate chapters are devoted to the characteristics and use of neutron generators; radiation hazards and safety considerations; radiation monitoring and interpretation of measurements; and requirements for an effective safety programme. Two appendices deal with non-radiation hazards and safety considerations, and with a neutron generator laboratory, respectively. An extensive list of bibliographic references is included

  14. International antiterrorist conventions concerning the safety of air transport

    Directory of Open Access Journals (Sweden)

    Jacek BARCIK

    2008-01-01

    Full Text Available In this article the international law regulations are presented concerning the civilian safety of the air transport. The history concerning air terrorism and international antiterrorist conventions was described in detail, involving The Chicago Convention, The Tokyo Convention, The Hague Convention and Montreal Convention.

  15. The Radiological Safety Analysis Computer Program (RSAC-5) user's manual

    International Nuclear Information System (INIS)

    Wenzel, D.R.

    1994-02-01

    The Radiological Safety Analysis Computer Program (RSAC-5) calculates the consequences of the release of radionuclides to the atmosphere. Using a personal computer, a user can generate a fission product inventory from either reactor operating history or nuclear criticalities. RSAC-5 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated through the inhalation, immersion, ground surface, and ingestion pathways. RSAC+, a menu-driven companion program to RSAC-5, assists users in creating and running RSAC-5 input files. This user's manual contains the mathematical models and operating instructions for RSAC-5 and RSAC+. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-5 and RSAC+. These programs are designed for users who are familiar with radiological dose assessment methods

  16. Radiological protection principles concerning the safeguard, use or release of contaminated materials, buildings, areas or dumps from uranium mining. Recommendations of the Commission on Radiological Protection with explanations

    International Nuclear Information System (INIS)

    Mueller-Neumann, M.

    1992-01-01

    The volume presents the full texts of the SSK Recommendations addressing the aspects and problems involved, and which can be separately retrieved from the database: 1) Radiological protection principles concerning the release of scrap from the shut-down of uranium mining plants; 2) Radiological protection principles concerning the release for industrial use of areas contaminated from uranium mining; 3) Radiological protection principles concerning the use for forest and agricultural purposes and as public gardens (parks) and residential areas of areas contaminated from uranium mining; 4) Radiological protection principles concerning the safeguard and use of mine dumps; 5) Radiological protection principles concerning the release for further commercial or industrial use of buildings used for commercial or industrial purposes and the disposal of building debris from uranium mining and milling; 6) Radiological protection principles concerning the release for general use of reusable equipment and installations from uranium mining. The following appendices round up the material: 1) Radiation exposure from mining in Saxony and Thuringia and its evaluation (Summary of the results of consultations during the 1990 closed meeting); 2) Radiological protection principles for the limitation of the radiation exposure of the public to radon and its daughters; 3) Epidemiological studies on the health state of the inhabitants of the mining region and the miners in Saxony and Thuringia. (orig.) [de

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

    Science.gov (United States)

    Orders, Amy B; Wright, Donna

    2003-01-01

    other facilities may assign the duties and title of "radiation safety officer" to a radiologist or other management, per the requirements of regulatory agencies in that state. Radiation safety in a medical setting can be delineated into two main categories--equipment and personnel requirements--each having very specific guidelines. The literature fails to adequately address the blatant link between radiology department managers and radiation safety duties. The breadth and depth of this relationship is of utmost concern and warrants deeper insight as the demands of the regulatory agencies increase with the new advances in technology, procedures and treatments associated with radiation-producing devices and radioactive materials.

  18. Effect of changes in technical parameters in radiological safety

    International Nuclear Information System (INIS)

    Avendano, Ge; Fernandez, C

    2007-01-01

    This work analyzes the generation of secondary radiation that affects the professionals of health during interventional X ray procedures in first level hospitals. The research objectives were, on the one hand, to quantify the amount of radiation and to compare it with norms in force with respect to magnitudes, and on the other hand to evaluate the elements of protection used. The measurements will help to improve the radiological safety, to assess the eventuality of risks and, in the last term, to the possibility of norms modification for the improvement of the protection, especially that of the personnel who daily make a certain amount of interventional procedures guided by radiation, like angiographic cine applications, using continuous or pulsed fluoroscopy. The motivation of the study is in the suspicion that present interventionism is made with a false sensation of safety, based only in the use of lead apron and protection elements incorporated in the equipment by the manufacturer, nevertheless not always the health personnel are conscious that an excessive proximity with the tube and the patient body becomes a risky source of secondary and scattered radiation. The obtained results allow us to demonstrate the existence of conditions of risk, even possible iatrogenic events, in particular when the procedures imply the use of certain techniques of radiographic exploration, thus reaching the conclusion that the radiographic methodology must be changed in order to rationalize so much?. In order to achieve this we propose modifications to the present norms and legislation referred to the radiological safety in Chile

  19. Radiological safety of nuclear power plants in India

    International Nuclear Information System (INIS)

    Sathish, A.V.

    2015-01-01

    Safety in nuclear power plants (NPPs) is often less understood and more talked about, thus the author wanted to share the facts to clear the myths. Safety is accorded overriding priority in all the activities. All nuclear facilities are sited, designed, constructed, commissioned and operated in accordance with strict quality and safety standards. Principles of defence in depth, redundancy and diversity are followed in the design of all nuclear facilities and their systems/components. PPs in India are not only safe but are also well regulated, have proper radiological protection of workers and the public, regular surveillance, approved standard operating and maintenance procedures, a well-defined waste management methodology, periodically rehearsed emergency preparedness and disaster management plans. The regulatory framework in the country is robust, with the independent Atomic Energy Regulatory Board (AERB) having powers to frame the policies, laying down safety standards, monitoring and enforcing all the safety provisions. As a result, India's safety record has been excellent in over 400 reactor years of operation of power reactors

  20. Radiological and nuclear safety- evolution, standards and similarity

    International Nuclear Information System (INIS)

    Soman, S.D.

    1996-01-01

    With the realisation of potential for severe health affects after the discovery of x-rays and radioactivity, the radiation protection aspect became focus of interest for medical users from the beginning of this century. With the activities of International Commission on Radiological Protection (ICRP), the standards evolved during all these years based on epidemiological data and radio-biological research. The current standards are the ICRP recommendations of 1990. Based on these, internationally harmonised standards for protection against ionising radiation and safety of radioactive sources were brought out by IAEA in 1994. The nuclear safety (implies safety of nuclear power plants) came into prominence when large scale units were designed and operated since mid 1950s. The philosophy in nuclear safety has evolved in past 2-3 decades taking into account the lessons learned from accidents, mainly Three Mile Island (1979) and Chernobyl-4 (1986). These current nuclear safety standards are incorporated in INSAG reports, particularly INSAG-3. This paper brings out salient features of these evolutions, current standards and similarity of radiation and nuclear safety standards in their present form. (author). 7 refs., 10 tabs

  1. Safety considerations concerning light water reactors in Sweden

    International Nuclear Information System (INIS)

    Nilsson, T.

    1977-01-01

    In 1975 the Swedish Nuclear Power Inspectorate was commissioned by the Government to perform a Reactor Safety Study concerning commercial light water reactors. The study will contain an account of: - rules and regulations for reactor designs; - operation experience of the Swedish nuclear power plants with international comparisons; - the development of reactor designs during the last 10 years; - demands and conditions for inspection and inspection methods; - nuclear power plant operation organization; - training of operators; and - the results of research into nuclear safety. The study is scheduled for completion by July 1st, 1977, however, this paper gives a summary of the results of the Reactor Safety Study already available. The paper contains detailed statistics concerning safety related occurrences and reactor scrams in Sweden from July 1st, 1974 until the beginning of 1977

  2. Federal Radiological Monitoring and Assessment Center Health and Safety Manual

    Energy Technology Data Exchange (ETDEWEB)

    FRMAC Health and Safety Working Group

    2012-03-20

    This manual is a tool to provide information to all responders and emergency planners and is suggested as a starting point for all organizations that provide personnel/assets for radiological emergency response. It defines the safety requirements for the protection of all emergency responders. The intent is to comply with appropriate regulations or provide an equal level of protection when the situation makes it necessary to deviate. In the event a situation arises which is not addressed in the manual, an appropriate management-level expert will define alternate requirements based on the specifics of the emergency situation. This manual is not intended to pertain to the general public.

  3. Radiologic safety program for ionizing radiation facilities in Parana, Brazil

    International Nuclear Information System (INIS)

    Schmidt, M.F.S.; Tilly Junior, J.G.

    1997-01-01

    A radiologic safety program for inspection, licensing and control of the use of ionizing radiation in medical, industrial and research facilities in Parana, Brazil is presented. The program includes stages such as: 1- division into implementation phases considering the activity development for each area; 2-use of the existing structure to implement and to improve services. The development of the program will permit to evaluate the improvement reached and to correct operational strategic. As a result, a quality enhancement at the services performed, a reduction for radiation dose exposure and a faster response for emergency situations will be expected

  4. Overview of Generation IV (Gen IV) Reactor Designs - Safety and Radiological Protection Considerations

    International Nuclear Information System (INIS)

    Baudrand, Olivier; Blanc, Daniel; Ivanov, Evgeny; Bonneville, Herve; Clement, Bernard; Kissane, Martin; Meignen, Renaud; Monhardt, Daniel; Nicaise, Gregory; Bourgois, Thierry; Bruna, Giovanni; Hache, Georges; Repussard, Jacques

    2012-01-01

    The purpose of this document is to provide an updated overview of specific safety and radiological protection issues for all the reactor concepts adopted by the GIF (Generation IV International Forum), independent of their advantages or disadvantages in terms of resource optimization or long-lived-waste reduction. In particular, this new document attempts to bring out the advantages and disadvantages of each concept in terms of safety, taking into account the Western European Nuclear Regulators' Association (WENRA) statement concerning safety objectives for new nuclear power plants. Using an identical framework for each reactor concept (sodium-cooled fast reactors or SFR, high / very-high temperature helium-cooled reactors of V/HTR, gas-cooled fast reactors or GFR, lead-or lead / bismuth-cooled fast reactors or LFR, molten salt reactors or MSR, and supercritical-water-cooled reactors or SCWR), this summary report provides some general conclusions regarding their safety and radiological protection issues, inspired by WENRA's safety objectives and on the basis of available information. Initial lessons drawn from the events at the Fukushima-Daiichi nuclear power plant in March 2011 have also been taken into account in IRSN's analysis of each reactor concept

  5. Pre-Exposure Prophylaxis for HIV Prevention : Safety Concerns

    NARCIS (Netherlands)

    Tetteh, Raymond A; Yankey, Barbara A; Nartey, Edmund T; Lartey, Margaret; Leufkens, Hubert G M; Dodoo, Alexander N O

    Available evidence supports the efficacy of pre-exposure prophylaxis (PrEP) in decreasing the incidence of human immunodeficiency virus (HIV) infection among high-risk individuals, especially when used in combination with other behavioural preventive methods. Safety concerns about PrEP present

  6. Critical review of the reactor-safety study radiological health effects model. Final report

    International Nuclear Information System (INIS)

    Cooper, D.W.; Evans, J.S.; Jacob, N.; Kase, K.R.; Maletskos, C.J.; Robertson, J.B.; Smith, D.G.

    1983-03-01

    This review of the radiological health effects models originally presented in the Reactor Safety Study (RSS) and currently used by the US Nuclear Regulatory Commission (NRC) was undertaken to assist the NRC in determining whether or not to revise the models and to aid in the revision, if undertaken. The models as presented in the RSS and as implemented in the CRAC (Calculations of Reactor Accident Consequences) Code are described and critiqued. The major elements analyzed are those concerning dosimetry, early effects, and late effects. The published comments on the models are summarized, as are the important findings since the publication of the RSS

  7. Critical review of the reactor-safety study radiological health effects model. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, D.W.; Evans, J.S.; Jacob, N.; Kase, K.R.; Maletskos, C.J.; Robertson, J.B.; Smith, D.G.

    1983-03-01

    This review of the radiological health effects models originally presented in the Reactor Safety Study (RSS) and currently used by the US Nuclear Regulatory Commission (NRC) was undertaken to assist the NRC in determining whether or not to revise the models and to aid in the revision, if undertaken. The models as presented in the RSS and as implemented in the CRAC (Calculations of Reactor Accident Consequences) Code are described and critiqued. The major elements analyzed are those concerning dosimetry, early effects, and late effects. The published comments on the models are summarized, as are the important findings since the publication of the RSS.

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

    International Nuclear Information System (INIS)

    Vaz, Pedro

    2015-01-01

    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. - Highlights: • The hazards associated to the use of radioactive sources must be taken into account. • Security issues are of paramount importance in the use of radioactive sources. • Radiation sources can be used to perpetrate terrorist acts (RDDs, INDs, REDs). • DSRS and orphan sources trigger radiological protection, safety and security concerns. • Regulatory control, from cradle to grave, of radioactive sources is mandatory.

  9. Food safety concerns of fast food consumers in urban Ghana.

    Science.gov (United States)

    Omari, Rose; Frempong, Godfred

    2016-03-01

    In Ghana, out-of-home ready-to-eat foods including fast food generally have been associated with food safety problems. Notwithstanding, fast food production and consumption are increasing in Ghana and therefore this study sought to determine the food safety issues of importance to consumers and the extent to which they worry about them. First, through three focus group discussions on consumers' personal opinions about food safety issues, some emergent themes were obtained, which were used to construct an open-ended questionnaire administered face-to-face to 425 respondents systematically sampled from 20 fast food restaurants in Accra. Findings showed that most fast food consumers were concerned about food hazards such as pesticide residue in vegetables, excessive use of artificial flavour enhancers and colouring substances, bacterial contamination, migrated harmful substances from plastic packages, and general unhygienic conditions under which food is prepared and sold. Consumers also raised concerns about foodborne diseases such as cholera, typhoid, food poisoning, diarrhoea, bird flu and swine flu. The logistic regression model showed that being male increased the likelihood of worrying about general food safety issues and excessive use of flavour enhancers than in females while being youthful increased the likelihood of being worried about typhoid fever than in older consumers. These findings imply that consumers in urban Ghana are aware and concerned about current trends of food safety and foodborne disease challenges in the country. Therefore, efforts targeted at improving food safety and reducing incidences of foodborne diseases should not only focus on public awareness creation but should also design more comprehensive programmes to ensure the making of food safety rules and guidelines and enforcing compliance to facilitate availability and consumers' choice of safe foods. Copyright © 2015 Elsevier Ltd. All rights reserved.

  10. Current Approaches of Regulating Radiological Safety of Medical and Industrial Practices in Romania

    International Nuclear Information System (INIS)

    Goicea, C.

    2016-01-01

    The principal document regulating the radiological safety of ionizing radiation application in Romania is the “Fundamental Norms for Radiological Safety”. These norms establish the requirements concerning the assurance of radiological safety of occupational exposed workers, population and environment, in accordance with the provisions of Law 111/1996 on the safe deployment of nuclear activities, republished. Justification of practices for all new practices which lead to exposure to ionizing radiation shall be justified in writing by their initiator, underlining their economic, social or other nature advantages, in comparison with the detriment which they could cause to health. CNCAN authorise these practices, provided that they consider the justification as being thorough. The applicant, respectively the authorisation holder, has to demonstrate that all actions to ensure radiation protection optimization are undertaken, with a view to ensure that all exposures, including the potential ones, within the framework of practice developed are maintained at the lowest reasonable achievable level, taking into account the economic and social factors: ALARA principle.

  11. Report of radiological safety for a micro PET

    International Nuclear Information System (INIS)

    Gallegos M, R.; Ruiz T, C. G.; Martinez D, A.; Rodriguez V, M.

    2010-09-01

    Considering one of the guides emitted by the National Commission of Nuclear Security and Safeguards, was realized the report of radiological safety for a micro tomography by positrons emission that is part of Bimodal System of Images developed in their entirety for personnel of the Physics Institute of UNAM. With this system is sought to obtain tomography images of small animals using non destructive methods, such as computerized micro tomography and micro tomography by positrons emission. In this work each one of the report points is enumerated and only it is described, to big features on that consist, due to the great extension of each one of them. The report has two parts; the first is denominated -Of the installation and the Organization- and is given to know the interior and external characteristics of the installation, besides how and under which authority the activities will be executed inside the laboratory. The second part is called -of the Radiological Protection- and has for objective to describe the radiation sources that will be used, as well as the measures of radiological protection foreseen inside the laboratory. The most important part in the report consists on the description of the three radionuclides to use: 18 F, 11 C and 13 N, as well as the methods for the shielding calculation and for the estimate of the dose equivalent during the normal operation of the equipment. These methods were applied three times, because the calculation was made for each radionuclide. The results of these calculations show that: 1) it not is necessary to have a structural shielding, due to the activity sources very reduced, and 2) the dose limit per year (according to the ICRP-60) it will not be surpassed neither in the case of the occupationally exposed personnel, neither on the public in general. (Author

  12. Food colors: Existing and emerging food safety concerns.

    Science.gov (United States)

    Oplatowska-Stachowiak, Michalina; Elliott, Christopher T

    2017-02-11

    Food colors are added to different types of commodities to increase their visual attractiveness or to compensate for natural color variations. The use of these additives is strictly regulated in the European Union, the United States, and many other countries worldwide. There is a growing concern about the safety of some commonly used legal food colorants and there is a trend to replace the synthetic forms with natural products. Additionally, a number of dyes with known or suspected genotoxic or carcinogenic properties have been shown to be added illegally to foods. Robust monitoring programs based on reliable detection methods are required to assure the food is free from harmful colors. The aim of this review is to present an up to date status of the various concerns arising from use of color additives in food. The most important food safety concerns in the field of food colors are lack of uniform regulation concerning legal food colors worldwide, possible link of artificial colors to hyperactive behavior, replacement of synthetic colors with natural ones, and the presence of harmful illegal dyes-both known but also new, emerging ones in food. The legal status of food color additives in the EU, United States, and worldwide is summarized. The reported negative health effects of both legal and illegal colors are presented. The European Rapid Alert System for Food and Feed notifications and US import alerts concerning food colors are analyzed and trends in fraudulent use of color additives identified. The detection methods for synthetic colors are also reviewed.

  13. The influence of Goiania radiological accident on Brazilian public opinion concerning new nuclear electric plants

    International Nuclear Information System (INIS)

    Meldonian, Nelson Leon; Mattos, Luis Antonio Terribile de

    1997-01-01

    The Brazilian society is against applications of nuclear energy, mainly respecting to construction of new nuclear power plants, believing that they are harmful to population's welfare and the environment. By this reason, Brazilian nuclear sector would promote a more intensive program of public discussion, not limited to technical and scientific community. Intending to contribute to a better judgment by society about the differences between diverse employment of nuclear energy, arguments concerned to its benefits are presented, pointing out that adverse accounts to nuclear electricity based on Goiania radiological accident, are not justified

  14. Operation QUICKSILVER. Onsite radiological safety report, October 1978-September 1979

    International Nuclear Information System (INIS)

    Mullen, O.W.; Eubank, B.F.

    1980-02-01

    QUICKSILVER was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1978 to September 30, 1979. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeroes before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific optional procedures are defined

  15. Operation Praetorian onsite radiological safety report, October 1981-September 1982

    International Nuclear Information System (INIS)

    Mullen, O.W.; Eubank, B.F.

    1983-09-01

    PRAETORIAN was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1981 through September 30, 1982. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeros before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

  16. Safety requirements and radiological protection for ore installations

    International Nuclear Information System (INIS)

    2003-06-01

    This norm establishes the safety and radiological protection requirements for mining installations which manipulates, process and storing ores, raw materials, steriles, slags and wastes containing radionuclides of the uranium and thorium natural series, simultaneously or separated, and which can cause undue exposures to the public and workers, at anytime of the functioning or pos operational stage. This norm applies to the mining installations activities, suspended or which have ceased their activities before the issue date of this norm, destined to the mining, physical, chemical and metallurgical processing, and the industrialization of raw materials and residues containing associated radionuclides from the natural series of uranium and thorium, including the stages of implantation, operation and decommissioning of the installation

  17. Operation CRESSET: onsite radiological safety report, October 1977--September 1978

    International Nuclear Information System (INIS)

    Mullen, O.W.; Eubank, B.F.

    1979-06-01

    CRESSET was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1977 to September 30, 1978. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeroes before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

  18. Operation FULCRUM: onsite radiological safety report, October 1976--September 1977

    International Nuclear Information System (INIS)

    Mullen, O.W.; Eubank, B.F.

    1978-03-01

    FULCRUM was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1976 to September 30, 1977. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeroes before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

  19. Operation GUARDIAN onsite radiological safety report, October 1980-September 1981

    International Nuclear Information System (INIS)

    Mullen, O.W.; Eubank, B.F.

    1983-02-01

    GUARDIAN was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1980 to September 30, 1981. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection intruments surveyed reentry routes into ground zeroes before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

  20. Importance of the lower limit of detection in radiological safety

    International Nuclear Information System (INIS)

    Rafael Terol T.; Hermenegildo Maldonado M.

    1991-01-01

    The concept of the Lower Limit of Detection (LLD) it contributes in the solution of some problems related with the radiological safety, such as the realization of the tests of flight of the sealed radioactive sources; the determination of radioisotopes in environmental samples; the estimate of present radionuclides in polluted foods; in general, the detection of small quantities of radioactive materials present in materials of use or consumption by part of the man in his daily life; as the one Lower Limit of Detection is related with topics of statistics, in this work a small review of them is made, it was superficially discussed the mensuration problems related with the establishment of the Lower Limit of Detection

  1. Malaysian experiences in radiological safety assessment on norm wastes

    International Nuclear Information System (INIS)

    Syed Hakimi Sakuma Syed Ahmad; Khairuddin Mohamad Kontol

    2000-01-01

    Radiological Impact Assessments (RIAs) on proposed disposal sites for NORM wastes were performed in Malaysia. Analysis results were used to derive site specific guidelines for allowable residual concentrations of radionuclides in soil, calculation of doses and risks. Appropriate use scenarios and site specific parameters were used as much as possible so as to be realistic so that will reasonably ensure that individual dose limits and or constraints will be achieved. Disposals were performed to fulfil Atomic Energy Licensing Board of Malaysia (AELB) requirements for which the operator must carry out a radiological impact assessment. This is to demonstrate that no member of public will be exposed to more than 1 mSv/year from all activities. Fatal cancer risk factor is 5x10 -2 per man.Sv. Radionuclides of main concern are radium-226 and radium-228 which are considered as toxic. Sensitivity and uncertainty analyses were performed to show that the parameters used as input into the computer model were justified so as to improve confidence of the public and the AELB in respect of the results of the analysis. Case study to determine a proposed near surface disposal site for treated oil sludge was described. (author)

  2. Shoe concerns and foot problems of wearers of safety footwear.

    Science.gov (United States)

    Marr, S J; Quine, S

    1993-05-01

    In Australia workers in many industries are required to wear safety footwear (footwear incorporating a steel toe cap). An investigation of the problems reported by 321 workers (70 per cent male) employed in a broad range of work activities and required to wear safety footwear was conducted in 1990 and 1991. Respondents were interviewed by a professionally trained podiatrist using a structured questionnaire followed by a foot examination. An extremely high percentage (91 per cent) of subjects reported one or more foot problems (which were verified by the podiatrist), and most considered that the safety footwear either caused the problem or adversely affected an existing foot condition. The main shoe concerns reported were excessive heat (65 per cent of all respondents), inflexible soles (52 per cent), weight (48 per cent) and pressure from steel toe cap (47 per cent). Certain gender differences were identified. General recommendations are made.

  3. Effect of Kiken-Yochi training (KYT) induction on patient safety at the department of radiological technology

    International Nuclear Information System (INIS)

    Yasuda, Mitsuyoshi; Uchiyama, Yushi; Sakiyama, Koshi; Shibata, Masako; Sasaki, Haruaki; Kato, Kyoichi; Nakazawa, Yasuo; Sanbe, Takeyuki; Yoshikawa, Kohki

    2013-01-01

    In this report, we evaluated whether radiological technologists' (RTs') awareness of patient safety would improve and what kind of effects would be seen at the department of radiological technology by introducing KYT [K: kiken (hazard), Y: yochi (prediction), T: (training)]. KYT was carried out by ten RTs based on a KYT sheet for the department of radiological technology. To evaluate the effects of KYT, we asked nine questions each to ten participants before and after KYT enforcement with regard to their attitude to patient safety and to operating procedures for working safely. Significant improvements after KYT enforcement were obtained in two items concerning medical safety: It is important for any risk to be considered by more than one person; The interest in preventive measures against medical accident degree conducted now) and one concerning operating procedures (It is necessary to have a nurse assist during testing with the mobile X-ray apparatus) (p<0.05). Performing KYT resulted in improved awareness of the importance of patient safety. KYT also enabled medical staffers to evaluate objectively whether the medical safety measures currently performed would be effective for patients. (author)

  4. Pre-Exposure Prophylaxis for HIV Prevention: Safety Concerns.

    Science.gov (United States)

    Tetteh, Raymond A; Yankey, Barbara A; Nartey, Edmund T; Lartey, Margaret; Leufkens, Hubert G M; Dodoo, Alexander N O

    2017-04-01

    Available evidence supports the efficacy of pre-exposure prophylaxis (PrEP) in decreasing the incidence of human immunodeficiency virus (HIV) infection among high-risk individuals, especially when used in combination with other behavioural preventive methods. Safety concerns about PrEP present challenges in the implementation and use of PrEP. The aim of this review is to discuss safety concerns observed in completed clinical trials on the use of PrEP. We performed a literature search on PrEP in PubMed, global advocacy for HIV prevention (Aids Vaccine Advocacy Coalition) database, clinical trials registry " http://www.clinicaltrials.gov " and scholar.google, using combination search terms 'pre-exposure prophylaxis', 'safety concerns in the use of pre-exposure prophylaxis', 'truvada use as PrEP', 'guidelines for PrEP use', 'HIV pre-exposure prophylaxis' and 'tenofovir' to identify clinical trials and literature on PrEP. We present findings associated with safety issues on the use of PrEP based on a review of 11 clinical trials on PrEP with results on safety and efficacy as at April 2016. We also reviewed findings from routine real-life practice reports. The pharmacological intervention for PrEP was tenofovir disoproxil fumarate/emtricitabine in a combined form as Truvada ® or tenofovir as a single entity. Both products are efficacious for PrEP and seem to have a good safety profile. Regular monitoring is recommended to prevent long-term toxic effects. The main adverse effects observed with PrEP are gastrointestinal related; basically mild to moderate nausea, vomiting and diarrhea. Other adverse drug effects worth monitoring are liver enzymes, renal function and bone mineral density. PrEP as an intervention to reduce HIV transmission appears to have a safe benefit-risk profile in clinical trials. It is recommended for widespread use but adherence monitoring and real-world safety surveillance are critical in the post-marketing phase to ensure that the benefits

  5. Standards and criteria of international organizations concerning agricultural aspects of radiological emergency situations

    International Nuclear Information System (INIS)

    Richards, J.I.; Hance, R.J.; Crick, M.J.

    1997-01-01

    The nuclear facilities are not generally located in densely populated zones, but usually in rural rather agricultural environment. The Chernobyl accident has shown that farming activities may be affected over hundreds if not thousands kilometers from the accident site. Emergency plans must be implemented in order to trigger countermeasures aiming at reducing agricultural product contamination even in countries having not nuclear facilities or programmes of their own. In Introduction the paper presents the principal objectives to be taken into account by the governmental authorities (at central and local level) after an agricultural countermeasure strategy has been elaborated. The second section deals with the development of criteria and intervening levels. On the basis of the new Recommendations of International Commission on Radiological Protection and the Guidelines concerning the Intervention Levels for Protecting the Public in the Event of a Nuclear Accident or Radiological Emergency issued by an IAEA Consultative Group, IAEA and FAO have published in 1994 common directives concerning the measures to be taken at agricultural level in case of an accidental release of radioactivity. The section 3 presents the concepts and criteria for selecting efficient and appropriate countermeasures. It discusses the importance of planning and intervention preparations, the management of accidents and the proper protection measures. The generic activity levels requiring intervention for withdraw from market of alimentary products are presented in the Section 4. The paper discusses also specific level s of intervention (for milk and meat for instance adopted in Belarus, Ukraine and Russia) as well as future prospects

  6. The safety concept of the Federal Government concerning waste management

    International Nuclear Information System (INIS)

    Pfaffelhuber, J.K.

    1976-01-01

    The safety concept of the FRG concerning waste management is based on the ultimate aim of having in operation until 1985 nuclear power plants with a capacity of approx. 45,000 MWe, i.e. 50 nuclear power plants with an annual fuel consumption of 1,500 tons. A critical survey shows that there is still a great number of questions to be solved, concerning the fuel cycle in particular in terms of industrial standards, and that various problems ought to be the subject of R and D activities. Activities in the field of waste management so far are concerned only with project studies and details of project definition studies. On the one hand, the principles of the safety concept for waste management are to make possible and to guarantee the operation of nuclear facilities, and on the other hand, they are to subject those facilities which serve the purpose of waste disposal to similar safety regulations as the nuclear power plants are subjected to. The integrated waste disposal system of the Federal government for CWRs until the mid eighties is described. R+D activities are still necessary, in particular concerning reprocessing techniques, techniques in the reprocessing of Pu, the conditioning of highly active wastes, testing final storage techniques, and in the field of retention of gaseous radioactive nuclides (iodine, krypton, tritium) and of safeguarding waste disposal parks against terrorists and sabotage. The legal basis for the protection of the citizen is the Atomic Energy Act and its ordinances, EURATOM basic standards, and ICRP recommendations, some of which were tightened up for the FRG. Some recommendations of the Strahlenschutzkommision - radiation exposure, storage and separation of 85 Kr, 129 J, 131 J, and 133 Xe - are dealt with in detail. (HPH/LN) [de

  7. Radiology

    International Nuclear Information System (INIS)

    Bigot, J.M.; Moreau, J.F.; Nahum, H.; Bellet, M.

    1990-01-01

    The 17th International Congress of Radiology was conducted in two separate scientific sessions, one for radiodiagnosis and one for radiation oncology. Topics covered are: Radiobiology -radioprotection; imaging and data processing; contrast media; MRI; nuclear medicine; radiology and disasters; radiology of tropical diseases; cardiovascular radiology; interventional radiology; imaging of trauma; imaging of chest, gastro-intestinal tract, breast and genito-urinary tract; imaging in gynecology;imaging in oncology; bone and joint radiology; head and neck-radiology; neuro-radiology. (H.W.). refs.; fig.; tabs

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

    Science.gov (United States)

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

    2010-09-01

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

  9. Radiological safety at Argonne National Laboratory's heavy ion research facility

    International Nuclear Information System (INIS)

    Cooke, R.H.; Wynveen, R.A.

    1985-01-01

    This paper discusses the radiological safety system to be employed at the Argonne tandem-linac accelerator system (ATLAS). The design parameters of ATLAS that affect safety have remained unchanged since ATLAS construction began in 1982. This paper will present the details of the hardware, the administrative controls, and the radiation monitoring that will be in effect when beam is produced in April 1985. The experimental hall utilizing the maximum energy beam (proportional27 MeV per nucleon) from the completed ATLAS has been partitioned with shielding blocks into its final configuration. Because scientists want access to some of the partitioned-off areas while beam is present in other areas, an interlock and logic system allowing such occupancy has been designed. The rationale and hardware of the system will be discussed. Since one of the potential radiation hazards is high-energy forward-directed neutrons from any location where the beam impinges (such as collimators, bending and focussing systems, experimental targets, and beam stops), radiation surveys and hazard assessments are necessary for the administrative controls that allow occupancy of various areas. Because of the various uses of ATLAS, neutrons (the dominant beam hazard) will be non-existent in some experiments and will be of energies > or approx.10 MeV for a few experiments. These conditions may exist at specific locations during beam preparation but may change rapidly when beam is finally delivered to an experimental area. Monitoring and assessing such time varying and geographically changing hazards will be a challenge since little data will be available on source terms until various beams are produced of sufficient intensity and energy to make measurements. How the operating division for ATLAS and the Argonne safety division are addressing this aspect through administrative controls will also be discussed. (orig./HSI)

  10. Physician attitudes towards pharmacological cognitive enhancement: safety concerns are paramount.

    Directory of Open Access Journals (Sweden)

    Opeyemi C Banjo

    2010-12-01

    Full Text Available The ethical dimensions of pharmacological cognitive enhancement have been widely discussed in academic circles and the popular media, but missing from the conversation have been the perspectives of physicians - key decision makers in the adoption of new technologies into medical practice. We queried primary care physicians in major urban centers in Canada and the United States with the aim of understanding their attitudes towards cognitive enhancement. Our primary hypothesis was that physicians would be more comfortable prescribing cognitive enhancers to older patients than to young adults. Physicians were presented with a hypothetical pharmaceutical cognitive enhancer that had been approved by the regulatory authorities for use in healthy adults, and was characterized as being safe, effective, and without significant adverse side effects. Respondents overwhelmingly reported increasing comfort with prescribing cognitive enhancers as the patient age increased from 25 to 65. When asked about their comfort with prescribing extant drugs that might be considered enhancements (sildenafil, modafinil, and methylphenidate or our hypothetical cognitive enhancer to a normal, healthy 40 year old, physicians were more comfortable prescribing sildenafil than any of the other three agents. When queried as to the reasons they answered as they did, the most prominent concerns physicians expressed were issues of safety that were not offset by the benefit afforded the individual, even in the face of explicit safety claims. Moreover, many physicians indicated that they viewed safety claims with considerable skepticism. It has become routine for safety to be raised and summarily dismissed as an issue in the debate over pharmacological cognitive enhancement; the observation that physicians were so skeptical in the face of explicit safety claims suggests that such a conclusion may be premature. Thus, physician attitudes suggest that greater weight be placed upon the

  11. Questionnaire responses concerning safety issues in MR examination

    International Nuclear Information System (INIS)

    Yamaguchi-Sekino, Sachiko; Nakai, Toshiharu; Muranaka, Hiroyuki

    2011-01-01

    Recently, the rising numbers of medical implants and scanners with higher static magnetic field have increased safety concerns for magnetic resonance (MR) examination. To determine future safety focus, we distributed anonymous questionnaires to 3250 members of the Japanese Society for Magnetic Resonance in Medicine (JSMRM) and received 978 responses. Safety issues on the questionnaire concentrated on the handling of patients with implants (Q7-18, appendix), acoustic trauma due to scanning (Q19-21, appendix), and MR compatibility within the scanner room (Q22-25, appendix). Ninety-three percent of respondents indicated they had encountered cases with implants or medical materials of unknown MR compatibility; 21.7% reported heating problems and 15.0%, nerve stimulation problems, in patients with implants during MR examination. Although 88.7% of respondents recognized the term ''MR compatibility'', 68.2% indicated limited detailed understanding of the term. Eleven percent had had cases with suspected acoustic injury from MR scanner noise. Scanner noise levels were not clarified in any way in 37.4% cases, but 69.5% applied ear protection to patients. Labeling of ''MR compatibility'' of equipment brought into the MR scanner room was reported by 71.9%. More than 50% experienced MR compatibility issues related to equipment brought into the MR scanner room. With regard to safety issues on metallic objects which are implanted in MR workers, 88.1% indicated they would continue current operations even the implant is inside the body. Respondents identified lectures and seminars by professional societies, safety training by manufacturers, and information from the Internet and literature as the 3 main sources for up-dating safety information for MR examination. (author)

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

    International Nuclear Information System (INIS)

    2002-01-01

    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

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

    International Nuclear Information System (INIS)

    2005-01-01

    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

  14. Safety concerns for superconducting magnets of upcoming fusion experiments

    International Nuclear Information System (INIS)

    Turner, L.R.

    1983-01-01

    -Several fusion experiments being constructed (Tore Supra) or contemplated (DCT 8, Alcator DCT) feature superconducting coils. These coils introduce the following safety concerns: 1. Internally Cooled Conductor (ICC). ICC's are found to be highly stable against short heat pulses, even when the coolant is stagnant or moving at low steady-state velocity. However, a large heat pulse is certain to quench the conductor. Thus, determining the stability limits is vital. 2. Helium II Cooling. Helium II has both unique advantages as a coolant and unique safety problems. 3. Shorted Turns. In magnets with shorts from operational accidents, the current can switch back and forth between the short and the shorted turns, as those alternatively go normal and superconducting. 4. Hybrid Superconducting-Normal Conducting Coil System. The possibility of unequal currents in the different magnets and thus of unexpected forces on the superconducting magnets is much greater than for an all-superconducting system. Analysis of these problems are presented

  15. Development of safety analysis technology for integral reactor; evaluation on safety concerns of integral reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hee Chul; Kim, Woong Sik; Lee, J. H. [Korea Institute of Nuclear Safety, Taejeon (Korea)

    2002-03-01

    The Nuclear Desalination Plant (NDP) is being developed to produce electricity and fresh water, and is expected to locate near population zone. In the aspect of safety, it is required to protect the public and environment from the possible releases of fission products and to prevent the fresh water from the contamination of radioactivity. Thus, in this study, the safety characteristics of the integral reactor adopting passive and inherent safety features significantly different from existing nuclear power plants were investigated. Also, safety requirements applicable to the NDP were analyzed based on the regulatory requirements for current light water reactor and advanced reactor designs, and user requirements for small-medium size reactors. Based on these analyses, some safety concerns to be considered in the design stage have been identified and discussed. They include the use of proven technology for new safety features, systematic event classification and selection, strengthening containment function, and the safety impacts on desalination-related systems. The study presents the general safety requirements applicable to licensing of an integral reactor and suggests additional regulatory requirements, which need to be developed, based on the direction to resolution of the safety concerns. The efforts to identify and technically resolve the safety concerns in the design stage will provide the early confidence of SMART safety and the technical basis to evaluate the safety to designers and reviewers in the future. Suggestion on the development of additional regulatory requirements will contribute for the regulator to taking actions for licensing of an integral reactor. 66 refs., 5 figs., 24 tabs. (Author)

  16. National Institute for Radiological Protection and Nuclear Safety - IRSN. Annual Report 2016, Financial Report 2016

    International Nuclear Information System (INIS)

    2017-01-01

    IRSN is the nation's public service expert in nuclear and radiation risks, and its activities cover all the related scientific and technical issues in France and in the international arena. Its work therefore concerns a wide range of complementary fields, including environmental monitoring, radiological emergency response, radiation protection and human health in normal and accident situations, prevention of major accidents, and safety and security relating to nuclear reactors, plants, laboratories, transportation, and waste. It also carries out assessments in the nuclear defense field. In addition, IRSN contributes to government policy in nuclear safety, the protection of human health and the environment against ionizing radiation, and measures aimed at safeguarding nuclear materials, facilities and transportation operations against the risk of malicious acts. Within this context, it interacts with all the organizations concerned including public authorities, in particular nuclear safety and security authorities, local authorities, businesses, research organizations, and stakeholder associations. This document is IRSN's annual and financial report for 2016. Content: 1 - Activity Key Figures; 2 - Strategy; 3 - Panorama 2016; 4 - Activities: safety (Safety of civil nuclear facilities, Experimental reactors, Nuclear fuel cycle facilities, Human and organizational factors, Reactor aging, Severe accidents, Fuel, Criticality, Fire and containment, Natural hazards, Defense-related facilities and activities, Radioactive waste management, Geological disposal of radioactive waste); security and nonproliferation (Nuclear security, Nuclear nonproliferation, Chemical weapons ban); radiation protection - human and environment health (Environmental monitoring, Radon and polluted sites, Radiation protection in the workplace, Effects of chronic exposure, Protection in health care); emergency and post-accident situations (Emergency preparedness and response, Post

  17. Compliance of Iranian dentists with safety standards of oral radiology

    Science.gov (United States)

    Shahab, S; Kavosi, A; Nazarinia, H; Mehralizadeh, S; Mohammadpour, M; Emami, M

    2012-01-01

    Objectives Dentists use radiographs in their daily practice. Their knowledge and behaviour towards radiographic examination can affect patients' exposure to radiation. The aim of this study was to survey the knowledge and behaviour of Iranian dentists regarding oral radiology safety standards. Methods 1000 questionnaires were given to the participants of the 48th Annual Congress of the Iranian Dental Association, of which 700 were returned. The participants were asked about demographic data, primary knowledge of radiation protection, selection criteria, radiographic equipment and technique, methods of patient and personnel protection and management of radiographic waste. Descriptive analysis of data was performed. Results 44% of respondents said the initial radiograph they took was of the periapical view of a limited area. 12% preferred the periapical paralleling technique. F-speed film was used by 9% and E-speed film by 62%. Only 2% had digital receptors. Proper exposure time was selected by 26.5%. The use of long and rectangular collimators was 15% and 6%, respectively. 34% occasionally covered their patients with both thyroid shields and lead aprons. 36% used the position and distance rule correctly for their own protection. Proper disposal of the used processing solutions and the lead foils were done by only 1% and 3%, respectively. Conclusions It can be concluded that the majority of dentists in the study group did not select the proper method, material and equipment in order to minimize the exposure of their patient to unnecessary radiation in dental radiography. PMID:22301640

  18. Radiological safety of decayed source removal facility (DSRF) - an overview

    International Nuclear Information System (INIS)

    Rajput, Raksha; George, Jain Reji; Pathak, B.K.

    2018-01-01

    Industrial radiography is one of the major applications of radioisotope in engineering industry for Non-Destructive Testing (NDT). The equipment used for this purpose is called Industrial Radiography Exposure Device (IGRED) or radiography (RG) camera. In India, more than 1800 IGREDs including imported cameras are being used in NDT industry. These cameras are of different types and have various capacities to house different radioisotopes. Generally, 192 Ir sources are being used for NDT work. The sources are being supplied by BRIT to the users. After the useful period of the utilization of gamma intensity, the decayed source is returned to BRIT in RG camera. The decayed source is removed from the camera in the Decayed Source Removal Facility (DSRF). This facility serves the purpose of a miniature hot-cell with the capability of storing the decayed sources which are removed from the cameras. The empty camera is inspected for its mechanical functions and sent to BRIT's hot-cell for loading the new source. DSRF is situated at BRIT Vashi Complex. This paper deals with the radiological safety in the operation of DSRF for removing decayed sources from industrial radiography cameras

  19. Study contribution to the new international philosophy of the radiological safety system on chemical processing of the natural uranium

    International Nuclear Information System (INIS)

    Silva, T.M. da.

    1988-01-01

    The objective of the work is to adapt the radiological Safety System in the facilities concerned to the chemical treatment of the uranium concentrated (yellow-cake) until conversion in uranium hexafluoride in the pilot plant of IPEN-CNEN/SP, to the new international philosophy adopted by the International Commission Radiological on Protection ICPR publication 22(1973), 26(1977), 30(1978) and the International Atomic Energy Agency IAEA publication 9(1982). The new philosophy changes fully the Radiological Protection concepts of preceding philosophy, changes, also, the concept of the work place and individual monitoring as well as the classification of the working areas. These new concepts are applied in each phase of the natural uranium treatment chemical process in conversion facility. (author)

  20. Safety coaches in radiology: decreasing human error and minimizing patient harm

    Energy Technology Data Exchange (ETDEWEB)

    Dickerson, Julie M.; Adams, Janet M. [Cincinnati Children' s Hospital Medical Center, Department of Radiology, MLC 5031, Cincinnati, OH (United States); Koch, Bernadette L.; Donnelly, Lane F. [Cincinnati Children' s Hospital Medical Center, Department of Radiology, MLC 5031, Cincinnati, OH (United States); Cincinnati Children' s Hospital Medical Center, Department of Pediatrics, Cincinnati, OH (United States); Goodfriend, Martha A. [Cincinnati Children' s Hospital Medical Center, Department of Quality Improvement, Cincinnati, OH (United States)

    2010-09-15

    Successful programs to improve patient safety require a component aimed at improving safety culture and environment, resulting in a reduced number of human errors that could lead to patient harm. Safety coaching provides peer accountability. It involves observing for safety behaviors and use of error prevention techniques and provides immediate feedback. For more than a decade, behavior-based safety coaching has been a successful strategy for reducing error within the context of occupational safety in industry. We describe the use of safety coaches in radiology. Safety coaches are an important component of our comprehensive patient safety program. (orig.)

  1. Safety coaches in radiology: decreasing human error and minimizing patient harm

    International Nuclear Information System (INIS)

    Dickerson, Julie M.; Adams, Janet M.; Koch, Bernadette L.; Donnelly, Lane F.; Goodfriend, Martha A.

    2010-01-01

    Successful programs to improve patient safety require a component aimed at improving safety culture and environment, resulting in a reduced number of human errors that could lead to patient harm. Safety coaching provides peer accountability. It involves observing for safety behaviors and use of error prevention techniques and provides immediate feedback. For more than a decade, behavior-based safety coaching has been a successful strategy for reducing error within the context of occupational safety in industry. We describe the use of safety coaches in radiology. Safety coaches are an important component of our comprehensive patient safety program. (orig.)

  2. Safety coaches in radiology: decreasing human error and minimizing patient harm.

    Science.gov (United States)

    Dickerson, Julie M; Koch, Bernadette L; Adams, Janet M; Goodfriend, Martha A; Donnelly, Lane F

    2010-09-01

    Successful programs to improve patient safety require a component aimed at improving safety culture and environment, resulting in a reduced number of human errors that could lead to patient harm. Safety coaching provides peer accountability. It involves observing for safety behaviors and use of error prevention techniques and provides immediate feedback. For more than a decade, behavior-based safety coaching has been a successful strategy for reducing error within the context of occupational safety in industry. We describe the use of safety coaches in radiology. Safety coaches are an important component of our comprehensive patient safety program.

  3. Radiation Safety in the Neonatal Intensive Care Unit: Too Little or Too Much Concern?

    Directory of Open Access Journals (Sweden)

    Cheng-Chung Yu

    2010-12-01

    Full Text Available With rising numbers of extremely premature infants in the neonatal intensive care unit (NICU who require multiple radiologic examinations for their complex medical conditions, concerns the risk of radiation exposure become a more prevalent issue. The biological effects from cumulative doses of both primary and secondary radiation can be particularly troubling for very premature babies due to their inherent sensitivity to both iatrogenic and environmental insults. Similarly, radiologic studies performed in the NICU pose potentially significant exposure risks to caretakers and to the families of patients often present in the NICU during these examinations. The purpose of this article is to critically review the available literature regarding current exposure rates in the NICU, address the validity of radiation exposure concerns, and suggest areas for improvement. With few exceptions, studies reveal that there were only low doses of radiation derived from any single radiographic examination in standard NICUs and that the radiation dosage used was in compliance with recommendations made by the Commission of European Communities (EC and International Commission on Radiological Protection (ICRP. However, there were wide variations in the radiation dose per single examination (mean entrance skin doses ranged from 15 to 73.6 μGy and in the frequency (mean ranged from 3.2 to 31 examinations per infant of those examinations. Studies also reported low secondary exposure rates from scatter radiation to others present in the NICU during radiographic examinations. Key to limiting unnecessary radiation exposure in the NICU is the employment of proper radiation techniques and safety measures. Thus, adhering to recommendations made by the EC and ICRP can help to reduce the anxiety of patients' families and medical staff regarding their risks from the effects of ionizing radiation in the NICU.

  4. Radioactive sources of main radiological concern in the Kola-Barents region

    International Nuclear Information System (INIS)

    Bergman, R.; Baklanov, A.

    1998-07-01

    transport. The danger of uncontrolled chain reactions constitutes a potentially severe risk associated with both nuclear submarines and spent nuclear fuel. The problems involved in maintaining adequate and sufficient storage capacity have escalated recently. At present most storage facilities are filled to the limit. The principal research needs have been identified and classified in two groups. The first concerns objects or situations of known or probable risk, for which the radiological consequences may be relatively high. The need of research given high priority reflects the known or potential importance of certain chains of events for radioactive releases and associated radiological consequences. The assessments and ranking of priority summarised in this report often focus directly on radiological consequences. However, severe accidents leading to radioactive release are likely to influence social and economic conditions in areas subjected to substantial radioactive contamination. Such associated socio-economic effects have not been touched upon at least not explicitly. Yet, these issues are undoubtedly highly relevant, and constitute elements that besides the radiological issues proper would be particularly suited for further analyses. Some facets of this complex interactions are also discussed

  5. Radioactive sources of main radiological concern in the Kola-Barents region

    Energy Technology Data Exchange (ETDEWEB)

    Bergman, R.; Baklanov, A

    1998-07-01

    transport. The danger of uncontrolled chain reactions constitutes a potentially severe risk associated with both nuclear submarines and spent nuclear fuel. The problems involved in maintaining adequate and sufficient storage capacity have escalated recently. At present most storage facilities are filled to the limit. The principal research needs have been identified and classified in two groups. The first concerns objects or situations of known or probable risk, for which the radiological consequences may be relatively high. The need of research given high priority reflects the known or potential importance of certain chains of events for radioactive releases and associated radiological consequences. The assessments and ranking of priority summarised in this report often focus directly on radiological consequences. However, severe accidents leading to radioactive release are likely to influence social and economic conditions in areas subjected to substantial radioactive contamination. Such associated socio-economic effects have not been touched upon at least not explicitly. Yet, these issues are undoubtedly highly relevant, and constitute elements that besides the radiological issues proper would be particularly suited for further analyses. Some facets of this complex interactions are also discussed 151 refs, 30 figs, 3 tabs

  6. Research and managing institutions in Ukraine concerning the radiological consequences of the Chernobyl accident

    International Nuclear Information System (INIS)

    Nasvit, O.

    1998-01-01

    The paper presents temporal changes of the national organizations in managing the Chernobyl accident and its activities. The National Academy of Sciences of Ukraine started its activity from the first days after the accident. In 1990 a special executive body, the State committee of Chernobyl Affairs was established in Ukraine to manage the whole activity to overcome the Chernobyl problems. In 1991 it was rearranged into the Ministry of Chernobyl Affairs. In 1996 a new Ministry of Ukraine on Emergences and Affairs of Population Protection from the Consequences of Chernobyl Catastrophe(MEA) was founded on the basis of the Min. Chernobyl and Headquarters Staff of Civil Defence. The National Commission on Radiological Protection of Ukraine (NCRPU) belongs to the Parliament structure. NCRPU is responsible for approval of radiological safety standards and derived regulations. Very often the regulation approved are stricter than the international recommendations. There is an essential lack of attention within the Parliament to the activity of NCRPU. Ministry of Health is responsible for all kinds of medical care for the people suffering from the Chernobyl Catastrophe. In order to provide permanent medical service, a nation-wide scheme has been worked out. Scientific Center for Radiation Medicine is the leading scientific institute of the Academy of Medical Sciences. The State scientific Center of Environmental Radio geochemistry was created in 1996 on the basis of the two departments of the Institute of Geochemistry. The Center was created in order to improve coordination and managing of scientific researches on the behavior of artificial and natural radionuclides and chemical substances in the environment etc.. The Chernobyl Scientific-Technical center for International Research was created in March,1996. The Ukrainian Scientific Hygienic Center of Ministry of Health was created in 1989 and included two institutions. The subjects, the direction of research works

  7. Radiology

    International Nuclear Information System (INIS)

    Edholm, P.R.

    1990-01-01

    This is a report describing diagnostic techniques used in radiology. It describes the equipment necessary for, and the operation of a radiological department. Also is described the standard methods used in radiodiagnosis. (K.A.E.)

  8. Key issues concerning changes in the radiological protection system: some thoughts from the French Society for Radiation Protection (SFRP)

    International Nuclear Information System (INIS)

    Schieber, C.; Cordoliani, Y.S.

    2002-01-01

    In 1999, the International Radiological Protection Association (IRPA) asked for contributions to the debate on future changes to the radiological protection system proposed by the International Commission on Radiological Protection (ICRP). In response, the Board of the French Society for Radiation Protection (SFRP) created a working group to deal specifically with this issue. It met on several occasions between April and July and its findings were presented at the IRPA Congress in May 2000. They were also published in the French journal Radioprotection and in the British Journal of Radiological Protection. To further its discussions, the Board of the SFRP decided to create a second working group which became operational in September 2001. It has around 20 members representing the major players in the radiological protection field in France: authorities, experts and professionals from the nuclear, medical and research fields as well as one association representative (the list of members can be found at the end of this document). The working group was set up to produce proposals relating to the key issues likely to be raised, particularly by the ICRP, concerning the development of new radiological protection recommendations. The members of the working group analysed the ICRP memorandum published in the June 2001 edition of the Journal of Radiological Protection and used their own experience to determine what these key issues would be. The following issues were discussed: General thoughts on the new radiological protection system proposed by the ICRP, Individual and collective approaches to the radiological risk, Comparison with chemical risk management, Radiological protection of the environment, Changes in exposure levels and units of measurement. This paper, which has been approved by the Board of the SFRP, gives the main conclusions of the working group on the key issues in these areas. It is intended to reflect the various opinions expressed during the groups

  9. The communication of radiological risk to populations exposed to a radiological accident: considerations concerning the accident in Goiania

    International Nuclear Information System (INIS)

    Curado, M.P.

    1996-01-01

    The main purpose of this paper is to describe the reactions of a population subjected to the effects of a radiological accident and receiving information about radiation effects for the first time. The behaviour of the victims during various phases of the accident is discussed. (author)

  10. Learning from errors in radiology to improve patient safety.

    Science.gov (United States)

    Saeed, Shaista Afzal; Masroor, Imrana; Shafqat, Gulnaz

    2013-10-01

    To determine the views and practices of trainees and consultant radiologists about error reporting. Cross-sectional survey. Radiology trainees and consultant radiologists in four tertiary care hospitals in Karachi approached in the second quarter of 2011. Participants were enquired as to their grade, sub-specialty interest, whether they kept a record/log of their errors (defined as a mistake that has management implications for the patient), number of errors they made in the last 12 months and the predominant type of error. They were also asked about the details of their department error meetings. All duly completed questionnaires were included in the study while the ones with incomplete information were excluded. A total of 100 radiologists participated in the survey. Of them, 34 were consultants and 66 were trainees. They had a wide range of sub-specialty interest like CT, Ultrasound, etc. Out of the 100 responders, 49 kept a personal record/log of their errors. In response to the recall of approximate errors they made in the last 12 months, 73 (73%) of participants recorded a varied response with 1 - 5 errors mentioned by majority i.e. 47 (64.5%). Most of the radiologists (97%) claimed receiving information about their errors through multiple sources like morbidity/mortality meetings, patients' follow-up, through colleagues and consultants. Perceptual error 66 (66%) were the predominant error type reported. Regular occurrence of error meetings and attending three or more error meetings in the last 12 months was reported by 35% participants. Majority among these described the atmosphere of these error meetings as informative and comfortable (n = 22, 62.8%). It is of utmost importance to develop a culture of learning from mistakes by conducting error meetings and improving the process of recording and addressing errors to enhance patient safety.

  11. Overview on measures concerning the radiation exposure reduction following events with serious radiological consequences (catalogue of measures) Pt. 2. Background information, theory and examples of use

    International Nuclear Information System (INIS)

    Genkel, Simone; Schnadt, Horst

    2010-01-01

    The report edited by the German Federal Ministry for the Environment, Nature Conservation and Nuclear Safety includes the following chapters: Summary of materials: international nuclear and radiological event scale (INES), nuclear power plants in Europe, significance of the reference nuclide I-131, emergency protection measures, radiation protection measures, contaminated surface waters, contaminated matter disposal, prevention of radiation exposure by inhalation, decision making concerning agriculture and food, radiation protection during disposal procedures. Theoretical fundamentals: decontamination, dose rate, contaminated soils, inhalation dose, contaminated articles, contaminated surface waters, contaminated skin, contamination by ingestion, conversion factors, calculation procedures for appropriate measures. Examples for use of the catalogue of measures.

  12. Radiological Source Terms for Tank Farms Safety Analysis

    Energy Technology Data Exchange (ETDEWEB)

    COWLEY, W.L.

    2000-06-27

    This document provides Unit Liter Dose factors, atmospheric dispersion coefficients, breathing rates and instructions for using and customizing these factors for use in calculating radiological doses for accident analyses in the Hanford Tank Farms.

  13. Ayurveda formulations: A roadmap to address the safety concerns

    Directory of Open Access Journals (Sweden)

    Kishor Patwardhan

    2017-10-01

    Full Text Available It is a matter of serious concern that the number of case reports pointing at a possible association between the clinical toxicity and the use of Ayurveda formulations is increasing significantly over the years in scientific medical literature. Though most of these cases are connected with the presence of heavy metals such as lead, mercury and arsenic in these formulations, there are also reports suggesting toxicity due to the presence of toxic chemicals of herbal origin. In the year 2008, the Government of India took an initiative of establishing the National Pharmacovigilance Programme for Ayurveda, Siddha and Unani drugs in a structured way. However, due to lack of sustained support, this program has now become defunct. This issue is of vital importance and needs to be addressed effectively on a priority basis. In this communication, we propose the following crucial policy interventions to be introduced at different levels: a. Amendments to Drug and Cosmetic Act, b. Issuing consumer guidelines, c. Issuing prescription guidelines, d. Issuing clinical monitoring guidelines, e. Implementation of good manufacturing guidelines, f. Promoting documentation of clinical safety, g. Identifying the sources of contamination, and, h. Provision for stringent punishment. If these policy interventions are taken up and implemented, a significant positive change in the scenario can be expected in the near future.

  14. Production of neutrons in particle accelerators: a PNRI safety concern

    International Nuclear Information System (INIS)

    Garcia, Corazon M.; Cayabo, Lynette B.; Artificio, Thelma P.; Melendez, Johnylen V.; Piquero, Myrna E.; Parami, Vangeline K.

    2002-09-01

    In the safety assessment made for the first cyclotron facility in the Philippines, that is the cyclotron in the P.E.T. (Positron Emission Tomography) center of the St. Luke's Medical Center, the concern on the production of neutrons associated with the operation of particle accelerators has been identified. This takes into consideration the principles in the operation of particle accelerators and the associated production of neutrons resulting from their operation, the hazards and risks in their operation. The Bureau of Health Devices and Technology (BHDT) of the Department of Health in the Philippines regulates and controls the presently existing six (6) linear accelerators distributed in different hospitals in the country, being classified as x-ray producing devices. From the results of this study, it is evident that the production of neutrons from the operation of accelerators, produces neutrons and that activation due to neutrons can form radioactive materials. The PNRI (Philippine Nuclear Research Institute) being mandated by law to regulate and control any equipment or devices producing or utilizing radioactive materials should take the proper steps to subject all accelerator facilities and devices in the Philippines such as linear accelerators under its regulatory control in the same manner as it did with the first cyclotron in the country. (Author)

  15. Health and safety concerns of textiles with nanomaterials

    Science.gov (United States)

    Almeida, L.; Ramos, D.

    2017-10-01

    There is a growing concern related to the effects of nanomaterials in health and safety.Nanotechnologies are already present in many consumer products, including textiles. “Nanotextiles” can be considered as traditional textiles with the incorporation of nanoparticles. They present often functionalities such as antibacterial, ultraviolet radiation protection, water and dirt repellency, self-cleaning or flame retardancy. Nanoparticles can be released from the textile materials due to different effects (abrasion and other mechanical stresses, sweat, irradiation, washing, temperature changes, etc.). It is then expectable that “nanotextiles” may release individual nanoparticles, agglomerates of nanoparticles or small particles of textile with or without nanoparticles, depending on the type of integration of the nanoparticles in textiles. The most important exposure route of the human body to nanoparticles in case of textiles is skin contact. Several standards are being developed under the auspices of the European Committee for Standardization. In this paper, it is presented the development and application of a test method to evaluate the skin exposure to nanoparticles, to evaluate the transfer of the nanoparticles from the textile to the skin by the effect of abrasion and sweat.

  16. Nuclear safety. Concerns about the nuclear power reactors in Cuba

    International Nuclear Information System (INIS)

    Wells, Jim; Aloise, Gene; Flaherty, Thomas J.; Fitzgerald, Duane; Zavala, Mario; Hayward, Mary Alice

    1992-09-01

    the atmosphere, contains defective welds. Another said that reactor operator trainees have received training on inadequate reactor simulators. In contrast, a representative of the Cuban government told us that Cuba wants to build its reactor in accordance with safety standards. Also, according to information provided to us by a representative of the Russian government, Cuba's reactor has been constructed according to safety rules that take into account, among other things, the possible impacts of an earthquake. State Department, NRC, and DOE officials have expressed a number of concerns about the construction and operation of Cuba's nuclear power reactors. According to State Department officials, the United States maintains a comprehensive embargo on any U.S. transactions with Cuba and discourages other countries from providing assistance, except for safety purposes, to Cuba's nuclear power program. The United States would prefer that the construction of the reactors never be completed and wants Cuba to sign the Non-Proliferation Treaty or the Treaty of Tlatelolco, both of which bind signatories to blanket nonproliferation commitments for their entire nuclear program, before the United States considers reversing its policy of discouraging other countries from assisting Cuba with the construction of the reactors. The United States has asked Russia to cease providing any nuclear assistance until Cuba has signed either treaty. NRC officials are aware of, but could not verify, the Cuban emigres' allegations of safety deficiencies because available information was limited. They said, however, that if the allegations were true, the cited deficiencies could affect the safety of the reactors operation. In addition, they expressed concern about the ability of Cuba's industrial infrastructure to support the nuclear power reactors, the lack of a regulatory structure, the adequacy of training for reactor operators, the quality of the civil construction, and the design of the

  17. Gonad Shielding for Patients Undergoing Conventional Radiological Examinations: Is There Cause for Concern?

    OpenAIRE

    Karami; Zabihzadeh; Gholami

    2016-01-01

    Background Gonad shielding is one of the fundamental methods by which to protect reproductive organs in patients undergoing conventional radiological examinations. A lack of or inadequate shielding of the gonads may increase the exposure of these organs and result in malignancies future generations. Objectives The aim of this study is to investigate the prevalence of gonad shielding in patients undergoing conventional radiological...

  18. Stockholm Safety Conference. Analysis of the sessions on radiological protection, licensing and risk assessment

    International Nuclear Information System (INIS)

    Gea, A.

    1981-01-01

    A summary of the sessions on radiological protection, licensing and risk assessment in the safety conference of Stockholm is presented. It is considered the new point of view of the nuclear safety, probabilistic analysis, components failures probability and accident analysis. They are included conclusions applicable in many cases to development countries. (author)

  19. Indicators of the management for the continuous improvement of the radiological safety in a radioactive facility

    International Nuclear Information System (INIS)

    Amador B, Z. H.

    2006-01-01

    The use of safety indicators is common in the nuclear industry. In this work the implementation of indicators for the efficiency analysis of the radiological safety management system of a radioactive installation is presented. Through the same ones the occupational exposure, the training Y authorization of the personnel, the control of practices Y radioactive inventory, the results of the radiological surveillance, the occurrence of radiological events, the aptitude of the monitoring equipment, the management of the radioactive waste, the public exposure, the audits Y the costs of safety are evaluated. Its study is included in the periodic training of the workers. Without this interrelation it is not possible to maintain the optimization of the safety neither to achieve a continuous improvement. (Author)

  20. Oil wells and gas wells: aspects of radiological safety

    International Nuclear Information System (INIS)

    Soares, S.M.V.O.

    1987-01-01

    The objective of the present work is to present and analyse the main radiological protection problems associated with non destructive inspections of oil wells, with the view of minimizing the dose to members of the public living in nearby urban zones. Problems related to the surveillance of such activities and the need for well formulated procedures are also discussed based on specific Brasilian regulations. Finally, some examples of radiological accidents that have occured in urban zones are described including the methodology employed for the rescue of Iridium-192 sources and for the estimate of radiation doses for workers and general public. (author) [pt

  1. Overview of Generation IV (Gen IV) Reactor Designs - Safety and Radiological Protection Considerations. Published on September 24, 2012

    International Nuclear Information System (INIS)

    Couturier, Jean; Bruna, Giovanni; Baudrand, Olivier; Blanc, Daniel; Ivanov, Evgeny; Bonneville, Herve; Clement, Bernard; Kissane, Martin; Meignen, Renaud; Monhardt, Daniel; Nicaise, Gregory; Bourgois, Thierry; Hache, Georges

    2012-01-01

    The purpose of this document is to provide an updated overview of specific safety and radiological protection issues for all the reactor concepts adopted by the GIF (Generation IV International Forum), independent of their advantages or disadvantages in terms of resource optimization or long-lived-waste reduction. In particular, this new document attempts to bring out the advantages and disadvantages of each concept in terms of safety, taking into account the Western European Nuclear Regulators' Association (WENRA) statement concerning safety objectives for new nuclear power plants. Using an identical framework for each reactor concept (sodium-cooled fast reactors or SFR, high / very-high temperature helium-cooled reactors of V/HTR, gas-cooled fast reactors or GFR, lead-or lead / bismuth-cooled fast reactors or LFR, molten salt reactors or MSR, and supercritical-water-cooled reactors or SCWR), this summary report provides some general conclusions regarding their safety and radiological protection issues, inspired by WENRA's safety objectives and on the basis of available information. Initial lessons drawn from the events at the Fukushima-Daiichi nuclear power plant in March 2011 have also been taken into account in IRSN's analysis of each reactor concept

  2. Gonad Shielding for Patients Undergoing Conventional Radiological Examinations: Is There Cause for Concern?

    Directory of Open Access Journals (Sweden)

    Karami

    2016-04-01

    Full Text Available Background Gonad shielding is one of the fundamental methods by which to protect reproductive organs in patients undergoing conventional radiological examinations. A lack of or inadequate shielding of the gonads may increase the exposure of these organs and result in malignancies future generations. Objectives The aim of this study is to investigate the prevalence of gonad shielding in patients undergoing conventional radiological examinations and the availability of gonad shields and gonad shielding protocols in radiology departments. Materials and Methods A retrospective, observational cross-sectional study on the application of gonad shielding, the availability of gonad shields and the existence of gonad shielding protocols in radiology departments was performed in five different hospitals in Ahvaz, Iran. Results The highest application of gonad shielding was 6.6% for the pediatric hospital. The prevalence of gonad shielding was less than 0.2%. In 64.3% of the radiography rooms, at least one flat-contact gonad shield of a large size was available. Only large-sized gonad shields were available. Curved-contact and shadow gonad shields did not exist. Gonad shielding protocols were not existence in any of the fourteen radiography rooms investigated. Conclusions Comprehensive protection programs with on-the-job training courses for staff members are strongly recommended, as well as, the provision of radiological shields and gonad shielding protocols in radiology departments to reduce the patient’s radiation dose during radiological examinations.

  3. The present condition of the radiation safety control education in training schools for radiological technologists

    International Nuclear Information System (INIS)

    Takahashi, Yasuyuki; Saito, Kyoko; Hirai, Shoko; Igarashi, Hiroshi; Negishi, Tooru; Hirano, Kunihiro; Kawaharada, Yasuhiro

    2010-01-01

    We made a detailed study on the course of study in radiation safety control prescribed on March 28, 2003. Questionnaires were sent to 39 training schools for radiological technology, to which 66.7% replied (26/39). Subjects on radiation safety control must include knowledge and technology in both radiation control and medical safety. The contents for instruction of radiation control were in accordance with those given in the traditional program; however, some discrepancies were found in the contents of medical safety. As medical safety, emphasized by the revised Medical Service Law, is regarded as very important by many hospitals, safety control education that include medical ethics should be required as part of the curriculum in the training schools for radiological technologists. (author)

  4. Radiological safety training for accelerator facilities: DOE handbook

    International Nuclear Information System (INIS)

    1997-03-01

    This program management guide describes the proper implementation standard for core training as outline in the DOE Radiological Control (RadCon) Manual. Its purpose is to assist DOE employees and Managing and Operating (M ampersand O) contractors having responsibility for implementing the core training recommended by the RadCon Manual

  5. Radiological safety training for accelerator facilities: DOE handbook

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-03-01

    This program management guide describes the proper implementation standard for core training as outline in the DOE Radiological Control (RadCon) Manual. Its purpose is to assist DOE employees and Managing and Operating (M&O) contractors having responsibility for implementing the core training recommended by the RadCon Manual.

  6. Radiological profile of pulmonary tuberculosis in HIV: concerning 171 observations in Kinshasa

    International Nuclear Information System (INIS)

    Djamba, O.N.; Mukaya, J.; Kayembe, J.M.

    2011-01-01

    This prospective descriptive study was conducted in Depistage center of the Tuberculosis treatment of Kabinda during a period of three months, had as objectives to study the radiological profile of pulmonary tuberculosis in HIV and HIV- patients, then to compare the frequency of different radiological abnormalities between the two groups to determine some characteristics of co-infection HIV/TP+. Among 171 patients with contagious pulmonary tuberculosis, 50 patients had positive serology for HIV, a prevalence of 29,2%. The intrathoracic lymph nodes, localized lesions only in the lower field were more observed in HIV, as well as pleurisy and the absence of radiological abnormality. The only one case of miliary was HIV positive. By contrast, excavations and localized lesions in the upper field were predominant in HIV-. Atypical radiological manifestations of pulmonary tuberculosis were more common in patients with HIV infection.

  7. Contribution to the study of the new international philosophy of the radiological safety in the natural uranium chemical treatment

    International Nuclear Information System (INIS)

    Moraes da Silva, T. de

    1990-01-01

    The objective of this work is to adapt the Radiological Safety System in the facilities concerned to the chemical treatment of the uranium concentrated (yellow-cake) until conversion in uranium hexafluoride in the pilot plant of IPEN-CNEN/SP, to the new international philosophy adopted by ICRP and IAEA. The new philosophy changes fully the Radiological Protection concepts of preceding philosophy, changes, also, the concept of the workplace and individual monitoring as well as the classification of the working areas. In this paper we show the monitoring program, in each phase of the natural uranium treatment chemical process in conversion facility for external irradiation, surface contamination and air contamination. The results were analysed according with the new philosophy and used to reclassify the workplace. It was introduced the condition work concept taking account the time spent by the worker in that workplace. (author)

  8. Evaluation of radiological safety conditions of panoramic portable irradiators of industrial radiography used in Brazil

    International Nuclear Information System (INIS)

    Aquino, Josilto Oliveira de

    2003-08-01

    In Brazil, the applications of ionizing radiation in industrial area are performed in about 900 installations, in which around 3000 radioactive sources are handled. Industrial radiography represents 14 % of this total, with 217 X rays equipment and 287 gamma radiography apparatus, according to a survey conducted in the present work. From these gamma apparatus, 90 % employ 192 Ir sources, followed by 60 Co and 75 Se, with 5 % each. The great majority of the 192 Ir apparatus have been in continuous usage in Brazil for more than 20 years, which means that they are old equipment. The totality of the 11 models of 192 Ir apparatus used in Brazil is imported from abroad. Those apparatus are portable, and almost all operate according to category II, i.e., the source assembly is mechanically projected out of the container. This last characteristic, besides the fact that the apparatus are already old-fashioned and worn-out, raises concerns about their radiological safety. The main objective of this work was to develop a specific methodology for inspection, testing and assessment of the radiological safety devices and state of maintenance of the 192 Ir apparatus. The idea is to prevent accidents, as physical failures can lead to overexposure of working staffs. In order to accomplish this, almost a hundred 192 Ir apparatus, from the 11 models used in Brazil, were studied. According to our results, almost 20 % of the 97 apparatus evaluated presented some kind of unsafe condition for proper operation, like poor state of maintenance and faults at the lock that retains the source at the secure position. From the 11 imported models of 192 Ir apparatus in use in Brazil, six models were already manufactured incorporating the safety devices specified by the first edition of the Standard ISO 3999, edited in 1977. However, five models do not comply even with this first edition of the Standard ISO 3999. Thus, they lack some important and basic safety devices. None of the 11 models comply

  9. Definitive closure of nuclear power plants. Aspects concerning physical safety

    International Nuclear Information System (INIS)

    Rodriguez, C.; Puntarulo, L.; Canibano, J.

    1988-01-01

    This paper analyzes the various safety requirements that must be fulfilled by nuclear power plants for their operation without restrictions, such as safeguards, nuclear safety and physical protection. Physical protection, the subject most extensively dealt by the authors, is defined as safety measures aimed at providing protection against deliberate hostile deeds, such as robberies or non-authorized transport of radioactive materials or sabotage in nuclear facilities, performed either by individuals or by groups of individuals. (Author)

  10. Implementation of a radiological safety management system in a hospital of Mexico City

    International Nuclear Information System (INIS)

    Martinez V, D.; Rivera M, T.; Velez D, V.

    2007-01-01

    Full text: The reflection of this work is based in some radiological accidents that its have happened in some hospital centers or of research. The over exposure of some people is due to the pursuit of the procedures, the lack of quality assurance of the equipment or the inappropriate actions of the technicians. In Mexico one has seen in several hospitals the lack of existence of a Quality Assurance Program to prevent the accidents, the execution of the same ones and those good practices and the lack of Safety Culture makes that the hospital radiological safety it is faulty. The objective of the present work is the implementation of a radiological safety management in a hospital of Mexico City. (Author)

  11. Occupational safety and health textbook for radiological personnel employed in structural material testing

    International Nuclear Information System (INIS)

    Abraham, J.

    1981-01-01

    The comprehensive textbook for X-ray and radiological testing personnel includes requirements and rules of occupational safety and health on the basis of Hungarian and international (mainly German) literature. In the chapter Fundamentals, X-ray and radioactive radiations, their measurements and biological effects, doses etc are described. In the chapter Occupational safety and health, the jobs representing radiation hazards are listed and safety regulations for them are reported. Finally, information for prevention and first aid is presented. Control questions are added to each part. The Appendix contains safety standards and regulations, information on legal aspects of safety and radiation protection as well as recommendations. (Sz.J.)

  12. Safety regulations concerning instrumentation and control systems for research reactors

    International Nuclear Information System (INIS)

    El-Shanshoury, A.I.

    2009-01-01

    A brief study on the safety and reliability issues related to instrumentation and control systems in nuclear reactor plants is performed. In response, technical and strategic issues are used to accomplish instrumentation and control systems safety. For technical issues there are ; systems aspects of digital I and C technology, software quality assurance, common-mode software, failure potential, safety and reliability assessment methods, and human factors and human machine interfaces. The strategic issues are the case-by-case licensing process and the adequacy of the technical infrastructure. The purpose of this work was to review the reliability of the safety systems related to these technical issues for research reactors

  13. Radiological Safety Assessment of Transporting Radioactive Wastes to the Gyeongju Disposal Facility in Korea

    Directory of Open Access Journals (Sweden)

    Jongtae Jeong

    2016-12-01

    Full Text Available A radiological safety assessment study was performed for the transportation of low level radioactive wastes which are temporarily stored in Korea Atomic Energy Research Institute (KAERI, Daejeon, Korea. We considered two kinds of wastes: (1 operation wastes generated from the routine operation of facilities; and (2 decommissioning wastes generated from the decommissioning of a research reactor in KAERI. The important part of the radiological safety assessment is related to the exposure dose assessment for the incident-free (normal transportation of wastes, i.e., the radiation exposure of transport personnel, radiation workers for loading and unloading of radioactive waste drums, and the general public. The effective doses were estimated based on the detailed information on the transportation plan and on the radiological characteristics of waste packages. We also estimated radiological risks and the effective doses for the general public resulting from accidents such as an impact and a fire caused by the impact during the transportation. According to the results, the effective doses for transport personnel, radiation workers, and the general public are far below the regulatory limits. Therefore, we can secure safety from the viewpoint of radiological safety for all situations during the transportation of radioactive wastes which have been stored temporarily in KAERI.

  14. Radiological safety assessment of transporting radioactive waste to the Gyeongju disposal facility in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Jong Tae; Baik, Min Hoon; Kang, Mun Ja; Ahn, Hong Joo; Hwang, Doo Seong; Hong, Dae Seok; Jeong, Yong Hwan; Kim, Kyung Su [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-12-15

    A radiological safety assessment study was performed for the transportation of low level radioactive wastes which are temporarily stored in Korea Atomic Energy Research Institute (KAERI), Daejeon, Korea. We considered two kinds of wastes: (1) operation wastes generated from the routine operation of facilities; and (2) decommissioning wastes generated from the decommissioning of a research reactor in KAERI. The important part of the radiological safety assessment is related to the exposure dose assessment for the incident-free (normal) transportation of wastes, i.e., the radiation exposure of transport personnel, radiation workers for loading and unloading of radioactive waste drums, and the general public. The effective doses were estimated based on the detailed information on the transportation plan and on the radiological characteristics of waste packages. We also estimated radiological risks and the effective doses for the general public resulting from accidents such as an impact and a fire caused by the impact during the transportation. According to the results, the effective doses for transport personnel, radiation workers, and the general public are far below the regulatory limits. Therefore, we can secure safety from the viewpoint of radiological safety for all situations during the transportation of radioactive wastes which have been stored temporarily in KAERI.

  15. New Automated System Available for Reporting Safety Concerns | Poster

    Science.gov (United States)

    A new system has been developed for reporting safety issues in the workplace. The Environment, Health, and Safety’s (EHS’) Safety Inspection and Issue Management System (SIIMS) is an online resource where any employee can report a problem or issue, said Siobhan Tierney, program manager at EHS.

  16. Safety Issues Concerning the Medical Use of Cannabis and Cannabinoids

    Directory of Open Access Journals (Sweden)

    Mark A Ware

    2005-01-01

    Full Text Available Safety issues are a major barrier to the use of cannabis and cannabinoid medications for clinical purposes. Information on the safety of herbal cannabis may be derived from studies of recreational cannabis use, but cannabis exposure and effects may differ widely between medical and recreational cannabis users. Standardized, quality-controlled cannabinoid products are available in Canada, and safety profiles of approved medications are available through the Canadian formulary. In the present article, the evidence behind major safety issues related to cannabis use is summarized, with the aim of promoting informed dialogue between physicians and patients in whom cannabinoid therapy is being considered. Caution is advised in interpreting these data, because clinical experience with cannabinoid use is in the early stages. There is a need for long-term safety monitoring of patients using cannabinoids for a wide variety of conditions, to further guide therapeutic decisions and public policy.

  17. Radiological safety design considerations for fusion research experiments

    International Nuclear Information System (INIS)

    Crase, K.W.; Singh, M.S.

    1979-01-01

    A wide variety of fusion research experiments are in the planning or construction stages. Two such experiments, the Nova Laser Fusion Facility and the Mirror Fusion Test Facility (MFTF), are currently under construction at Lawrence Livermore Laboratory. Although the plasma chamber vault for MFTF and the Nova target room will have thick concrete walls and roofs, the radiation safety problems are made complex by the numerous requirements for shield wall penetrations. This paper addresses radiation safety considerations for the MFTF and Nova experiments, and the need for integrated safety considerations and safety technology development during the planning stages of fusion experiments

  18. Radiological Protection Criteria for the Safety of LILW Repository in Croatia

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  19. Preliminary report in radiological safety for 1993 hydrology campaign

    International Nuclear Information System (INIS)

    Badano, A.; Suraez, R.; Dellepere, A.; Barreiro, M.

    1993-01-01

    The purpose of this report is to provide a study about industrial effluents influence on water pollution of Montevideo coastal beaches. The methods which have been considered are nuclear tracer techniques with a special attention in the radioprotection supervision. Three points are considered as evaluation: handling of radioactive tracers and safety, radiation protection workers, environment and public safety. tabs

  20. Progress report concerning safety research for nuclear reactor facilities

    International Nuclear Information System (INIS)

    1978-01-01

    Examination and evaluation of safety research results for nuclear reactor facilities have been performed, as more than a year has elapsed since the plan had been initiated in April, 1976, by the special sub-committee for the safety of nuclear reactor facilities. The research is carried out by being divided roughly into 7 items, and seems to be steadily proceeding, though it does not yet reach the target. The above 7 items include researches for (1) criticality accident, (2) loss of coolant accident, (3) safety for light water reactor fuel, (4) construction safety for reactor facilities, (5) reduction of release of radioactive material, (6) safety evaluation based on the probability theory for reactor facilities, and (7) aseismatic measures for reactor facilities. With discussions on the progress and the results of the research this time, research on the behaviour on fuel in abnormal transients including in-core and out-core experiments has been added to the third item, deleting the power-cooling mismatch experiment in Nuclear Safety Research Reactor of JAERI. Also it has been decided to add two research to the seventh item, namely measured data collection, classification and analysis, and probability assessment of failures due to an earthquake. For these 7 items, the report describes the concrete contents of research to be performed in fiscal years of 1977 and 1978, by discussing on most rational and suitable contents conceivable at present. (Wakatsuki, Y.)

  1. India's power program and its concern over environmental safety

    International Nuclear Information System (INIS)

    Prasad, G.E.; Mittra, J.

    2001-01-01

    India's need of electrical power is enormous and per capita consumption of power is to be increased at least by ten times to reach the level of world average. Thermal Power generation faces two fold problems. First, there is scarcity of good quality fuel and second, increasing environmental pollution. India's self reliant, three stage, 'closed-fuel-cycle' nuclear power program is promising better solution to the above problems. To ensure Radiation Protection and Safety of Radiation Sources, Indian Nuclear Power program emphasizes upon design and engineering safety by incorporating necessary safety features in the design, operational safety through structured training program and typically through software packages to handle rare unsafe events and regulation by complying safety directives. A health survey among the radiation workers indicates that there is no extra threat to the public from nuclear power program. Based on latest technology, as available in case of nuclear power option, it is quite possible to meet high energy requirement with least impact on the environment.. (authors)

  2. India's power programs and its concern over environmental safety

    International Nuclear Information System (INIS)

    Prasad, G.E.; Mittra, J.; Sarma, M.S.R.

    2000-01-01

    India's need for electrical power is enormous and per capita consumption of power is to be increased at least by 10 times to reach the level of the world average. Thermal power generation faces two-fold problems. First, there is scarcity of good quality fuel and second, increasing environmental pollution. India 's self reliant, . three stage, 'closed-fuel-cycle' nuclear power program is promising a better solution to the above problems. To ensure Radiation Protection and Safety of Radiation Sources, the Indian Nuclear Power program emphasizes upon design and engineering safety by incorporating' necessary safety features in the design, operational safety through a structured training program and typically through software packages to handle rare unsafe events and regulation by complying safety directives. A health survey among the radiation workers indicates that there is no extra threat to the public from the nuclear power program. Based on the latest technology, as available in case of the nuclear power option, it is quite possible to meet high energy requirements with least impact on the environment. (authors)

  3. Radiation safety concerns and diagnostic reference levels for computed tomography scanners in Tamil Nadu

    International Nuclear Information System (INIS)

    Livingstone, Roshan S.; Dinakaran, Paul M.

    2011-01-01

    Radiation safety in computed tomography (CT) scanners is of concern due its widespread use in the field of radiological imaging. This study intends to evaluate radiation doses imparted to patients undergoing thorax, abdomen and pelvic CT examinations and formulate regional diagnostic reference levels (DRL) in Tamil Nadu, South India. In-site CT dose measurement was performed in 127 CT scanners in Tamil Nadu for a period of 2 years as a part of the Atomic Energy Regulatory Board (AERB)-funded project. Out of the 127 CT scanners,13 were conventional; 53 single-slice helical scanners (SSHS); 44 multislice CT (MSCT) scanners; and 17 refurbished scanners. CT dose index (CTDI) was measured using a 32-cm polymethyl methacrylate (PMMA)-body phantom in each CT scanner. Dose length product (DLP) for different anatomical regions was generated using CTDI values. The regional DRLs for thorax, abdomen and pelvis examinations were 557, 521 and 294 mGy cm, respectively. The mean effective dose was estimated using the DLP values and was found to be 8.04, 6.69 and 4.79 mSv for thorax, abdomen and pelvic CT examinations, respectively. The establishment of DRLs in this study is the first step towards optimization of CT doses in the Indian context. (author)

  4. New U.K. safety legislation and its effects on the control of radiological hazards

    International Nuclear Information System (INIS)

    Bell, B.H.J.; Luxon, S.G.

    1977-01-01

    This paper explains the objectives of the Health and Safety at Work etc Act 1974 and refers in particular to its effects on the control of hazards at nuclear installations and, more widely, on the control of radiological hazards generally. It deals also with the changes resulting from the setting up of the Health and Safety Commission and its Executive under the new Act, and the effects of these changes on the work of the Nuclear Installations Inspectorate. (auth.) [fr

  5. Multi-criteria analysis for evaluating the radiological and ecological safety measures in radioactive waste management

    International Nuclear Information System (INIS)

    Sazykina, T.G.; Kryshev, I.I.

    2006-01-01

    A methodological approach is presented for multicriterial evaluating the effectiveness of radiation ecological safety measures during radioactive waste management. The approach is based on multicriterial analysis with consideration of radiological, ecological, social, economical consequences of various safety measures. The application of the multicriterial approach is demonstrated taking as an example of decision-making on the most effective actions for rehabilitation of a water subject, contaminated with radionuclides [ru

  6. Nuclear and radiological safety 1980-1994. International Atomic Energy Agency Publications

    International Nuclear Information System (INIS)

    1995-06-01

    This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Nuclear and Radiological Safety issued during the period 1980-1994. The following aspects are covered: Uranium mining and milling, Fuel fabrication and storage, Nuclear power plants, Research reactors, Radiation sources and accelerators, Transport of radioactive materials, Waste repositories, Radiation protection, Accident response, Radioactive waste management, Safety analysis, Quality management, Legal and governmental aspects

  7. Nuclear and radiological safety. 1986-1998. International Atomic Energy Agency publications

    International Nuclear Information System (INIS)

    1999-04-01

    This catalogue lists all sales publications of the IAEA dealing with nuclear and radiological safety issued from 1986 to 1998. Publications are sorted according to the following subjects: Uranium mining and milling; Fuel fabrication and storage; Nuclear power plants; Research reactors; Radiation sources and accelerators; Transport of radioactive material; Waste repositories; Radiation protection; Accident response; Radioactive waste management; Safety analysis; Quality management; Legal and governmental aspects

  8. Nuclear and radiological safety. 1990-2001. International Atomic Energy Agency publications

    International Nuclear Information System (INIS)

    2001-08-01

    This catalogue lists all sales publications of the IAEA dealing with nuclear and radiological safety issued from 1990 to 2001. Publications are sorted according to the following subjects: Uranium mining and milling. Fuel fabrication and storage. Nuclear power plants. Research reactors. Radiation sources and accelerators. Transport of radioactive material. Waste repositories. Radiation protection. Accident response. Radioactive waste management. Safety analysis. Quality management. Legal and governmental aspects

  9. Nuclear and radiological safety. 1990-2001. International Atomic Energy Agency publications

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-08-01

    This catalogue lists all sales publications of the IAEA dealing with nuclear and radiological safety issued from 1990 to 2001. Publications are sorted according to the following subjects: Uranium mining and milling. Fuel fabrication and storage. Nuclear power plants. Research reactors. Radiation sources and accelerators. Transport of radioactive material. Waste repositories. Radiation protection. Accident response. Radioactive waste management. Safety analysis. Quality management. Legal and governmental aspects.

  10. Safety concerns related to modular/prefabricated building construction.

    Science.gov (United States)

    Fard, Maryam Mirhadi; Terouhid, Seyyed Amin; Kibert, Charles J; Hakim, Hamed

    2017-03-01

    The US construction industry annually experiences a relatively high rate of fatalities and injuries; therefore, improving safety practices should be considered a top priority for this industry. Modular/prefabricated building construction is a construction strategy that involves manufacturing of the whole building or some of its components off-site. This research focuses on the safety performance of the modular/prefabricated building construction sector during both manufacturing and on-site processes. This safety evaluation can serve as the starting point for improving the safety performance of this sector. Research was conducted based on Occupational Safety and Health Administration investigated accidents. The study found 125 accidents related to modular/prefabricated building construction. The details of each accident were closely examined to identify the types of injury and underlying causes. Out of 125 accidents, there were 48 fatalities (38.4%), 63 hospitalized injuries (50.4%), and 14 non-hospitalized injuries (11.2%). It was found that, the most common type of injury in modular/prefabricated construction was 'fracture', and the most common cause of accidents was 'fall'. The most frequent cause of cause (underlying and root cause) was 'unstable structure'. In this research, the accidents were also examined in terms of corresponding location, occupation, equipment as well as activities during which the accidents occurred. For improving safety records of the modular/prefabricated construction sector, this study recommends that future research be conducted on stabilizing structures during their lifting, storing, and permanent installation, securing fall protection systems during on-site assembly of components while working from heights, and developing training programmes and standards focused on modular/prefabricated construction.

  11. Safety and proliferation concerns as constraints on nuclear power

    International Nuclear Information System (INIS)

    Gordon, L.

    1981-01-01

    Issues of safety and proliferation with respect to the nuclear option are discussed in this chapter. The basic premises underlying the author's analysis are: energy supply and use is a means to promote desired forms of development and not an end in itself; avoidance of nuclear mysticiam; avoidance of permanent discrimination; recognition of incommensurables; technological sophistication; and nuclear proliferation motivations apart from nuclear power development. A rational energy planner in a developing country will have to weigh carefully the interwoven factors of comparative costs and safety. Apart from cost considerations, the principal motivation for developing nuclear power is energy security

  12. The NKS programmes for Nordic cooperation on nuclear and radiological safety

    DEFF Research Database (Denmark)

    Andersson, Kasper Grann; Leino, Kaisu; Magnússon, Sigurður M.

    2013-01-01

    NKS is a platform for Nordic cooperation and competence maintenance in nuclear and radiological safety, including emergency preparedness. It is an informal forum serving as an umbrella for Nordic initiatives and interests. It runs joint activities of interest to financing organisations and other...

  13. Analysis of conditions to safety and radiological protection of Brazilian research particle accelerators facilities

    International Nuclear Information System (INIS)

    Lourenco, Manuel Jacinto Martins

    2010-01-01

    Eleven institutions of education and research in Brazil use particle accelerators, which fulfill different functions and activities. Currently, these institutions employ a total of fifteen accelerators. In this paper, the object of study is the radiological protection of occupationally exposed individuals, the general public and the radiation safety of particle accelerators. Research facilities with accelerators are classified in categories I and II according to the International Atomic Energy Agency or groups IX and X in accordance with the Brazilian National Commission of Nuclear Energy. Of the 15 accelerators in use for research in Brazil, four belong to category I or group X and eleven belong to category II or group IX. The methodology presented and developed in this work was made through the inspection and assessment of safety and radiological protection of thirteen particle accelerators facilities, and its main purpose was to promote safer use of this practice by following established guidelines for safety and radiological protection. The results presented in this work showed the need to create a program, in our country, for the control of safety and radiological protection of this ionizing radiation practice. (author)

  14. Radiological safety methodology in radioactive tracer applications for hydrodynamics and environmental studies

    International Nuclear Information System (INIS)

    Suarez, R.; Badano, A.; Dellepere, A.; Artucio, G.; Bertolotti, A.

    1995-01-01

    The use of radioactive tracer techniques as control sewage disposal contamination in Montevideo Estuarine and Carrasco beach has been studied for the Nuclear Technology National Direction. Hydrodynamic models simulation has been introduced as work methodology. As well as radiological safety and radioactive material applications in the environmental studies has been evaluated mainly in the conclusions and recommendations in this report. maps

  15. Arrangements for preparedness for a nuclear or radiological emergency. Safety guide (Spanish Edition); Disposiciones de preparacion para emergencias nucleares o radiologicas. Guia de seguridad

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-15

    Under the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency, one function of the IAEA is to collect and disseminate to States Parties and Member States information concerning methodologies, techniques and available results of research relating to response to such emergencies. The primary objectives of this Safety Guide, co-sponsored by FAO, OCHA, ILO, PAHO and WHO, are to provide guidance on preparedness and response for a nuclear or radiological emergency, to describe appropriate responses to a range of emergencies, and to provide background information on past experience, thus helping the user to better implement arrangements that address the underlying issues.

  16. Radiology

    International Nuclear Information System (INIS)

    Meyers, M.A.

    1989-01-01

    This paper reports on disease processes originating within the alimentary tract, may extend through the extraperitoneal spaces, and abnormalities primarily arising within other extraperitoneal sites may significantly affect the bowel. Symptoms and signs may be obscure, delayed, or nonspecific, and the area is generally not accessible to auscultation, palpation, or percussion. Radiologic evaluation thus plays a critical role

  17. Identifying Food Safety Concerns when Communication Barriers Exist

    Science.gov (United States)

    Neal, Jack A.; Dawson, Mary; Madera, Juan M.

    2011-01-01

    Abstract: Students must be prepared to lead a diverse workforce. The objective of this study was to establish a teaching method that helps students identify barriers to food safety while working in a simulated environment with communication barriers. This study employed a perspective taking exercise based upon the principles of social learning…

  18. The maintenance and the radiological safety in gamma irradiation facilities

    International Nuclear Information System (INIS)

    Torres C, G.

    1991-01-01

    Presently work the outstanding aspects of the operation and maintenance of the Industrial Irradiator JS 6500 are described that the ININ operates, in the Nuclear Center of Salazar, Estado de Mexico and its relationship with the radiological security for the occupationally exposed personnel. The signal devices are described and of control of the associate teams, as the system of cooling of the source; the plant of treatment of water of the pool and the system of extraction of ozone. On the other hand the procedures are mentioned for the sure operation and the application of the annual programs of maintenance, in their aspects of more interest, to reduce to the maximum the correction of faults, during the routine operation

  19. Assessment of Safety Parameters for Radiological Explosion Based on Gaussian Dispersion Model

    Energy Technology Data Exchange (ETDEWEB)

    Pandey, Alok [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Yu, Hyungjoon; Kim, Hong Suk [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2014-10-15

    These sources if used with explosive (called RDD - radiological dispersion device), can cause dispersion of radioactive material resulting in public exposure and contamination of the environment. Radiological explosion devices are not weapons for the mass destruction like atom bombs, but can cause the death of few persons and contamination of large areas. The reduction of the threat of radiological weapon attack by terrorist groups causing dispersion of radioactive material is one of the priority tasks of the IAEA Nuclear Safety and Security Program.Emergency preparedness is an essential part for reducing and mitigating radiological weapon threat. Preliminary assessment of dispersion study followed by radiological explosion and its quantitative effect will be helpful for the emergency preparedness team for an early response. The effect of the radiological dispersion depends on various factors like radioisotope, its activity, physical form, amount of explosive used and meteorological factors at the time of an explosion. This study aim to determine the area affected by the radiological explosion as pre assessment to provide feedback to emergency management teams for handling and mitigation the situation after an explosion. Most practical scenarios of radiological explosion are considered with conservative approach for the assessment of the area under a threat for emergency handling and management purpose. Radioisotopes under weak security controls can be used for a radiological explosion to create terror and socioeconomic threat for the public. Prior assessment of radiological threats is helpful for emergency management teams to take prompt decision about evacuation of the affected area and other emergency handling actions. Comparable activities of Co-60 source used in radiotherapy and Sr-90 source of disused and orphaned RTGs with two different quantities of TNT were used for the scenario development of radiological explosion. In the Basic Safety Standard (BSS

  20. Assessment of Safety Parameters for Radiological Explosion Based on Gaussian Dispersion Model

    International Nuclear Information System (INIS)

    Pandey, Alok; Yu, Hyungjoon; Kim, Hong Suk

    2014-01-01

    These sources if used with explosive (called RDD - radiological dispersion device), can cause dispersion of radioactive material resulting in public exposure and contamination of the environment. Radiological explosion devices are not weapons for the mass destruction like atom bombs, but can cause the death of few persons and contamination of large areas. The reduction of the threat of radiological weapon attack by terrorist groups causing dispersion of radioactive material is one of the priority tasks of the IAEA Nuclear Safety and Security Program.Emergency preparedness is an essential part for reducing and mitigating radiological weapon threat. Preliminary assessment of dispersion study followed by radiological explosion and its quantitative effect will be helpful for the emergency preparedness team for an early response. The effect of the radiological dispersion depends on various factors like radioisotope, its activity, physical form, amount of explosive used and meteorological factors at the time of an explosion. This study aim to determine the area affected by the radiological explosion as pre assessment to provide feedback to emergency management teams for handling and mitigation the situation after an explosion. Most practical scenarios of radiological explosion are considered with conservative approach for the assessment of the area under a threat for emergency handling and management purpose. Radioisotopes under weak security controls can be used for a radiological explosion to create terror and socioeconomic threat for the public. Prior assessment of radiological threats is helpful for emergency management teams to take prompt decision about evacuation of the affected area and other emergency handling actions. Comparable activities of Co-60 source used in radiotherapy and Sr-90 source of disused and orphaned RTGs with two different quantities of TNT were used for the scenario development of radiological explosion. In the Basic Safety Standard (BSS

  1. Medical social consequences of the safety problems of oncological radiology

    International Nuclear Information System (INIS)

    Pilipenko, M.Yi.; Stadnik, L.L.; Shal'opa, O.Yu.; Rigan, M.M.; Skalets'kij, Yu.M.

    2015-01-01

    Actuality of the problem of patient safety in oncoradiology in Ukraine is grounded. The results of international audit TLD (IAEA/WHO) quality during dosimetry procedures cobalt-telegamma vehicles in Ukraine are investigated, as well as legal and regulatory framework providing for the safety of radiotherapy care, scientific publications on patient safety. Methods: statistical, analytical, bibliographical, systematic approach. On the example of radiation therapy using the results of the international program of the IAEA/WHO TLD audit quality dosimetry calibration devices for remote gamma therapy in Ukraine from 1998 to 2014 the attempt to assess the extent of medical and social consequences of underestimating of medical errors in oncoradiology is made. The problems of regulatory nature of medical errors in oncoradiology are preliminary identified. The problem of medical errors in the treatment of cancer radiation methods in Ukraine is extremely important. Usually the problems of errors in oncoradiology are considered in organizational, technical, personnel and technical aspects, while medical and social consequences of problem are not covered. About 10 thousand of cancer patients in year may suffer from errors related only to dose calculation according to the optimistic variant, while the number of patients for the same period on the pessimistic case can reach 15 thousand. There are a number of legal character problems in oncoradiology related to patient safety that require clarification. The first priority for improving the safety of patients in oncoradiology is the recording and analysis of radiation therapy defects and their consequences

  2. Radiological tracking down of pulmonary tuberculosis in France; Investigation concerning 984 declared cases

    International Nuclear Information System (INIS)

    Hirsch, A.; Le Gales, C.; Lefaure, C.; Vallier, F.

    1987-01-01

    The purpose of this study is to: describe the populations with a pulmonary tuberculosis risk factor, determine the percentage of cases observed by systematic tracking down in a declared tubercular population, compare the populations effectively covered by radiological tracking down to the populations with risk a factor, and compare the medical characteristics (symptomatology and the bacteriological expectoration results) of pulmonary tuberculosis cases discovered by systematic tracking down to the characteristics of cases discovered during hospital consultations or by personal doctors

  3. Stake holder involvement in remediation programmes in a uranium mining area: changes of radiological concerns in the societal context

    International Nuclear Information System (INIS)

    Gatzweiler, R.; Hagen, M.; Leder, F.; Kraus, W.; Zimmermann, G.

    2002-01-01

    In 1990 after the political change in East Germany the public concerns on the radiological legacy of 45 years of uranium mining and milling in a densely populated area led to the launching of a huge remediation programme covering approximately 13 billion DM. Half of the remediation programme has been completed. Since the implementation of this programme the dominating attitude of the affected public has totally changed, from concerns for a great danger to health and mistrust of all planned activities to acceptance of the remediation programme and indifference about the radiological hazards. The success in getting adequate public acceptance in decision-making for remediation actions could be accounted for as more dependent on the societal, i.e. the scientific-technical, political and social-economic context of the radiological problems to be solved, and less due to whether stakeholders are completely and formally involved in the decision process. The scientific-technical context: Within the radiation protection system the missing national and international guidance on intervention and on protection against enhanced natural radiation provides a certain flexibility in decision-making but may negatively affect the credibility of expert judgements and increase uncertainties. Therefore it was important that appropriate parts of the former East German radiation protection legislation were kept in force and flexibility interpreted with regard to the remediation of an area contaminated by natural radionuclides. The political context: After the political change in East Germany suddenly a totalitarian and closed political system that did not provide any information on the radiological and other impacts of uranium mining and milling turned into an open and democratic society delivering full and open information. As part of the following unification process the German Government took over the full ownership of the Wismut company from the Soviet Union and thus the responsibility

  4. Accelerator driven systems from the radiological safety point of view

    Indian Academy of Sciences (India)

    Spallation reaction products like high energy gammas, neutrons, muons, pions and several radiotoxic nuclides including Po-210 complicate the situation. In the present paper, we discuss radiation safety measures like bulk shielding, containment of radiation leakage through ducts and penetration and induced activity in the ...

  5. Considerations concerning the reliability of reactor safety equipment

    International Nuclear Information System (INIS)

    Furet, J.; Guyot, Ch.

    1967-01-01

    A review is made of the circumstances which favor a good collection of maintenance data at the C.E.A. The large amount of data to be treated has made necessary the use of a computer for analyzing automatically the results collected. Here, only particular aspects of the reliability from the point of view of the electronics used for nuclear reactor control will be dealt with: sale and unsafe failures; probability of survival (in the case of reactor safety); availability. The general diagrams of the safety assemblies which have been drawn up for two types of reactor (power reactor and low power experimental reactor) are given. Results are presented of reliability analysis which could be applied to the use of functional modular elements, developed industrially in France. Improvement of this reliability appears to be fairly limited by an increase in the redundancy; on the other hand it is shown how it may be very markedly improved by the use of automatic tests with different frequencies for detecting unsafe failures rates of measurements for the sub-assemblies and for the logic sub-assemblies. Finally examples are given to show the incidence of the complexity and of the use of different technologies in reactor safety equipment on the reliability. (authors) [fr

  6. Preparedness and Response for a Nuclear or Radiological Emergency. General Safety Requirements (Chinese Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    This publication, jointly sponsored by the FAO, IAEA, ICAO, ILO, IMO, INTERPOL, OECD/NEA, PAHO, CTBTO, UNEP, OCHA, WHO and WMO, is the new edition establishing the requirements for preparedness and response for a nuclear or radiological emergency which takes into account the latest experience and developments in the area. It supersedes the previous edition of the Safety Requirements for emergency preparedness and response, Safety Standards Series No. GS-R-2, which was published in 2002. This publication establishes the requirements for ensuring an adequate level of preparedness and response for a nuclear or radiological emergency, irrespective of its cause. These Safety Requirements are intended to be used by governments, emergency response organizations, other authorities at the local, regional and national levels, operating organizations and the regulatory body as well as by relevant international organizations at the international level.

  7. Preparedness and Response for a Nuclear or Radiological Emergency. General Safety Requirements (Arabic Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    This publication, jointly sponsored by the FAO, IAEA, ICAO, ILO, IMO, INTERPOL, OECD/NEA, PAHO, CTBTO, UNEP, OCHA, WHO and WMO, is the new edition establishing the requirements for preparedness and response for a nuclear or radiological emergency which takes into account the latest experience and developments in the area. It supersedes the previous edition of the Safety Requirements for emergency preparedness and response, Safety Standards Series No. GS-R-2, which was published in 2002. This publication establishes the requirements for ensuring an adequate level of preparedness and response for a nuclear or radiological emergency, irrespective of its cause. These Safety Requirements are intended to be used by governments, emergency response organizations, other authorities at the local, regional and national levels, operating organizations and the regulatory body as well as by relevant international organizations at the international level.

  8. Preparedness and Response for a Nuclear or Radiological Emergency. General Safety Requirements (Russian Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    This publication, jointly sponsored by the FAO, IAEA, ICAO, ILO, IMO, INTERPOL, OECD/NEA, PAHO, CTBTO, UNEP, OCHA, WHO and WMO, is the new edition establishing the requirements for preparedness and response for a nuclear or radiological emergency which takes into account the latest experience and developments in the area. It supersedes the previous edition of the Safety Requirements for emergency preparedness and response, Safety Standards Series No. GS-R-2, which was published in 2002. This publication establishes the requirements for ensuring an adequate level of preparedness and response for a nuclear or radiological emergency, irrespective of its cause. These Safety Requirements are intended to be used by governments, emergency response organizations, other authorities at the local, regional and national levels, operating organizations and the regulatory body as well as by relevant international organizations at the international level.

  9. Computer program for storage of historical and routine safety data related to radiologically controlled facilities

    International Nuclear Information System (INIS)

    Marsh, D.A.; Hall, C.J.

    1984-01-01

    A method for tracking and quick retrieval of radiological status of radiation and industrial safety systems in an active or inactive facility has been developed. The system uses a mini computer, a graphics plotter, and mass storage devices. Software has been developed which allows input and storage of architectural details, radiological conditions such as exposure rates, current location of safety systems, and routine and historical information on exposure and contamination levels. A blue print size digitizer is used for input. The computer program retains facility floor plans in three dimensional arrays. The software accesses an eight pen color plotter for output. The plotter generates color plots of the floor plans and safety systems on 8 1/2 x 11 or 20 x 30 paper or on overhead transparencies for reports and presentations

  10. Development of a management system of radiological safety with application to hospitals

    International Nuclear Information System (INIS)

    Velazquez M, J.D.; Rivera M, T.; Santos R, J.R.

    2008-01-01

    The medicine is the area that more it has benefited with the implementation of the radiation. However, a great number of incidents/accidents they have happened in hospitals in recent years. The above-mentioned stands out the necessity to improve the acting of the radiological safety management systems in Hospitals. This work presents a Management System of Radiological Safety (SGSR). The SGSR has as fundamental objective the one of maintaining the radiological risks inside acceptable levels. The SGSR is generic and it can be applied in the nuclear medicine, radiodiagnostic, radiotherapy, and in other areas of the health sector where it is required to prevent accidents or incidents that affect the health or the well-being of the worker or user. Also it was diagnosed a Specialties Hospital of the Mexico City using some characteristics of the SGSR. The obtained results show that the SGSR can contribute significantly in the improvement of the quality of the service in the attention to the patients and in the radiological safety. (Author)

  11. Radiological safety assessment inside ancient Egyptian tombs in Saqqara.

    Science.gov (United States)

    El-Kameesy, S U; Salama, E; El-Fiki, S A; Ehab, M; Rühm, W

    2016-12-01

    Many archaeological sites in Egypt are unique worldwide, such as ancient tombs and pyramids, because they document fundamental developments in human civilization that took place several thousands of years ago. For this reason, these sites are visited by numerous visitors every year. The present work is devoted to provide a pre-operational radiological baseline needed to quantify occupational radiation exposure at the famous Saqqara region in Cairo, Egypt. A hyperpure Ge detector has been used in the γ-ray spectrometric analysis while the (222)Rn concentration was measured using a portable radon monitor RTM 1688-2, SARAD. The mean specific activities of (226)Ra, (232)Th and (40)K in the samples collected from the interior walls of the Saqqara tombs were determined and found to show average values of 16, 8.5 and 45 Bq kg(-1), respectively. The concentration of radon was measured inside the tombs Serapeum, South tomb and the Zoser Pyramid (fifth level) and an associated average working level of 0.83 WL was obtained. In order to avoid the health hazards associated with the exposure to radon during the long period of work inside these tombs, proposed solutions are introduced.

  12. Preclosure radiological safety analysis for the exploratory shaft facilities

    International Nuclear Information System (INIS)

    Ma, C.W.; Miller, D.D.; Jardine, L.J.

    1992-06-01

    This study assesses which structures, systems, and components of the exploratory shaft facility (ESF) are important to safety when the ESF is converted to become part of the operating waste repository. The assessment follows the methodology required by DOE Procedure AP-6.10Q. Failures of the converted ESF during the preclosure period have been evaluated, along with other underground accidents, to determine the potential offsite radiation doses and associated probabilities. The assessment indicates that failures of the ESF will not result in radiation doses greater than 0.5 rem at the nearest unrestricted area boundary. Furthermore, credible accidents in other underground facilities will not result in radiation doses larger than 0.5 rem, even if any structure, system, or component of the converted ESF fails at the same time. Therefore, no structure, system, or component of the converted ESF is important to safety

  13. Online Food Safety Information System for Nuclear or Radiological Emergencies

    International Nuclear Information System (INIS)

    Albinet, Franck; Adjigogov, Lazar; Dercon, Gerd

    2016-01-01

    Over the last year, the protocol with regards to data management and visualization requirements for food safety decision-making, developed under CRP D1.50.15 on R esponse to Nuclear Emergency Affecting Food and Agriculture , was further implemented. The development team moved away from early series of disconnected prototypes to a more advanced Information System integrating both data management and visualization components outlined in the agreed protocol

  14. Development of an auditable safety analysis in support of a radiological facility classification

    International Nuclear Information System (INIS)

    Kinney, M.D.; Young, B.

    1995-01-01

    In recent years, U.S. Department of Energy (DOE) facilities commonly have been classified as reactor, non-reactor nuclear, or nuclear facilities. Safety analysis documentation was prepared for these facilities, with few exceptions, using the requirements in either DOE Order 5481.1B, Safety Analysis and Review System; or DOE Order 5480.23, Nuclear Safety Analysis Reports. Traditionally, this has been accomplished by development of an extensive Safety Analysis Report (SAR), which identifies hazards, assesses risks of facility operation, describes and analyzes adequacy of measures taken to control hazards, and evaluates potential accidents and their associated risks. This process is complicated by analysis of secondary hazards and adequacy of backup (redundant) systems. The traditional SAR process is advantageous for DOE facilities with appreciable hazards or operational risks. SAR preparation for a low-risk facility or process can be cost-prohibitive and quite challenging because conventional safety analysis protocols may not readily be applied to a low-risk facility. The DOE Office of Environmental Restoration and Waste Management recognized this potential disadvantage and issued an EM limited technical standard, No. 5502-94, Hazard Baseline Documentation. This standard can be used for developing documentation for a facility classified as radiological, including preparation of an auditable (defensible) safety analysis. In support of the radiological facility classification process, the Uranium Mill Tailings Remedial Action (UMTRA) Project has developed an auditable safety analysis document based upon the postulation criteria and hazards analysis techniques defined in DOE Order 5480.23

  15. Software Reliability Issues Concerning Large and Safety Critical Software Systems

    Science.gov (United States)

    Kamel, Khaled; Brown, Barbara

    1996-01-01

    This research was undertaken to provide NASA with a survey of state-of-the-art techniques using in industrial and academia to provide safe, reliable, and maintainable software to drive large systems. Such systems must match the complexity and strict safety requirements of NASA's shuttle system. In particular, the Launch Processing System (LPS) is being considered for replacement. The LPS is responsible for monitoring and commanding the shuttle during test, repair, and launch phases. NASA built this system in the 1970's using mostly hardware techniques to provide for increased reliability, but it did so often using custom-built equipment, which has not been able to keep up with current technologies. This report surveys the major techniques used in industry and academia to ensure reliability in large and critical computer systems.

  16. Safety concerns and risk management of multiple sclerosis therapies

    DEFF Research Database (Denmark)

    Soelberg Sorensen, P.

    2017-01-01

    Currently, more than ten drugs have been approved for treatment of relapsing-remitting multiple sclerosis (MS). Newer treatments may be more effective, but have less favorable safety record. Interferon-β preparations and glatiramer acetate treatment require frequent subcutaneous or intramuscular...... disease activity can choose between dimethyl fumarate and teriflunomide or the “old injectable.” Patients with very active MS may choose a more effective drug as the initial treatment. In case of side effects on one drug, switch to another drug can be tried. Suboptimal effect of the first drug indicates...... escalation to a highly efficacious drug. A favorable benefit-risk balance can be maintained by appropriate patient selection and appropriate risk management on therapy. New treatments will within the coming 1-2 years change our current treatment algorithm for relapsing-remitting MS....

  17. Quality and safety based management of radiological and clinical equipment

    International Nuclear Information System (INIS)

    Arora, S.; Saini, P.S.

    2001-01-01

    TQM (Total quality management) is the 'buzz' acronym expected in almost every aspect of industrial manufacturing, product development and services solicited by the outside agencies. The correct management of the many technological resources in health institutions in terms of efficiency, effectiveness and safety is a necessity in view of the criteria on which modern medicine is based. Almost all activities -be they diagnostic, therapeutic and rehabilitative - carried out within a modern hospital are based on widespread application of equipment and technology, the efficiency of which can directly influence the quality of service offered to the patient

  18. Eminent radiological safety issues confronting the State of Hawaii

    International Nuclear Information System (INIS)

    Hashimoto, H.H.

    1984-01-01

    The State of Hawaii currently has over one hundred radioactive material use licenses. Nuclear Regulatory Commission licenses are primarily held by hospitals, industrial radiographers, and academic institutions. Complementing this, the State Department of Health regulates x-ray machines, radium, and has an emergency response role for accidents involving radioactive materials. The existing radiation protection program was created by piecemeal legislation. As a result, regulatory surveillance and actual control vary widely among the agencies. The State Legislature, in 1980, decided that action must be taken to set a clear state policy towards the use and disposal of nuclear materials. It was therefore recommended that the State of Hawaii Radiation Safety Advisory Committee be convened to assist the state in the evaluation of the issues. This report contains issue papers on radiation related topics addressed by the Radiation Safety Advisory Committe. Topics discussed include transportation, environmental monitoring, emergency response, and waste disposal. A survey of various radioactive sources identified medical applications as a category requiring stricter control. Selected chapters of the Hawaii Revised Statutes are also examined

  19. 'Speaking up' about patient safety concerns and unprofessional behaviour among residents: validation of two scales.

    Science.gov (United States)

    Martinez, William; Etchegaray, Jason M; Thomas, Eric J; Hickson, Gerald B; Lehmann, Lisa Soleymani; Schleyer, Anneliese M; Best, Jennifer A; Shelburne, Julia T; May, Natalie B; Bell, Sigall K

    2015-11-01

    To develop and test the psychometric properties of two new survey scales aiming to measure the extent to which the clinical environment supports speaking up about (a) patient safety concerns and (b) unprofessional behaviour. Residents from six large US academic medical centres completed an anonymous, electronic survey containing questions regarding safety culture and speaking up about safety and professionalism concerns. Confirmatory factor analysis supported two separate, one-factor speaking up climates (SUCs) among residents; one focused on patient safety concerns (SUC-Safe scale) and the other focused on unprofessional behaviour (SUC-Prof scale). Both scales had good internal consistency (Cronbach's α>0.70) and were unique from validated safety and teamwork climate measures (rspeaking up behaviour about safety and professionalism concerns (r=0.21, pspeaking up behaviour among residents. These two scales may fill an existing gap in residency and safety culture assessments by measuring the openness of communication about safety and professionalism concerns, two important aspects of safety culture that are under-represented in existing metrics. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

  20. Training Programs on Radiological Safety for users of Ionizing Radiations in Peru

    International Nuclear Information System (INIS)

    Medina Gironzini, E.

    2003-01-01

    In Peru, people who work with ionizing radiations must have an authorization (Individual License) as established in the Radiological Safety Regulations, which are the mandatory rules. The Technical Office of the National Authority (OTAN), which is the technical organ of the Peruvian Institute of Nuclear Energy (IPEN) in charge of controlling radiations within the country , grants the authorization after the candidate demonstrates that he/she knows the specific use of the technique using radiations, as well a s the aspects related to safety and radiological protection. Since it was created in 1972, the Superior Center of Nuclear Studies (VSEN) from IPEN has carried out different training courses so that people can work safety with ionizing radiations in medicine, industry and investigation. The analysis of the radiological safety programs carried out by CSEN during the last 30 years, which allowed the training of more than 2200 people in the country and, at the same time, made possible the securing of the respective Individual License, is presented in this work. The courses, nuclear medicine, radiotherapy, industrial radiography, nuclear gauges gamma irradiator, etc...) and are part of the continuous education program of CSEN. (Author)

  1. Radiological safety aspects of the operation of proton accelerators

    International Nuclear Information System (INIS)

    Thomas, R.H.; Stevenson, G.R.

    1988-01-01

    Particle accelerators are finding increased application in both the fundamental and applied sciences and in industry around the world. Positive ion accelerators are being applied in a host of fields, including radiation damage studies, induced activation and dating measurements, radiography, radiotherapy and fusion research. Because these devices can be potent sources of neutrons, it is important that information concerning their safe operation be widely available. This report is conceived as a source book providing authoritative guidance in radioprotection from an important category of radiation sources. It thus supplements other manuals of the IAEA related to the planning and implementation of radiation protection programmes. Refs, figs and tabs

  2. The public component of sea basins radiological safety

    International Nuclear Information System (INIS)

    Agutov, V.I.

    2003-01-01

    Full text: The sea is the key and essential element of the basin although the bigger share of the basin consists of the river ecosystems. The classical theory of sustainable basin development implies that the one of the main indicator of sustainable development is the river ecosystem biodiversity and especially the sturgeon kind of fish with long life cycle. The fish biodiversity and stocks of valuable fish were totally destroyed. One of the most serious causes for that was the inadequate water policy aimed at the construction of the river dam complexes and the construction of the huge water reservoirs. These water reservoirs were used for different purposes, but the main danger is coming from their usage as nuclear power plant cooling ponds. The wide public has received the opportunity to learn about the ecological danger of such objects. The modern Russian society doesn't fully believe to the results of monitoring by state agencies. In order to propel these activities the creation of non-governmental ecological organizations is needed within the all the key elements of river ecosystems. The information skeleton throughout the whole basin needed for successful and effective functioning of these organizations can be constructed only under the condition of having good and modern means of communication such as electronic ones (e-mail, Internet) and publishing of own newspapers and bulletins. Our regional non-governmental organization has created already such a network within the Don and accepting existing local organizations as members. The activities on the creation of the same networks have been already induced in the Volga and Ural rivers basins. Now the networks are more or less shaped and we start equipping the local NGOs with radiation detection devices of 'Inspector'class for measuring the beta and gamma radiation. Having the needed experts and specialists the independent networked organizations will be able not only to monitor the radiological situation

  3. Criticality safety concerns of uranium deposits in cascade equipment

    International Nuclear Information System (INIS)

    Plaster, M.J.

    1996-01-01

    The Paducah and Portsmouth Gaseous Diffusion Plants enrich uranium in the 235 U isotope by diffusing gaseous uranium hexafluoride (UF 6 ) through a porous barrier. The UF 6 gaseous diffusion cascade utilized several thousand open-quotes stagesclose quotes of barrier to produce highly enriched uranium (HEU). Historically, Portsmouth has enriched the Paducah Gaseous Diffusion Plant's product (typically 1.8 wt% 235 U) as well as natural enrichment feed stock up to 97 wt%. Due to the chemical reactivity of UF 6 , particularly with water, the formation of solid uranium deposits occur at a gaseous diffusion plant. Much of the equipment operates below atmospheric pressure, and deposits are formed when atmospheric air enters the cascade. Deposits may also be formed from UF 6 reactions with oil, UF 6 reactions with the metallic surfaces of equipment, and desublimation of UF 6 . The major deposits form as a result of moist air in leakage due to failure of compressor casing flanges, blow-off plates, seals, expansion joint convolutions, and instrument lines. This report describes criticality concerns and deposit disposition

  4. Legal requirements concerning the technical safety of nuclear installations

    International Nuclear Information System (INIS)

    Nolte, R.

    1984-01-01

    A short survey on nuclear risks and the nuclear safety conception is followed by the attempted clear definition of the semantic import of section 7, sub-section (2), No. 3 of the Atomic Energy Act. There are first beginnings of a concretization of the state-of-the-art in science and technology, i.e. all kinds of sub-legislative regulations such as the regulations of the Radiation Protection Ordinance which show scientific substance, guidelines issued by the Ministers, as well as codes for practice set up by various technical bodies and standardization associations, all of which are designed to compensate for this loop hole in the legislation. This study goes to examine to what extent administration and jurisdiction may take into account such codes of practice for the concretization of the legal requirements, and whether they are even binding on those executing the law. Only the respective regulations of the Radiation Protection Ordinance have a binding effect. All other guidelines and codes of practice are not legally binding per se, nor are they capable of being legally permitted by being referred to in terms of legal norms or by the self-commitment of those executing the law. Any attempt of using them, as the basis of a prime facie evidence or as an anticipating expertise, at least evidentarily for the concretization will have to fail owing to their evaluating character and to the fact that they may interfere in sociological conflict. An exception may be a case where a clear distinction can be made as to what extent the contents of such codes of practice is related to scientific and technological findings or to decisions based on evaluations. In such a case, a prima facil evicdence for the conformity of the regulation in question with the state-of-the-art in science and technology may be considered, which would easy the concretization of Art. 7 II Section 3 of the Atomic Law. (orig./HSCH) [de

  5. Radiological Operational Safety Verification for LILW Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ju Youl [FNC Technology, SNU, Seoul (Korea, Republic of); Jeong, Seung Young; Kim, Byung Soo [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2011-10-15

    The successful implementation of radioactive waste repository program depends on scientific and technical aspects of excellent safety strategy as well as on societal aspects such as stakeholder acceptance and confidence. Monitoring is considered as key element in serving both ends. It covers all stages of the disposal process from site selection to institutional monitoring after the repository is closed. Basically, the purpose of the monitoring of radioactive waste disposal facility is not to reveal any increase of radioactivity due to the repository, but to provide reassurance and confirmation that the repository is fulfilling its passive safety purpose as an initial disposal concept and that long-term safety driven by regulatory requirements is ensured throughout the entire lifetime of disposal facility including post-closure phase. Five principal objectives of monitoring of geological disposal are summarized by IAEA-TECDOC-1208 as follows 1) Supporting management decisions in a staged programme of repository development: 2) Strengthening understanding of system behavior: 3) Societal decision making: 4) Accumulating an environmental database: 5) Nuclear safeguards (if repository contains fissile material, i.e., spent fuel or plutonium-rich waste) Based on the results of detailed studies of the above objectives and related phenomena, 6 categories of potential monitoring parameters are determined as follows: (1) degradation of repository structures, (2) behavior of the waste package and its associated buffer material, (3) near field chemical interactions between introduced materials, groundwater and host rock, (4) chemical and physical changes to the surrounding geosphere, (5) provision of an environmental database, and (6) nuclear safeguards. Typical monitoring parameters include temperature (heat), water level, pore-water and moisture content (groundwater), rock pressure, fractures, displacement and deformation (stress), water quality chemistry and dissolved

  6. An analysis of electronic health record-related patient safety concerns

    Science.gov (United States)

    Meeks, Derek W; Smith, Michael W; Taylor, Lesley; Sittig, Dean F; Scott, Jean M; Singh, Hardeep

    2014-01-01

    Objective A recent Institute of Medicine report called for attention to safety issues related to electronic health records (EHRs). We analyzed EHR-related safety concerns reported within a large, integrated healthcare system. Methods The Informatics Patient Safety Office of the Veterans Health Administration (VA) maintains a non-punitive, voluntary reporting system to collect and investigate EHR-related safety concerns (ie, adverse events, potential events, and near misses). We analyzed completed investigations using an eight-dimension sociotechnical conceptual model that accounted for both technical and non-technical dimensions of safety. Using the framework analysis approach to qualitative data, we identified emergent and recurring safety concerns common to multiple reports. Results We extracted 100 consecutive, unique, closed investigations between August 2009 and May 2013 from 344 reported incidents. Seventy-four involved unsafe technology and 25 involved unsafe use of technology. A majority (70%) involved two or more model dimensions. Most often, non-technical dimensions such as workflow, policies, and personnel interacted in a complex fashion with technical dimensions such as software/hardware, content, and user interface to produce safety concerns. Most (94%) safety concerns related to either unmet data-display needs in the EHR (ie, displayed information available to the end user failed to reduce uncertainty or led to increased potential for patient harm), software upgrades or modifications, data transmission between components of the EHR, or ‘hidden dependencies’ within the EHR. Discussion EHR-related safety concerns involving both unsafe technology and unsafe use of technology persist long after ‘go-live’ and despite the sophisticated EHR infrastructure represented in our data source. Currently, few healthcare institutions have reporting and analysis capabilities similar to the VA. Conclusions Because EHR-related safety concerns have complex

  7. Course of radiological protection and safety in the medical diagnostic with X-rays

    International Nuclear Information System (INIS)

    Dominguez A, C.E.

    1997-01-01

    The obtention of images of human body to the medical diagnostic is one of the more old and generalized applications for X-ray. Therefore the design and performance of equipment and installations as well as the operation procedures must be oriented toward safety with the purpose to guarantee this radiological practice will bring a net positive benefit to the society. Given that in Mexico only exists the standardization related to source and equipment generators of ionizing radiation in the industrial area and medical therapy, but not so to the medical diagnostic area it is the purpose of this work to present those standards related with this application branch. Also it is presented the preparation of a manual for the course named Formation of teachers in radiological protection and safety in the X-ray medical diagnostic in 1997 which was imparted at ININ. (Author)

  8. Proceedings of the 4. National Congress of the Mexican Society of Radiological Safety C.A

    International Nuclear Information System (INIS)

    1991-01-01

    In these sessions it had the participation of personalities of diverse internationally grateful organizations, with exhibitions about the situation of the nuclear industry of power, the applications of the radiations and the radiological safety in the international context. Also its were presented works about Emergency plans in Nuclear facilities and plants, Nuclear medicine, Food processing, Thermal neutrons, Neutron dosimetry, Charged particles, Thermoluminescence, Industrial radiography, Radiation monitoring, all of them with the participation of specialists with international prestige. The 41 works that are presented in the technical sessions come from Spanish, Brazilian, Greek and Mexican grateful institutions. All they are a sample of the intense activity in investigation and development in the areas of the nuclear industry as of the radiological safety. This congress reveals the impulse that the nuclear community grants to the formation of human resources

  9. Preclosure radiological safety analysis for accident conditions of the potential Yucca Mountain Repository: Underground facilities

    International Nuclear Information System (INIS)

    Ma, C.W.; Sit, R.C.; Zavoshy, S.J.; Jardine, L.J.; Laub, T.W.

    1992-06-01

    This preliminary preclosure radiological safety analysis assesses the scenarios, probabilities, and potential radiological consequences associated with postulated accidents in the underground facility of the potential Yucca Mountain repository. The analysis follows a probabilistic-risk-assessment approach. Twenty-one event trees resulting in 129 accident scenarios are developed. Most of the scenarios have estimated annual probabilities ranging from 10 -11 /yr to 10 -5 /yr. The study identifies 33 scenarios that could result in offsite doses over 50 mrem and that have annual probabilities greater than 10 -9 /yr. The largest offsite dose is calculated to be 220 mrem, which is less than the 500 mrem value used to define items important to safety in 10 CFR 60. The study does not address an estimate of uncertainties, therefore conclusions or decisions made as a result of this report should be made with caution

  10. Independent Commission for Radiological Protection and Nuclear Safety CIPRSN: Balance, obligations and future prospects

    International Nuclear Information System (INIS)

    Gieb, M.; Meruje, M. M; Sena Lino, A.

    2010-01-01

    This article summarizes the historical context of the regulatory situation in Portugal that led to the creation of the technical team of the Independent Commission for Radiological Protection and Nuclear Safety (CIPRSN), recalls its early works, and highlights the current work of some members of the team on the self-assessment of the national regulatory system of radiological protection and nuclear safety. The result of this self-assessment allows a detailed analysis of current problems and makes it possible to outline the future work plan of the technical team. It is hoped that this work may contribute to an improvement of the system, especially in view of new international and European legal instruments which are currently under implementation. (author)

  11. Radiological safety aspects of the operation of electron linear accelerators

    International Nuclear Information System (INIS)

    Swanson, W.P.

    1979-01-01

    This manual is intended as a guide for the planning and implementation of radiation protection programmes for all types of electron linear accelerators. Material is provided for guidance in the planning and installation stages, as well as for the implementation of radiation protection for continuing operations. Because of their rapidly growing importance, the problems of installation and radiation safety of standard medical and industrial accelerators are discussed in separate sections. Special discussions are devoted to the radiation protection problems unique to electron accelerators: thick-target bremsstrahlung, the electromagnetic cascade, the estimation of secondary-radiation yields from thick targets, and instrumental corrections for accelerator duty factor. In addition, an extensive review of neutron production is given which includes new calculations of neutron production in various materials. A recalculation of activation in a variety of materials has been done for this manual, and specific gamma-ray constants have been recalculated for a number of nuclides to take into account the contribution of K X-rays. The subjects of air and water activation, as well as toxic gas production in air have been specially reviewed. Betatrons and electron microtrons operating at the same energy produce essentially the same kind of secondary radiation as electron linacs and the material given in this manual is directly applicable to them

  12. Radiology

    International Nuclear Information System (INIS)

    Lissner, J.

    1985-01-01

    Diagnostic radiology is still the foremost of all innovative medical disciplines. This has many advantages but also some handicaps, e.g. the siting problem of medical equipment whose clinical potential is not fully known. This applies in particular to nuclear spin tomography, where the Laender governments and the Scientific Council seen to agree that all universities should have the appropriate equipment as soon as possible in order to intensify interdisciplinary research. Formerly, in the case of computerized tomography, there was less readiness. As a result, the siting of CT equipment is less organically structured. A special handicap of innovative fields is the problem of training and advanced training. The Chamber of Medicine and the Association of Doctors Participating in the Health Insurance Plan have issued regulations aimed at a better standardisation in this field. (orig.) [de

  13. Radiological safety status and quality assurance audit of medical X-ray diagnostic installations in India.

    Science.gov (United States)

    Sonawane, A U; Singh, Meghraj; Sunil Kumar, J V K; Kulkarni, Arti; Shirva, V K; Pradhan, A S

    2010-10-01

    We conducted a radiological safety and quality assurance (QA) audit of 118 medical X-ray diagnostic machines installed in 45 major hospitals in India. The main objective of the audit was to verify compliance with the regulatory requirements stipulated by the national regulatory body. The audit mainly covered accuracy check of accelerating potential (kVp), linearity of tube current (mA station) and timer, congruence of radiation and optical field, and total filtration; in addition, we also reviewed medical X-ray diagnostic installations with reference to room layout of X-ray machines and conduct of radiological protection survey. A QA kit consisting of a kVp Test-O-Meter (ToM) (Model RAD/FLU-9001), dose Test-O-Meter (ToM) (Model 6001), ionization chamber-based radiation survey meter model Gun Monitor and other standard accessories were used for the required measurements. The important areas where there was noncompliance with the national safety code were: inaccuracy of kVp calibration (23%), lack of congruence of radiation and optical field (23%), nonlinearity of mA station (16%) and timer (9%), improper collimator/diaphragm (19.6%), faulty adjustor knob for alignment of field size (4%), nonavailability of warning light (red light) at the entrance of the X-ray room (29%), and use of mobile protective barriers without lead glass viewing window (14%). The present study on the radiological safety status of diagnostic X-ray installations may be a reasonably good representation of the situation in the country as a whole. The study contributes significantly to the improvement of radiological safety by the way of the steps already taken and by providing a vital feed back to the national regulatory body.

  14. Radiological safety status and quality assurance audit of medical X-ray diagnostic installations in India

    Directory of Open Access Journals (Sweden)

    Sonawane A

    2010-01-01

    Full Text Available We conducted a radiological safety and quality assurance (QA audit of 118 medical X-ray diagnostic machines installed in 45 major hospitals in India. The main objective of the audit was to verify compliance with the regulatory requirements stipulated by the national regulatory body. The audit mainly covered accuracy check of accelerating potential (kVp, linearity of tube current (mA station and timer, congruence of radiation and optical field, and total filtration; in addition, we also reviewed medical X-ray diagnostic installations with reference to room layout of X-ray machines and conduct of radiological protection survey. A QA kit consisting of a kVp Test-O-Meter (ToM (Model RAD/FLU-9001, dose Test-O-Meter (ToM (Model 6001, ionization chamber-based radiation survey meter model Gun Monitor and other standard accessories were used for the required measurements. The important areas where there was noncompliance with the national safety code were: inaccuracy of kVp calibration (23%, lack of congruence of radiation and optical field (23%, nonlinearity of mA station (16% and timer (9%, improper collimator/diaphragm (19.6%, faulty adjustor knob for alignment of field size (4%, nonavailability of warning light (red light at the entrance of the X-ray room (29%, and use of mobile protective barriers without lead glass viewing window (14%. The present study on the radiological safety status of diagnostic X-ray installations may be a reasonably good representation of the situation in the country as a whole. The study contributes significantly to the improvement of radiological safety by the way of the steps already taken and by providing a vital feed back to the national regulatory body.

  15. Nuclear and radiological safety nuclear power nuclear fuel cycle and waste management

    International Nuclear Information System (INIS)

    1997-05-01

    This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Nuclear and Radiological Safety, Nuclear Power and Nuclear Fuel Cycle and Waste Management and issued during the period of 1995-1996. Most publications are in English. Proceedings of conferences, symposia and panels of experts may contain some papers in languages other than English (Arabic, Chinese, French, Russian or Spanish), but all these papers have abstracts in English

  16. Radiological safety status and quality assurance audit of medical X-ray diagnostic installations in India

    International Nuclear Information System (INIS)

    Sonawane, A.U.; Singh, Meghraj; Sunil Kumar, J.V.K.; Kulkarni, Arti; Shirva, V.K.; Pradhan, A.S.

    2010-01-01

    We conducted a radiological safety and quality assurance (QA) audit of 118 medical X-ray diagnostic machines installed in 45 major hospitals in India. The main objective of the audit was to verify compliance with the regulatory requirements stipulated by the national regulatory body. The audit mainly covered accuracy check of accelerating potential (kVp), linearity of tube current (mA station) and timer, congruence of radiation and optical field, and total filtration; in addition, we also reviewed medical X-ray diagnostic installations with reference to room layout of X-ray machines and conduct of radiological protection survey. A QA kit consisting of a kVp Test-O-Meter (ToM) (Model RAD/FLU-9001), dose Test-O-Meter (ToM) (Model 6001), ionization chamber-based radiation survey meter model Gun Monitor and other standard accessories were used for the required measurements. The important areas where there was noncompliance with the national safety code were: inaccuracy of kVp calibration (23%), lack of congruence of radiation and optical field (23%), nonlinearity of mA station (16%) and timer (9%), improper collimator/diaphragm (19.6%), faulty adjustor knob for alignment of field size (4%), nonavailability of warning light (red light) at the entrance of the X-ray room (29%), and use of mobile protective barriers without lead glass viewing window (14%). The present study on the radiological safety status of diagnostic X-ray installations may be a reasonably good representation of the situation in the country as a whole. The study contributes significantly to the improvement of radiological safety by the way of the steps already taken and by providing a vital feed back to the national regulatory body. (author)

  17. Radiological safety programme for the health departments in Parana, Brazil

    International Nuclear Information System (INIS)

    Schmidt, M.F.S.; Tilly, J.G. Jr.

    1998-01-01

    As a result of Brazil's centralized administration in the past, various parts of the public service were somewhat inefficient. Another reason was the size of the country. To improve the situation in the health sector, it was decided to transfer administrative responsibility to the municipal authorities. Accordingly, the public health system is now defined under the appropriate legislation as the 'Unified Health System' (SUS), comprising federal, state and municipal levels. This system promotes decentralization of therapeutic or preventive services (including the Radiation Facility Health Inspectorate) and proposes any additional legislation required. In Parana the Radiation Facility Health Inspectorate has 3600 organizations listed, employing ionizing radiation in medicine, industry and research, which need to be regularly inspected for licensing and control. In 1994, 50% of the annual inspection target in the state was attained. The Radiation Safety Programme for the Health Departments in Parana directs these activities in this State. Its strategies are: (1) to establish implementation phases for activities planned for each area; (2) to take advantage of the SUS structure to introduce or expand operational services at the primary, secondary and tertiary levels with appropriate equipment. The tertiary level involves co-ordination of the Programme and complementary executive functions, as well as maintaining an information system with other related organizations. The other levels include licensing, control and emergency response. As the Programme develops, indicators will be established to help identify progress achieved and correct operating strategy where necessary. Thus, the services provided to the public will be enhanced in quality and the radiation doses reduced. In addition, in emergency situations, the time elapsing between the event and its notification to the authorities will be reduced, minimizing the consequences of any accidents. (author)

  18. Radiological safety assessment of gas mantle industries in India

    International Nuclear Information System (INIS)

    Sadagopan, G.; Venkataraman, G.

    1994-01-01

    Thorium, a radioactive element of actinide family was discovered by Berzelius in 1828 and named by him in honor of the Scandinavian God open-quote Thor close-quote. Following its discovery the earliest known use of thorium was in the making of gas mantles. The other use as an X-ray contrast medium open-quote Thorotrast close-quote has since long been discontinued, where as even today its use in gas mantles is continued. Gas lights have been used as a source of light since 1800's. In India, although electric bulbs have replaced most of the gas lights, even today in villages and in urban areas where there is no continuous power supply and in outdoor lightings gas lamps are used. The mantle which is used in these lamps is called the Welsbach mantle and is a netted hose that is impregnated with thorium nitrate and other metals. The function of a gas mantle is to produce a bright light during operation of the lighting device (gas or kerosene lamp) in which the mantle is placed. When placed in a lighting device and heated to 1300-1800 degree Celcius thorium in the mantle incandesces and gives off bright light. In India presently there are about 70 manufacturing units handling 150 metric tons of thorium nitrate annually. There are about four hundred persons involved in manufacturing 200 million mantles per year. Thorium is chosen because of its property of incadescence, however since it is radioactive, radiation safety of the workplace, handling personnel and safe environmental condition for members of public have to be maintained

  19. Modeling and Analysis on Radiological Safety Assessment of Low- and Intermediate Level Radioactive Waste Repository

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Youn Myoung; Jung, Jong Tae; Kang, Chul Hyung (and others)

    2008-04-15

    Modeling study and analysis for technical support for the safety and performance assessment of the low- and intermediate level (LILW) repository partially needed for radiological environmental impact reporting which is essential for the licenses for construction and operation of LILW has been fulfilled. Throughout this study such essential area for technical support for safety and performance assessment of the LILW repository and its licensing as gas generation and migration in and around the repository, risk analysis and environmental impact during transportation of LILW, biosphere modeling and assessment for the flux-to-dose conversion factors for human exposure as well as regional and global groundwater modeling and analysis has been carried out.

  20. Modeling and Analysis on Radiological Safety Assessment of Low- and Intermediate Level Radioactive Waste Repository

    International Nuclear Information System (INIS)

    Lee, Youn Myoung; Jung, Jong Tae; Kang, Chul Hyung

    2008-04-01

    Modeling study and analysis for technical support for the safety and performance assessment of the low- and intermediate level (LILW) repository partially needed for radiological environmental impact reporting which is essential for the licenses for construction and operation of LILW has been fulfilled. Throughout this study such essential area for technical support for safety and performance assessment of the LILW repository and its licensing as gas generation and migration in and around the repository, risk analysis and environmental impact during transportation of LILW, biosphere modeling and assessment for the flux-to-dose conversion factors for human exposure as well as regional and global groundwater modeling and analysis has been carried out

  1. List of reports from BMFT, CEA, EPRI, JSTA and USNRC concerning reactor safety research

    International Nuclear Information System (INIS)

    1982-02-01

    This list reviews reports from the Federal Republic of Germany, from France from Japan and from the United States of America concerning special problems in the field of reactor safety research. According to the cooperation in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  2. Mothers' Concerns for Personal Safety and Privacy While Breastfeeding: An Unexplored Phenomenon.

    Science.gov (United States)

    Rosen-Carole, Casey; Allen, Katherine; Fagnano, Maria; Dozier, Ann; Halterman, Jill

    2018-04-01

    Preliminary qualitative research in upstate NY shows new mothers are worried about safety while breastfeeding. Little is known regarding prevalence of these concerns and their effect on breastfeeding outcomes. (1) Determine frequency of breastfeeding safety and privacy concerns; (2) Explore their association with breastfeeding outcomes. Mothers were surveyed immediately and 1-month postpartum about breastfeeding goals; both surveys addressed privacy and safety concerns at home, work, and in public. Outcome data included breastfeeding intent, exclusivity, and duration. Breastfeeding/non-breastfeeding mothers were compared using Chi-square and multivariate analyses. A total of 279 women enrolled. Of these 82.8% initiated breastfeeding; at 1-month 72% provided any breast milk, and 44% were exclusively breastfeeding. About 99% felt safe breastfeeding at home; 25% reported privacy concerns; and 5% felt "vulnerable or unsafe" while breastfeeding. At 1-month, 49% agreed there was a safe place to breastfeed/express milk at work (20% unsure). Non-breastfeeding mothers expressed more safety concerns outside home/at work: 18% breastfeeding versus 28% non-breastfeeding outside home; 27% breastfeeding versus 40% non-breastfeeding at work. Nearly 54% who reported feeling vulnerable/unsafe with breastfeeding initiated breastfeeding, compared with 86% not reporting this concern (p = 0.008). Fewer women initiating breastfeeding reported vulnerability/safety (3% breastfeeding versus 14% non-breastfeeding, p = 0.008) or privacy (22% breastfeeding versus 40% non-breastfeeding, p = 0.19) concerns. Associations held after controlling for age, race, parity, insurance, geography, and marital-status. Significant associations between initiation, privacy, and safety concerns did not extend to duration or exclusivity. Many breastfeeding women reported safety and privacy concerns, especially outside the home and at work, which may influence breastfeeding initiation. Further study

  3. Recommendations concerning models and parameters best suited to breeder reactor environmental radiological assessments

    International Nuclear Information System (INIS)

    Miller, C.W.; Baes, C.F. III; Dunning, D.E. Jr.

    1980-05-01

    Recommendations are presented concerning the models and parameters best suited for assessing the impact of radionuclide releases to the environment by breeder reactor facilities. These recommendations are based on the model and parameter evaluations performed during this project to date. Seven different areas are covered in separate sections

  4. Summary of data concerning radiological contamination at well PM-2, Nevada Test Site, Nye County, Nevada

    International Nuclear Information System (INIS)

    Russell, G.M.; Locke, G.L.

    1997-01-01

    Analysis of water from well Pahute Mesa No. 2 (PM-2), on Pahute Mesa in the extreme northwestern part of the Nevada Test Site, indicated tritium concentrations above background levels in August 1993. A coordinated investigation of the tritium occurrence in well PM-2 was undertaken by the Hydrologic Resources Management Program of the US Department of Energy. Geologic and hydrologic properties of the hydrogeologic units were characterized using existing information. Soil around the well and water quality in the well were characterized during the investigation. The purpose of this report is to present existing information and results from a coordinated investigation of tritium occurrence. The objectives of the overall investigation include: (1) determination of the type and concentration of contamination; (2) identification of the source and mechanism of contamination; (3) estimation of the extent of radiological contamination; (4) initiation of appropriate monitoring of the contamination; and (5) reporting of investigation results. Compiled and tabulated data of the area are presented. The report also includes characterization of geology, soil, hydrology, and water quality data

  5. ORNL necessary and sufficient standards for environment, safety, and health. Final report of the Identification Team for other industrial, radiological, and non-radiological hazard facilities

    International Nuclear Information System (INIS)

    1998-07-01

    This Necessary and Sufficient (N and S) set of standards is for Other Industrial, Radiological, and Non-Radiological Hazard Facilities at Oak Ridge National Laboratory (ORNL). These facility classifications are based on a laboratory-wide approach to classify facilities by hazard category. An analysis of the hazards associated with the facilities at ORNL was conducted in 1993. To identify standards appropriate for these Other Industrial, Radiological, and Non-Radiological Hazard Facilities, the activities conducted in these facilities were assessed, and the hazards associated with the activities were identified. A preliminary hazards list was distributed to all ORNL organizations. The hazards identified in prior hazard analyses are contained in the list, and a category of other was provided in each general hazard area. A workshop to assist organizations in properly completing the list was held. Completed hazard screening lists were compiled for each ORNL division, and a master list was compiled for all Other Industrial, Radiological Hazard, and Non-Radiological facilities and activities. The master list was compared against the results of prior hazard analyses by research and development and environment, safety, and health personnel to ensure completeness. This list, which served as a basis for identifying applicable environment, safety, and health standards, appears in Appendix A

  6. ORNL necessary and sufficient standards for environment, safety, and health. Final report of the Identification Team for other industrial, radiological, and non-radiological hazard facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    This Necessary and Sufficient (N and S) set of standards is for Other Industrial, Radiological, and Non-Radiological Hazard Facilities at Oak Ridge National Laboratory (ORNL). These facility classifications are based on a laboratory-wide approach to classify facilities by hazard category. An analysis of the hazards associated with the facilities at ORNL was conducted in 1993. To identify standards appropriate for these Other Industrial, Radiological, and Non-Radiological Hazard Facilities, the activities conducted in these facilities were assessed, and the hazards associated with the activities were identified. A preliminary hazards list was distributed to all ORNL organizations. The hazards identified in prior hazard analyses are contained in the list, and a category of other was provided in each general hazard area. A workshop to assist organizations in properly completing the list was held. Completed hazard screening lists were compiled for each ORNL division, and a master list was compiled for all Other Industrial, Radiological Hazard, and Non-Radiological facilities and activities. The master list was compared against the results of prior hazard analyses by research and development and environment, safety, and health personnel to ensure completeness. This list, which served as a basis for identifying applicable environment, safety, and health standards, appears in Appendix A.

  7. Safety concerns and suggested design approaches to the HTGR Reformer process concept

    International Nuclear Information System (INIS)

    Green, R.C.

    1981-09-01

    This report is a safety review of the High Temperature Gas-Cooled Reactor Reformer Application Study prepared by Gas-Cooled Reactor Associates (GCRA) of La Jolla, California. The objective of this review was to identify safety concerns and suggests design approaches to minimize risk in the High Temperature Gas-Cooled Reactor Reformer (HTGR-R) process concept

  8. Safety concerns and suggested design approaches to the HTGR Reformer process concept

    Energy Technology Data Exchange (ETDEWEB)

    Green, R.C.

    1981-09-01

    This report is a safety review of the High Temperature Gas-Cooled Reactor Reformer Application Study prepared by Gas-Cooled Reactor Associates (GCRA) of La Jolla, California. The objective of this review was to identify safety concerns and suggests design approaches to minimize risk in the High Temperature Gas-Cooled Reactor Reformer (HTGR-R) process concept.

  9. The health and safety concerns of immigrant women workers in the Toronto sportswear industry.

    Science.gov (United States)

    Gannagé, C M

    1999-01-01

    Immigrant women's conditions of work have worsened with new government and managerial strategies to restructure the Canadian apparel industry. Changes in occupational health and safety legislation have both given and taken away tools that immigrant women workers could use to improve the quality of their working lives. The author outlines a methodology for eliciting the health and safety concerns of immigrant women workers.

  10. Summary of Tiger Team Assessment and Technical Safety Appraisal recurring concerns in the Maintenance Area

    International Nuclear Information System (INIS)

    1993-01-01

    Tiger Team Assessments and Technical Safety Appraisals (TSA) were reviewed and evaluated for concerns in the Maintenance Area (MA). Two hundred and thirty one (231) maintenance concerns were identified by the Tiger Team Assessments and TSA reports. These recurring concerns appear below. A summary of the Noteworthy Practices that were identified and a compilation of the maintenance concerns for each performance objective that were not considered as recurring are also included. Where the Tiger Team Assessment and TSA identified the operating contractor or facility by name, the concern has been modified to remove the name while retaining the intent of the comment

  11. Statement on safety requirements concerning the long-term operation of the Muehleberg nuclear power station

    International Nuclear Information System (INIS)

    2012-12-01

    This report published by the Swiss Federal Nuclear Safety Inspectorate ENSI investigates the safety requirements with respect to the long-term operation of the Muehleberg nuclear power station in Switzerland. Relevant international requirements and Swiss legal stipulations concerning the long-term operation of the power station are stated. The management of aging processes is looked at. The regular verification of the integrity of various plant components such as containments, piping, steam generation system, etc. is looked at in detail. The state-of-the-art concerning deterministic accident analyses and refitting technology are discussed, as are automated safety systems. The applicable laws, decrees and guidelines are listed in appendices

  12. 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.

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

    International Nuclear Information System (INIS)

    Gaona, Enrique; Enriquez, Jesus G. Franco

    2004-01-01

    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 thermoluminescent 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

  14. Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users’ Manual

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Bradley J Schrader

    2009-03-01

    The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

  15. Radiological Safety Analysis Computer (RSAC) Program Version 7.2 Users’ Manual

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Bradley J Schrader

    2010-10-01

    The Radiological Safety Analysis Computer (RSAC) Program Version 7.2 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

  16. Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users Manual

    International Nuclear Information System (INIS)

    Schrader, Bradley J.

    2009-01-01

    The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods

  17. Neutronic Analysis and Radiological Safety of RSG-GAS Reactor on 300 Grams Uranium Silicide Core

    International Nuclear Information System (INIS)

    Pande Made Udiyani; Lily Suparlina; Rokhmadi

    2007-01-01

    As starting of usage silicide U 250 g fuel element in the core of RSG-GAS and will be continued with usage of silicide U 300 g fuel element, hence done beforehand neutronic analyse and radiological safety of RSG-GAS. Calculation done by ORIGEN2.1 code to calculate source term, and also by PC-COSYMA code to calculate radiological safety of radioactive dispersion from RSG-GAS. Calculation of radioactive dispersion done at condition of reactor is postulated be happened an accident of LOCA causing one fuel element to melt. Neutronic analysis indicate that silicide U 250 g full core shall to be operated beforehand during 625 MWD before converted to silicide U 300 g core. During operation of transition core with mixture of silicide U 250 g and 300 g, all parameter fulfill criterion of safety Designed Balance core of silicide U 300 g will be reached at the time of fifth full core. Result of calculation indicate that through mixture core of silicide U 250 and 300 g proposed can form silicide U 300 g balance core of reactor RSG-GAS safely. Calculation of radiology safety by deterministic for silicide U 300 g balance core, and accident postulation which is equal to core of silicide U 250 g yield output in the form of radiation activity (radionuclide concentration in the air and deposition on the ground), radiation dose (collective and individual), radiation effect (short- and long-range), which accepted by society in each perceived sector. Result of calculation indicated that dose accepted by society is not pass permitted boundary for public society if happened accident. (author)

  18. Evaluation of the Radiological Safety of 192 Ir Apparatus for Industrial Gamma Radiography

    International Nuclear Information System (INIS)

    Aquino, J. O.; Silva, F. C. A. da; Ramalho, A. T.; Godoy, J. M. O.

    2004-01-01

    The majority of the 192Ir apparatus for industrial gamma radiography have been in usage in Brazil for more than 20 years. They are portable, and almost all operate according to category II. The main objective of this work was to assess the radiological safety of the 11 models of 192Ir apparatus most used in Brazil. The 11 models of 192Ir apparatus were studied with respect to compliance with the main safety requirements of three editions of international Standards ISO 3999. Six models were already manufactured incorporating the safety devices specified in the first edition of ISO 3999, issued in 1977. However, five models were not. The validity of their type B certificates for transport packages was also evaluated. (Author) 8 refs

  19. Spent fuel transport in Romania by road: An approach considering safety, risk and radiological consequences

    International Nuclear Information System (INIS)

    Vieru, G.

    2001-01-01

    The transport of high-level radioactive wastes, involving Type B packages, is a part of the safety of the Romanian waste management programme and the overall aim of this activity is to promote the safe transport of radioactive materials in Romania. The paper presents a safety case analysis of the transport of a single spent fuel CANDU bundle, using a Romanian built Type B package, from the CANDU type nuclear power plant Cernavoda to the INR Pitesti, in order to be examined within INR's hot-cells facilities. The safety assessment includes the following main aspects: (1) evaluation and analysis of available data on road traffic accidents; (2) estimation of the expected frequency for severe road accident scenarios resulting in potential radionuclide release; and (3) evaluation of the expected radiological consequences and accident risks of transport operations. (author)

  20. Psychometrics of the AAN Caregiver Driving Safety Questionnaire and contributors to caregiver concern about driving safety in older adults.

    Science.gov (United States)

    Carvalho, Janessa O; Springate, Beth; Bernier, Rachel A; Davis, Jennifer

    2018-03-01

    ABSTRACTBackground:The American Academy of Neurology (AAN) updated their practice parameters in the evaluation of driving risk in dementia and developed a Caregiver Driving Safety Questionnaire, detailed in their original manuscript (Iverson Gronseth, Reger, Classen, Dubinsky, & Rizzo, 2010). They described four factors associated with decreased driving ability in dementia patients: history of crashes or citations, informant-reported concerns, reduced mileage, and aggressive driving. An informant-reported AAN Caregiver Driving Safety Questionnaire was designed with these elements, and the current study was the first to explore the factor structure of this questionnaire. Additionally, we examined associations between these factors and cognitive and behavioral measures in patients with mild cognitive impairment or early Alzheimer's disease and their informants. Exploratory factor analysis revealed a four-component structure, consistent with the theory behind the AAN scale composition. These four factor scores also were significantly associated with performance on cognitive screening instruments and informant reported behavioral dysfunction. Regressions revealed that behavioral dysfunction predicted caregiver concerns about driving safety beyond objective patient cognitive dysfunction. In this first known quantitative exploration of the scale, our results support continued use of this scale in office driving safety assessments. Additionally, patient behavioral changes predicted caregiver concerns about driving safety over and above cognitive status, which suggests that caregivers may benefit from psychoeducation about cognitive factors that may negatively impact driving safety.

  1. Control development of radiation protection and safety on personnel eye lens of interventional radiology

    International Nuclear Information System (INIS)

    Titik Kartika; Ishak

    2013-01-01

    The review on radiation protection and safety to the lens of personnel especially in interventional radiology activities has been carried out. The use of radiation in interventional radiology installations provide significant exposure to the lens of the eye, especially personnel. The results of the latest various surveys and researches on the effects of low dose radiation to the eye lens indicates that the eye lens dose threshold is less than the preconceived values. Based on these facts, recently, ICRP and IAEA provides recommendations regarding the reduction of the value of the eye lens dose limit for personnel. BAPETEN have adopted the value of the eye lens dose limit in the development of new regulations on radiation protection and safety. However, the application of this provision has various challenges that BAPETEN provide 3 (three) years transitional period. These challenges include the problem of monitoring the eye lens dose, the eye lens protective equipment which is not adequate, the lack of understanding of personnel related to the risk of low radiation to the eye lens, as well as the proper procedures to mitigate those risks. BAPETEN as a regulatory agency is expected to provide solutions to the problems faced by the stake holders. Therefore, to answer the challenge, it is necessary to develop better monitoring of radiation protection and safety. (author)

  2. The radiological safety in the petroleum industry. The behavior toward the prevention

    International Nuclear Information System (INIS)

    Adrian T, W.

    2006-01-01

    Inside the mark of the regulatory control it takes a preponderant place the control of sealed and open radioactive sources, in oil applications. In this task, the handling of the radioactive sources, the demand of the use of written procedures and the training, they are only some examples, of all those that conform the regulatory control. Among these topics they stand out a series of aspects divided in three big groups: operative radiological safety in the base, in the transport and in the task properly said. Given the great quantity of aspects that should be kept in mind, as well as the integration of all the control processes should be included strongly, aspects of safety and quality culture, and to introduce improvements as for the prevention refers, to correct deviations and remoteness that can be produced, avoiding like this, situations of radiological risk, emphasizing aspects of perception of the risk, training in attitudes, the implementation of audits and verifications of the safety level of the installation and the pursuit and control of the tasks that involve the manipulation of radioactive material, which are described in this work. (Author)

  3. Regulatory overview report 2013 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    2014-06-01

    The Swiss Federal Nuclear Safety Inspectorate (ENSI) acting as the regulatory body of the Swiss Federation assesses and monitors nuclear facilities in Switzerland: these include five nuclear power plants, the interim storage facilities based at each plant, the Central Interim Storage Facility (ZWILAG) at Wuerenlingen together with the nuclear facilities at the Paul Scherrer Institute (PSI) and the two universities of Basel and Lausanne. Using a combination of inspections, regulatory meetings, examinations and analyses together with reports from the licensees of individual facilities, ENSI obtains the overview required concerning nuclear safety. It ensures that the facilities comply with regulations. Its regulatory responsibilities include the transport of radioactive materials from and to nuclear facilities and the preparations for a deep geological repository for nuclear waste. ENSI maintains its own emergency organisation, an integral part of the national emergency structure. It provides the public with information on particular events in nuclear facilities. This Surveillance Report describes operational experience, systems technology, radiological protection and management in all the nuclear facilities. Generic issues relevant to all facilities such as probabilistic safety analyses are described. In 2013, the five nuclear power plants in Switzerland (Beznau Units 1 and 2, Muehleberg, Goesgen and Leibstadt) were all operated safely and had complied with their approved operating conditions. The nuclear safety at all plants was rated as being good. 34 events were reported. During operation, no reactor scrams were recorded. On the INES scale, ranging from 0-7, ENSI rated all reportable events as Level 0. The ENSI safety evaluation reflects both reportable events and the results of the approximately 460 inspections conducted during 2013. ZWILAG consists of several storage halls, a conditioning plant and a plasma plant. At the end of 2013, the cask storage hall

  4. Radiological safety aspects in the fabrication of mixed oxide fuel elements

    International Nuclear Information System (INIS)

    Krishnamurthi, T.N.; Janardhanan, S.; Soman, S.D.

    1981-01-01

    The problems of radiological safety in the fabrication of (U, Pu)O 2 fuel assemblies for fast reactors utilising high exposure plutonium are discussed. Derived working limits for plutonium as a function of the burn-up of RAPS (Rajasthan Atomic Power Station) fuel, external gamma and neutron exposures from feed product batches, finished fuel pins and assemblies are presented. Shielding requirements for the various glove box operations are also indicated. In general, high exposure plutonium handling calls for remote fabrication and automation at various stages would play a key role in minimising exposures to personnel in a large production plant. (author)

  5. 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; 3. Congreso Regional sobre Seguridad Radiologica y Nuclear, Congreso Regional IRPA y 3. Congreso Peruano de Proteccion Radiologica. Libro de Resumenes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    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.

  6. Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety. Radiological protection in Latin America and the Caribbean. Vol. 1,2; Actas del 3. Congreso Regional sobre Seguridad Radiologica y Nuclear. Proteccion Radiologica en America Latina y el Caribe. Vol. 1,2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    Two volumes contain more than 183 complete papers presented during the Third Regional Meeting on Radiological Protection and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin american specialist 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.

  7. Preliminary report of radiological safety to hydrology 1993 campaign; Informe preliminar de seguridad radiologica para la campana de hidrologia 1993

    Energy Technology Data Exchange (ETDEWEB)

    Badano, A; Suarez Antola, R; Dellepere, A; Barreiro, M [MIEM, Direccion Nacional de Tecnologia Nuclear, Montevideo (Uruguay)

    1993-07-01

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

  8. LMFBR conceptual design study: an overview of environmental and safety concerns

    International Nuclear Information System (INIS)

    Brenchley, D.L.

    1981-06-01

    The US Department of Energy (DOE) initiated the Liquid Metal Fast Breeder (LMFBR) Conceptual Design Study (CDS) with the objective of maintaining a viable breeder option. The project is scheduled to be completed in FY-1981 but decisions regarding plant construction will be delayed until at least 1985. This report provides a review of the potential environmental and safety engineering concerns for the CDS and recommends specific action for the Environmental and Safety Engineering Division of DOE

  9. LMFBR conceptual design study: an overview of environmental and safety concerns

    Energy Technology Data Exchange (ETDEWEB)

    Brenchley, D.L.

    1981-06-01

    The US Department of Energy (DOE) initiated the Liquid Metal Fast Breeder (LMFBR) Conceptual Design Study (CDS) with the objective of maintaining a viable breeder option. The project is scheduled to be completed in FY-1981 but decisions regarding plant construction will be delayed until at least 1985. This report provides a review of the potential environmental and safety engineering concerns for the CDS and recommends specific action for the Environmental and Safety Engineering Division of DOE.

  10. Ordinance of 14 March 1983 concerning the Federal Commission for the Safety of Nuclear Installations

    International Nuclear Information System (INIS)

    1983-01-01

    The Frederal Council issued a new Ordinance concerning the Federal Commission for the Safety of Nuclear Installations. This Ordinance replaces an Ordinance of 13 June 1960 and takes into account the distribution of tasks decided several years ago between the Commission, which operates on a part-time basis, and the principal Division for the Safety of Nuclear Installations attached to the Federal Office of Energy. (NEA) [fr

  11. Summary of Tiger Team Assessment and Technical Safety Appraisal recurring concerns in the Operations Area

    International Nuclear Information System (INIS)

    1993-01-01

    Fourteen Tiger Team Assessment and eight Technical Safety Appraisal (TSA) final reports have been received and reviewed by the DOE Training Coordination Program during Fiscal Year 1992. These assessments and appraisals included both reactor and non-reactor nuclear facilities in their reports. The Tiger Team Assessments and TSA reports both used TSA performance objectives, and list ''concerns'' as a result of their findings. However, the TSA reports categorized concerns into the following functional areas: (1) Organization and Administration, (2) Radiation Protection, (3) Nuclear Criticality Safety, (4) Occupational Safety, (5) Engineering/Technical Support, (6) Emergency Preparedness, (7) Safety Assessments, (8) Quality Verification, (9) Fire Protection, (10) Environmental Protection, and (11) Energetic Materials Safety. Although these functional areas match most of the TSA performance objectives, not all of the TSA performance objectives are addressed. For example, the TSA reports did not include Training, Maintenance, and Operations as functional areas. Rather, they included concerns that related to these topics throughout the 11 functional areas identified above. For consistency, the Operations concerns that were identified in each of the TSA report functional areas have been included in this summary with the corresponding TSA performance objective

  12. Radiological impacts analysis with use of new endpoint as complementary safety indicators

    International Nuclear Information System (INIS)

    Peralta Vital, J.L.; Gil Castillo, R.; Fleitas Estevez, G.G.; Olivera Acosta, J.

    2015-01-01

    The paper shows the new safety indicators on risk assessment (safety assessment) to radioactive waste environmental management implementation (concentrations and fluxes of naturally occurring radioactive materials (NORM)). The endpoint obtained, allow the best analysis of the radiological impact associated to radioactive waste isolation system. The common safety indicators for safety assessment purpose, dose and risk, are very time dependent, increasing the uncertainties in the results for long term assessment. The complementary and new proposed endpoints are more stable and they are not affected by changes in the critical group, pathways, etc. The NORM values on facility site were obtained as result of national surveys, the natural concentrations of U, Ra, Th, K has been associated with the variation of the lithologies in 3 geographical areas of the Country (Occidental, Central and Oriental). The results obtained are related with the safety assessment topics and allowed to apply the new complementary safety indicators, by comparisons between the natural concentrations and fluxes on site and its calculated values for the conceptual repository design. In order to normalize the concentration results, the analysis was realized adopting the criteria of the Repository Equivalent Rock Volume (RERV). The preliminary comparison showed that the calculated concentrations and fluxes in the Cuban conceptual radioactive waste repository are not higher than the natural values in the host rock. According to the application of new safety indicators, the reference disposal facility does not increase the natural activity concentration and fluxes in the environment. In order to implement these new safety indicator it has been used the current 226 Ra inventory of the Repository and the 226 Ra as natural concentration on the site. (authors)

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  14. Use of digital dosemeters for supporting staff radiation safety in paediatric interventional radiology suites.

    Science.gov (United States)

    McNeil, Sarah M; Lai, Priscilla; Connolly, Bairbre L; Gordon, Christopher L

    2013-12-01

    Modern-day interventional radiology (IR) procedures impart a wide range of occupational radiation doses to team members. Unlike thermoluminescent badges, digital dosemeters provide real-time dose readings, making them ideal for identifying different components during IR procedures, which influence staff radiation safety. This study focused solely on paediatric IR (PIR) cases. Digital dosemeters measured the impact of imaging modality, shielding, patient and operator specific factors, on the radiation dose received during various simulated and real live PIR procedures. They recorded potential dose reductions of 10- to 100-fold to each staff member with appropriate use of shielding, choice of imaging method, staff position in the room and complex interplay of other factors. The digital dosemeters were well tolerated by staff. Results highlight some unique radiation safety challenges in PIR that arise from dose increases with magnification use and close proximity of staff to the X-ray beam.

  15. Use of digital dosemeters for supporting staff radiation safety in paediatric interventional radiology suites

    International Nuclear Information System (INIS)

    McNeil, S. M.; Lai, P.; Connolly, B. L.; Gordon, C. L.

    2013-01-01

    Modern-day interventional radiology (IR) procedures impart a wide range of occupational radiation doses to team members. Unlike thermoluminescent badges, digital dosemeters provide real-time dose readings, making them ideal for identifying different components during IR procedures, which influence staff radiation safety. This study focused solely on paediatric IR (PIR) cases. Digital dosemeters measured the impact of imaging modality, shielding, patient and operator specific factors, on the radiation dose received during various simulated and real live PIR procedures. They recorded potential dose reductions of 10-to 100-fold to each staff member with appropriate use of shielding, choice of imaging method, staff position in the room and complex interplay of other factors. The digital dosemeters were well tolerated by staff. Results highlight some unique radiation safety challenges in PIR that arise from dose increases with magnification use and close proximity of staff to the X-ray beam. (authors)

  16. About the necessity to update the Radiological safety and protection regulations of the National Institute of Nuclear Research (ININ)

    International Nuclear Information System (INIS)

    Alvarez R, J.T.

    1997-01-01

    It is argued the necessity to update the Radiological safety and Protection regulations (Review 3) of ININ, with the purpose that it implements the ICRU operative magnitudes system. Such a system used with radiological protection purposes. The objective of this system is to do an estimation of the effective equivalent dose H E and/or the Effective dose E, proposed in the ICRP 26 and ICRU 60 dose limits systems respectively. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-11-01

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

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

    International Nuclear Information System (INIS)

    2013-01-01

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

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

    International Nuclear Information System (INIS)

    2012-01-01

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

  20. Potential off-normal events and associated radiological source terms for the compact ignition tokamak: Fusion Safety Program

    International Nuclear Information System (INIS)

    Holland, D.F.; Lyon, R.E.

    1987-10-01

    The Compact Ignition Tokamak (CIT), the latest step in the United States program to develop the commercial application of fusion power, is designed as the first fusion device to achieve ignition conditions. It is to be constructed near Princeton, New Jersey on the site of the existing Tokamak Fusion Test Reactor (TFTR). To address the environmental impact and public safety concerns, a preliminary analysis was performed of potential off-normal radiological releases. Operational occurrences, natural phenomena, accidents with external origins, and accidents external to the PPPL site were considered as potential sources for off-normal events. Based on an initial screening, events were selected for preliminary analysis. Included in these events were tritium releases from the tritium delivery and recovery system, tritium releases from the torus, releases of activated nitrogen from the test cell or cryostat, seismic events, and shipping accidents. In each case, the design considerations related to the event were reviewed and the release scenarios discussed. Because of the complexity of some of the proposed safety systems, in some cases event trees were used to describe the accident scenarios. For each scenario, the probability was estimated as well as the release magnitude, isotope, chemical form, and release mode. 10 refs., 17 figs., 5 tabs

  1. Radiological consequence analysis. Report on the work package 10. Preliminary safety analysis for the site Gorleben; Radiologische Konsequenzanalyse. Bericht zum Arbeitspaket 10. Vorlaeufige Sicherheitsanalyse fuer den Standort Gorleben

    Energy Technology Data Exchange (ETDEWEB)

    Larue, Juergen; Baltes, Bruno; Fischer, Heidemarie; Frieling, Gerd; Kock, Ingo; Navarro, Martin; Seher, Holger

    2013-02-15

    Work package 10 of the preliminary safety analysis for the site Gorleben concerns the analysis of release scenarios and the radiological consequences. The report includes the description of the applied methodology, the concept for the mathematical description of scenarios, the variety of scenarios for the radiological consequence analysis with the definition of the reference scenario. The database for the calculation covers geology and hydrology, the final repository concept and the process of the final disposal system. The used models were the one-phase transport model MARINE and the two-phase transport model TOUGH2. The report summarizes the results including an evaluation of the realization of the demonstration concept with respect to solution transport, fluid transport, robustness of the modeling results and analogy discussion to other disposal variants (i.e. borehole disposal and storage of transport or storage casks).

  2. Factors to Consider When Balancing Campus Safety Concerns with Students' Civil Rights

    Science.gov (United States)

    Ingersoll, Julia S.

    2017-01-01

    On April 16, 2007, a student at Virginia Tech University, known to be mentally ill, went on a rampage shooting 49 people on campus before taking his own life. When it was over, 32 people were dead, and the concept of a safe campus was forever changed. The incident revealed the inherent conflicts between campus safety concerns and students' civil…

  3. Application of the threshold of toxicological concern (TTC) to the safety evaluation of cosmetic ingredients

    NARCIS (Netherlands)

    Kroes, R.; Renwick, A.G.; Feron, V.; Galli, C.L.; Gibney, M.; Greim, H.; Guy, R.H.; Lhuguenot, J.C.; Sandt, J.J.M. van de

    2007-01-01

    The threshold of toxicological concern (TTC) has been used for the safety assessment of packaging migrants and flavouring agents that occur in food. The approach compares the estimated oral intake with a TTC value derived from chronic oral toxicity data for structurally-related compounds.

  4. Topical points of community policy concerning nuclear safety relevant to the Internal Market

    International Nuclear Information System (INIS)

    Schroeder, M.

    1991-01-01

    Starting with the Internal Market concept, the lecture describes general and specific expectations directed to the nuclear community from a point of view of nuclear safety, and analyzes those aspects of nuclear safety, EC policy focuses on. There are the following chapters: 1. Selection of sites for nuclear installations, 2. installation and reactor safety, 3. radioactive waste management, 4. decommissioning of nuclear installations, 5. radioactive waste storage, 6. coping with nuclear accidents and other radiological emergency situations. Sophistication of public health and environmental protection within the framework of the EURATOM Treaty is seen in connection with interim and final storage as well as reprocessing of radioactive waste, and with the decommissioning of nuclear facilities on the basis of section 30 ff., and installation and reactor safety on the basis of section 203 EURATOM Treaty. Improving the protection of public health in particular is possible and necessary in order to make the EURATOM community into a proper nuclear community of law. (orig./HSCH) [de

  5. Reporter Concerns in 300 Mode-Related Incident Reports from NASA's Aviation Safety Reporting System

    Science.gov (United States)

    McGreevy, Michael W.

    1996-01-01

    A model has been developed which represents prominent reporter concerns expressed in the narratives of 300 mode-related incident reports from NASA's Aviation Safety Reporting System (ASRS). The model objectively quantifies the structure of concerns which persist across situations and reporters. These concerns are described and illustrated using verbatim sentences from the original narratives. Report accession numbers are included with each sentence so that concerns can be traced back to the original reports. The results also include an inventory of mode names mentioned in the narratives, and a comparison of individual and joint concerns. The method is based on a proximity-weighted co-occurrence metric and object-oriented complexity reduction.

  6. Proceedings of the 7th National Congress of the Mexican Society of Radiological Safety C.A

    International Nuclear Information System (INIS)

    1997-01-01

    The Mexican Society of Radiological Safety, celebrates on this time the 100 Anniversary of the radioactivity discovery, phenomenon coined by Marie Curie in 1898 and discover by Henry Beckerel in March 1896, when both were working with natural radioactive isotopes. Subsequently, on the new age of Physics, the use of radioactive isotopes was impulse by the invention of Cyclotron made by Dr. Ernest Orland Lawrence in the United States, which permits the manufacturing of tens of artificial radioactive isotopes which convert its in an indispensable tool in Medicine, Industry, Research, Agriculture and other disciplines, by its wide variety of applications, creating the radiological safety culture by the implicit risk in the use of these materials. From its creation in 1976, our society was removing to promote the radiological safety and two years each celebrates its National Congress removing specialists in this discipline and invite new generations to awake their interest by this useful field. (Author)

  7. Verification of implementation of the radiological safety standards through the regulatory inspections

    International Nuclear Information System (INIS)

    Perez Gonzalez, Francisco; Fornet Rodriguez, Ofelia M.

    2008-01-01

    Full text: As an element of the updating process of the legal framework on radiological safety in Cuba, a new rule was put into force; the Radiological Basic Safety Standards (RBSS) in January 2002. Five years after the application of these new safety requirements, it was considered appropriate to assess the effectiveness of its implementation. Therefore, in this work the authors analysed the outcomes of the regulatory inspections conducted in this period upon medical and industrial practices in a sample of facilities representative of those with the highest radiological risks in the territory under supervision of a Territorial Delegation of the Nuclear Regulatory Authority. For better understanding of this presentation, a summary explanation of the structure of the rule is given in its introduction. The work was to identify for each deficiency, or finding, or counter-measure; out of the relevant inspections; the corresponding requirement/Article of the RBSS that shows difficulties in implementation. For each installation an analysis is made with regard to the relevant articles difficult to implement. Finally, the appraisal is shown separately for the medical practice, and for the industrial practice, and also in general for the whole sample of installations under review. The study showed that the implementation of the Standards has been satisfactory and uniform in the practices under review. So far it seems that there have not been major difficulties with the implementation of the Titles; III On Intervention, IV Dose Limits, as well as with the Especial, Final, and Transitory Dispositions. On the other hand, it is shown there is a need for continued work only with regard to the implementation of the requirements in Section IV Verification of Safety and in Section V On the responsibilities with regard to occupational exposure in Chapter III Title I, and correspondingly in Chapter II Occupational Exposure in Title II. It is recommended to conduct this kind of

  8. Design concepts and safety concerns of the small and medium size reactors (SMR)

    International Nuclear Information System (INIS)

    Seul, Kwang Won; Lee, Jae Hun; Kim, Hho Jung

    1998-01-01

    The small and medium size reactors (SMR) and interface facilities such as desalination plant are expected to be located near the population area because of restrictions in transporting the plant products such as fresh water to long distance area. To protect the public around the plant facility from the possible release of radioactive materials, the design development of the SMR is focusing on an enhancement of the safety and reliability as well as the economics. In this study, the major safety concepts of the SMR designs significantly different from the current PWR designs are investigated and the safety concerns applicable to the integrated SMR design of Korea (called SMART), were identified. Those safety issues include the use of proven technology, application of strengthening defense in depth, event categorization and selection, simplification of emergency planning, determination of accident source terms and so on. The efforts to resolve the safety concerns in the design stage will provide an improvement of the safety of the SMART design

  9. Automated discovery of safety and efficacy concerns for joint & muscle pain relief treatments from online reviews.

    Science.gov (United States)

    Adams, David Z; Gruss, Richard; Abrahams, Alan S

    2017-04-01

    Product issues can cost companies millions in lawsuits and have devastating effects on a firm's sales, image and goodwill, especially in the era of social media. The ability for a system to detect the presence of safety and efficacy (S&E) concerns early on could not only protect consumers from injuries due to safety hazards, but could also mitigate financial damage to the manufacturer. Prior studies in the field of automated defect discovery have found industry-specific techniques appropriate to the automotive, consumer electronics, home appliance, and toy industries, but have not investigated pain relief medicines and medical devices. In this study, we focus specifically on automated discovery of S&E concerns in over-the-counter (OTC) joint and muscle pain relief remedies and devices. We select a dataset of over 32,000 records for three categories of Joint & Muscle Pain Relief treatments from Amazon's online product reviews, and train "smoke word" dictionaries which we use to score holdout reviews, for the presence of safety and efficacy issues. We also score using conventional sentiment analysis techniques. Compared to traditional sentiment analysis techniques, we found that smoke term dictionaries were better suited to detect product concerns from online consumer reviews, and significantly outperformed the sentiment analysis techniques in uncovering both efficacy and safety concerns, across all product subcategories. Our research can be applied to the healthcare and pharmaceutical industry in order to detect safety and efficacy concerns, reducing risks that consumers face using these products. These findings can be highly beneficial to improving quality assurance and management in joint and muscle pain relief. Copyright © 2017 Elsevier B.V. All rights reserved.

  10. ED accreditation update. Physicians, medical staff may report safety concerns without fear of disciplinary action.

    Science.gov (United States)

    2007-11-01

    Educating your staff about The Joint Commission's requirements for concerns about hospital safety and quality of care requires the ED manager to set a tone of openness and cooperation, while at the same time emphasizing your department's role in addressing such concerns: * The ED should be the first place that staff members communicate quality and safety concerns. It is only when a problem is not addressed that they should take the issue to hospital administration and, if necessary, The Joint Commission. * A single event should not trigger a report to The Joint Commission, unless it is unusually serious. Otherwise, only a series of events should trigger a report. * Reassure your staff that you care about what is reported and will act quickly on it. Educate your staff about the reporting forms, and follow up with random audits to ensure compliance.

  11. Automated system for the management of the radiological safety in a radiopharmaceutical and labelled compounds production center

    International Nuclear Information System (INIS)

    Amador B, Z.H.; Alvarez Builla de Sologuren, E.

    2006-01-01

    The establishment in the Center of Isotopes of Cuba of a managerial quality system in matter of radiological safety Y the accumulated operational experience, its constitute the foundations for the development of a system of management of the radiological safety organically structured, with the application of evaluative techniques of it management Y it integration in an automated system. The Visual Basic 5 platform for the programming of the 'SASR' system is used. The functions of each one of the 11 modules that integrate it are described. With this it can be carried out the registration of the data of the training Y the personnel's authorization, the checkup of the radioactive inventory of the installation, the annual upgrade of the registrations of the individual doses of those workers, the analysis of the state of the available equipment for magnitude to control, the radiological situation of the work positions, the public exposure by the gassy discharges, the experiences of the radiological events, the annual consolidation of the costs of the safety Y the evaluation of indicators Y of tendencies. A computer tool that facilitates the effective management of the radiological safety in a radioactive installation is obtained. (Author)

  12. Radiological safety in extraction of rare earths in India: regulatory control

    International Nuclear Information System (INIS)

    Sinha, S.; Bhattacharya, R.

    2011-01-01

    The term 'rare earths' refers to a group of f-block elements in the periodic table including those with atomic numbers 57 (Lanthanum) to 71 (Lutetium), as well as the transition metals Yttrium (39) and Scandium (21). Economically extractable concentrations of rare earths are found in minerals such as monazite, bastnaesite, cerites, xenotime etc. Of these, monazite forms the main source for rare earths in India, which along with other heavy minerals is found abundantly in the coastal beach sands. However, in addition to rare earths, monazite also contains 0.35% U 3 O 8 and 8-9% ThO 2 . Hence, extraction of rare earths involves chemical separation of the rare earths from thorium and uranium which are radioactive. The processing and extraction of rare earths from monazite therefore invariably results in occupational radiation exposure to the workers involved in these operations. In addition, in the process of removal of radioactivity from rare earths, radioactive solid waste gets generated which has 2 2 8Ra concentration in the range 2000-5000 Bq/g. Unregulated disposal of such high active waste would not only result in contamination of the soil but the radionuclides would eventually enter the food chain and lead to internal exposure of the general public. Therefore such facilities involved in recovery of rare earths from monazite attract the provisions of radiological safety regulations. Atomic Energy Regulatory Board of India has been enforcing the provisions of The Atomic Energy (Radiation Protection) Rules, 2004 and The Atomic Energy (Safe Disposal of Radioactive Waste) Rules, 1987 in these facilities. This paper shall discuss the associated radiological hazard involved in recovery of rare earths from monazite. It shall also highlight the regulatory requirements for controlling the occupational exposure of workers during design stage such as requirements on lay out of the building, ventilation, containment of radioactivity, etc and also the during operational

  13. Radiological Protection in Odontology: Analysis from the Faculty of Odontology at Rio de Janeiro concerning standards, licenses, controls and installations

    International Nuclear Information System (INIS)

    Padilha Filho, L.G.; Borgues, J.C.; Raymundo Junior, R.; Koch, H.A.

    1998-01-01

    This work shows the need and the importance training odontologists on radiological protection has. This is based on a proposal recently made by Technical Regulations: Trends for Radiological Protection in Medical and Odontological Radiodiagnosis from the Secretariat of Health Security from the Ministry of Health. These establish basic standards for radiation protection in medical and odontological areas

  14. Driving and dementia: Efficient approach to driving safety concerns in family practice.

    Science.gov (United States)

    Lee, Linda; Molnar, Frank

    2017-01-01

    To provide primary care physicians with an approach to driving safety concerns when older persons present with memory difficulties. The approach is based on an accredited memory clinic training program developed by the Centre for Family Medicine Primary Care Collaborative Memory Clinic. One of the most challenging aspects of dementia care is the assessment of driving safety. Drivers with dementia are at higher risk of motor vehicle collisions, yet many drivers with mild dementia might be safely able to continue driving for several years. Because safe driving is dependent on multiple cognitive and functional skills, clinicians should carefully consider many factors when determining if cognitive concerns affect driving safety. Specific findings on corroborated history and office-based cognitive testing might aid in the physician's decisions to refer for comprehensive on-road driving evaluation and whether to notify transportation authorities in accordance with provincial reporting requirements. Sensitive communication and a person-centred approach are essential. Primary care physicians must consider many factors when determining if cognitive concerns might affect driving safety in older drivers. Copyright© the College of Family Physicians of Canada.

  15. Social media in health--what are the safety concerns for health consumers?

    Science.gov (United States)

    Lau, Annie Y S; Gabarron, Elia; Fernandez-Luque, Luis; Armayones, Manuel

    Recent literature has discussed the unintended consequences of clinical information technologies (IT) on patient safety, yet there has been little discussion about the safety concerns in the area of consumer health IT. This paper presents a range of safety concerns for consumers in social media, with a case study on YouTube. We conducted a scan of abstracts on 'quality criteria' related to YouTube. Five areas regarding the safety of YouTube for consumers were identified: (a) harmful health material targeted at consumers (such as inappropriate marketing of tobacco or direct-to-consumer drug advertising); (b) public display of unhealthy behaviour (such as people displaying self-injury behaviours or hurting others); (c) tainted public health messages (i.e. the rise of negative voices against public health messages); (d) psychological impact from accessing inappropriate, offensive or biased social media content; and (e) using social media to distort policy and research funding agendas. The examples presented should contribute to a better understanding about how to promote a safe consumption and production of social media for consumers, and an evidence-based approach to designing social media interventions for health. The potential harm associated with the use of unsafe social media content on the Internet is a major concern. More empirical and theoretical studies are needed to examine how social media influences consumer health decisions, behaviours and outcomes, and devise ways to deter the dissemination of harmful influences in social media.

  16. Guideline for examination concerning the evaluation of safety in light water power reactor installations

    International Nuclear Information System (INIS)

    1978-01-01

    This guideline was drawn up as the guide for examination when the safety evaluation of nuclear reactors is carried out at the time of approving the installation of light water power reactors. Accordingly in case of the examination of safety, it must be confirmed that the contents of application are in conformity with this guideline. If they are in conformity, it is judged that the safety evaluation of the policy in the basic design of a reactor facility is adequate, and also that the evaluation concerning the separation from the public in surroundings is adequate as the condition of location of the reactor facility. This guideline is concerned with light water power reactors now in use, but the basic concept may be the reference for the examination of the other types of reactors. If such a case occurs that the safety evaluation does not conform to this guideline, it is not excluded when the appropriate reason is clarified. The purpose of safety evaluation, the scope to be evaluated, the selection of the events to be evaluated, the criteria for judgement, the matters taken into consideration at the time of analysis, the concrete events of abnormal transient change and accident in operation, and the concrete events of serious accident and hypothetic accident are stipulated. The explanation and two appendices are attached. (Kako, I.)

  17. Safety and effectiveness of moderate sedation for radiologic non-vascular intervention

    International Nuclear Information System (INIS)

    Kim, Tae-Hoon

    2006-01-01

    The purpose of this study was to prospectively characterize the safety and effectiveness of moderate sedation/analgesia for performing radiologic non-vascular abdominal intervention. During a 3-month period, a total of 63 adult patients with a mean age of 64 years (range:27-82) underwent moderate sedation for 72 radiologic non-vascular interventional procedures. A combination of fentanyl citrate and midazolam hydrochloride, based on the patient's body weight, was intravenously administered until the patient was drowsy and tranquil. The adverse events associated with this moderate sedation were assessed. The visual analog scale format was used to measure the subjective feelings of the patient's pre-pro- cedural anxiety and intraprocedural pain. The mean total dose per kilogram of body weight of fentanyl used in PTBD was 1.148 μg. The mean total dose per kilogram of body weight of midazolam was 0.035 mg in PTBD, PTGBD, AD, PCN, DJS, GS and FRA, 0.039 mg in TDC, and 0.043 mg in BS. A temporary reduction of systolic blood pressure to less than 80 mmHg was observed during 5 procedures (6.9%), whereas a temporary elevation of systolic blood pressure above 150 mmHg was observed during 10 procedures (13.8%). A reduction of arterial oxygen saturation to less than 90% was observed during 14 procedures (19.4%). None of the patients required pharmacologic reversal agents or cardiopulmonary resuscitation. The mean anxiety score recorded before all procedures was 5.2 (distressing). The mean pain score during the procedure, which was recorded after all procedures, was 2.9 (mild). Moderate sedation allows performance of safe and effective radiologic non-vascular intervention, and it is also easy for an interventional radiologist to use. The patients should be continuously monitored to check their vital signs and arterial oxygen saturation during the procedures

  18. Safety and effectiveness of moderate sedation for radiologic non-vascular intervention

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Tae-Hoon [Dankook University Hospital, Chungju (Korea, Republic of)

    2006-06-15

    The purpose of this study was to prospectively characterize the safety and effectiveness of moderate sedation/analgesia for performing radiologic non-vascular abdominal intervention. During a 3-month period, a total of 63 adult patients with a mean age of 64 years (range:27-82) underwent moderate sedation for 72 radiologic non-vascular interventional procedures. A combination of fentanyl citrate and midazolam hydrochloride, based on the patient's body weight, was intravenously administered until the patient was drowsy and tranquil. The adverse events associated with this moderate sedation were assessed. The visual analog scale format was used to measure the subjective feelings of the patient's pre-pro- cedural anxiety and intraprocedural pain. The mean total dose per kilogram of body weight of fentanyl used in PTBD was 1.148 {mu}g. The mean total dose per kilogram of body weight of midazolam was 0.035 mg in PTBD, PTGBD, AD, PCN, DJS, GS and FRA, 0.039 mg in TDC, and 0.043 mg in BS. A temporary reduction of systolic blood pressure to less than 80 mmHg was observed during 5 procedures (6.9%), whereas a temporary elevation of systolic blood pressure above 150 mmHg was observed during 10 procedures (13.8%). A reduction of arterial oxygen saturation to less than 90% was observed during 14 procedures (19.4%). None of the patients required pharmacologic reversal agents or cardiopulmonary resuscitation. The mean anxiety score recorded before all procedures was 5.2 (distressing). The mean pain score during the procedure, which was recorded after all procedures, was 2.9 (mild). Moderate sedation allows performance of safe and effective radiologic non-vascular intervention, and it is also easy for an interventional radiologist to use. The patients should be continuously monitored to check their vital signs and arterial oxygen saturation during the procedures.

  19. Recommendation concerning maximum permissible radioactivity in animal feeds in case of a nuclear accident or other type of radiological emergency

    International Nuclear Information System (INIS)

    1988-01-01

    The SSK in its advice to the Federal Ministry of the Environment, Nature Conservation and Reactor Safety recommends to abstain from determining maximum permissible values to be applied in such cases of emergency. If, however, official limits are to be given, the following should be considered: (1) Distinction has to be made between animal feeds not subject to restrictive application with regard to time, animal species, or food chain (meat, milk, eggs), and those animal feeds whose application is subject to restrictions defined. (2) Maximum permissible activity data for animal feeds for restricted use should be ten times the value determined for non-restricted feeds. As to consultations within the EC on supplemtary tables to EC Directive No. 3954/87, the SSK presented its proposals in tables, using transfer factors from the literature concerning assessment of maximum permissible chronic intake of Cs-137, I-131, Sr-90, Pu-239, Am-241 by productive livestock (bovine, goats, sheep, swine, poultry). (HP) [de

  20. Radiological and environmental safety in front-end fuel cycle facilities

    International Nuclear Information System (INIS)

    Puranik, V.D.

    2011-01-01

    The front end nuclear fuel cycle comprises of mining and processing of beach mineral sands along the southern coast of Kerala, Tamilnadu and Orissa, mining and processing of uranium ore in Singhbhum-East in Jharkhand and refining and fuel fabrication at Hyderabad. The Health Physics Units (HPUs)/Environmental Survey Laboratories (ESLs) set up at each site from inception of operation to carry out regular in-plant, personnel monitoring and environmental surveillance to ensure safe working conditions, evaluate radiation exposure of workers, ensure compliance with statutory norms, help in keeping the environmental releases well within the limits and advise appropriate control measures. This paper describes the occupational and environmental radiological safety measures associated with the operations of front end of nuclear fuel cycle. Radiological monitoring in these facilities is important to ensure safe working environment, protection of workers against exposure to radiation and comply with regulatory limits of exposure. The radiation exposure of workers in different units of the front end nuclear fuels cycle facilities operated by IREL, UCIL and NFC and environmental monitoring results are summarised in this paper

  1. Radiological safety evaluation for a Waste Transfer Facility at Savannah River Site

    International Nuclear Information System (INIS)

    Ades, M.J.

    1993-01-01

    This paper provides a review of the radiological safety evaluation performed for a Waste Transfer Facility (WTF) located at the Savannah River Site (SRS). This facility transfers liquid radioactive waste between various waste processing facilities and waste storage facilities. The WTF includes functional components such as the diversion box and the pump pits, waste transfer lines, and the outside yard service piping and electrical services. The WSRC methodology is used to evaluate the consequences of postulated accidents that result in the release of radioactive material. Such accidents include transfer line breaks, underground liquid pathway release, fire in pump tank cells and HEPA filters, accidents due to natural phenomena, and externally induced events. Chemical hazards accidents are not considered. The analysis results indicate that the calculated mean onsite and offsite radiological consequences are bounded by the corresponding WSRC dose limits for each accident considered. Moreover, the results show that the maximum onsite and offsite doses calculated for the WTF are lower than the maximum doses determined for the whole radioactive waste facility where the WTF is located

  2. Radiological safety programs in the petroleum and petrochemistry industry of Venezuela

    International Nuclear Information System (INIS)

    Romero M, C.

    1996-01-01

    A diagnosis carried out five years ago showed that in Petroleos de Venezuela (PDVSA) and its subsidiaries, exist about 530 radioactive sources. Also, about 1500 workers were also occupationally exposed, during operations such as industrial radiography and well logging. The same study determined the occurrence of some non-reported accidents and incidents with the overexposure of workers, specially contractors. Most of these problems were the result of the bad application of the radiological protection practices, and on the other hand, the disregarding of the governmental authorities in applying the regulatory standards. In order to solve this situation, PDVSA settled the safety guide for working with ionizing radiation, in which guidelines and technical advice are stablished to perform a safer work with radioactive elements. A radiological protection program was also organized in all the company operational areas. The paper includes the programs, practices and procedures implemented by PDVSA and its subsidiaries. Besides, the result of applying this comprehensive radiation protection program will be showed. (author). 1 ref

  3. Diagnosis of current state of the radiological safety system in the radiotherapy services of CCSS

    International Nuclear Information System (INIS)

    Calvo, Carolina Masis

    2013-01-01

    This article presents an analysis of evaluation reports issued by the Area of Control of Quality and Radiation Protection (ACCPR) of the Caja Costarricense de Seguro Social (CCSS, unit responsible for monitoring and auditing the System of Institutional Radiation Safety of the Costa Rica. In addition, were conducted a series of interviews to the radiotherapy services and authorities of the services to determine the internal perception on the performance and suitability of these programs.The results of this research have allowed identifying an improvement in the level of compliments of the current legislation on protection and radiation safety in these services through the previous five years; and how internally there is a positive perception of the officials, confirming the suitability of Radiological Protection and Quality Control Programs local. As a result of the analysis of the information gathered, we propose a series of actions and recommendations, that will allow improvements in the System of Institutional Radiation Safety, as the implementation of evaluations type QUATRO and the improvement of the local training programs

  4. Radiological and the other safety aspects in the operation of electron beam facility

    International Nuclear Information System (INIS)

    Loterina, Roel Alamares

    2003-01-01

    The radiological safety aspects of the operation of an electron beam facility in general and the 3 MeV ALURTRON electron beam facility of the Malaysian Institute of Nuclear Technology Research (MINT) in particular were reviewed and evaluated. Evaluation was made based on existing records as well as actual monitoring around facility. Area monitoring results using TLDs are within permissible levels. The maximum reading of 7.29 mSv measured in year 2000 is very low as compared to the annual dose limit of 50 mSv/year. In general, the shielding for the installation is adequate and no significant radiation leakage were detected based on radiation survey results. However, measured radiation levels with a maximum of 1.9 mSv/h at the sampling ports easily exceed the limit of 25μSv/h. The facility is equipped with safety features, such as interlocked system, adequate shielding, engineered safety design of irradiation and accelerator rooms, and accessories such as conveyor system and product handling system. Warning lights and signals are adequately installed around the facility. Other identified hazards that may affect the operator, workers, and personnel were also evaluated based on previous records of monitoring. The ozone concentration levels with a maximum reading of 0.05 ppm measured in the environment of the facility are within the threshold limit value of 0.1 ppm. The measured noise levels at all locations around facility are generally below the maximum permissible level of 80dB. The ALURTRON has achieved a minimum safety requirement to warrant its full operation without relying on administrative controls and procedures to ensure safety in operation. (Auth.)

  5. Radiological, health, and safety, and occurrence reporting system audit report, Rifle, Colorado

    International Nuclear Information System (INIS)

    1993-11-01

    This paper describes an audit dated September 14--16, 1993. The performance of the contractors and subcontractors responsible for remedial action work at the former uranium ore processing site at Rifle, Colorado, and the uranium tailings disposal cell at Estes Gulch (Colorado) was reviewed during an audit conducted September 14 through 16, 1993. MK-Ferguson Company (MK-F) is the Remedial Action Contractor (RAC) responsible for engineering and construction management of the Rifle operations. The audit focused on radiological issues, occupational safety and health (OS ampersand H) issues, and the Occurrence Reporting and Processing System (ORPS). The close-out meeting was held on September 16, 1993, which was attended by representatives of MK-F, the US Department of Energy (DOE), and the Technical Assistance Contractor (TAC)

  6. Fundamental features and main problems of nuclear power and radiological safety law

    International Nuclear Information System (INIS)

    Moser, B.

    1981-01-01

    This report deals on a general basis with the legal spheres affected by the utilisation of nuclear energy and protection from ionising radiation. Following a historical survey of the development both in the field of national legisation in Austria and internationally, the five principal legal spheres are discussed in detail. These are administrative law, liability and insurance law, criminal law, constitutional law and international law. In the foreground of discussion is administrative law, which is mainly of a preventive nature. This also comprises radiological safety law. Next in importance is liability and insurance law, which, in contrast to the former, aims at compensation for damage. Criminal law is also intended to have a preventive effect. Finally, the author discusses the peaceful use of nuclear energy in relation to the constitutional law and the international law in force. (Auth.)

  7. Radiological and environmental consequences. Final report of the Nordic Nuclear Safety Research project BOK-2

    International Nuclear Information System (INIS)

    Palsson, S.E.

    2002-11-01

    Final report of the Nordic Nuclear Safety Research project BOK-2, Radiological and Environmental Consequences. The project was carried out 1998-2001 with participants from all the Nordic countries. Representatives from the Baltic States were also invited to some of the meetings and seminars. The project consisted of work on terrestrial and marine radioecology and had a broad scope in order to enable participation of research groups with various fields of interest. This report focuses on the project itself and gives a general summary of the studies undertaken. A separate technical report summarises the work done by each research group and gives references to papers published in scientific journals. The topics in BOK-2 included improving assessment of old and recent fallout, use of radionuclides as tracers in Nordic marine areas, improving assessment of internal doses and use of mass spectrometry in radioecology. (au)

  8. Operation Aqueduct: Onsite radiological safety report for announced nuclear tests, October 1989--September 1990

    International Nuclear Information System (INIS)

    Hernandez, G.M.; Jacklin, A.K.

    1992-01-01

    Aqueduct was the name assigned to the series of underground nuclear weapons tests conducted at the Nevada Test Site (NTS) from October 1, 1989, through September 30, 1990. This report includes those experiments publicly announced. Remote radiation measurements were taken during and after each nuclear event by a telemetry system. Reynolds Electrical ampersand Engineering Co., Inc. (REECO) Health Protection Department (HPD) Radiation Protection Technicians (RPTS) with portable radiation detection instruments surveyed reentry routes into ground zeros (GZ) before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene (IH) coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

  9. Operation Grenadier. Onsite radiological safety report for announced nuclear tests, October 1984-September 1985

    International Nuclear Information System (INIS)

    Mullen, O.W.; Eubank, B.F.

    1986-09-01

    Grenadier was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1984 through September 30, 1985. This report includes those experiments publicly announced. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeros before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

  10. Operation fusileer onsite radiological safety report for announced nuclear tests, October 1983-September 1984

    International Nuclear Information System (INIS)

    Mullen, O.W.; Eubank, B.F.

    1985-08-01

    Fusileer was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1983 through September 30, 1984. This report is limited to announced nuclear tests. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeros before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

  11. Evaluation of radiological safety assessment of a repository in a clay rock formation

    International Nuclear Information System (INIS)

    1999-01-01

    This report presents a comprehensive description of the post-closure radiological safety assessment of a repository for the spent fuel arisings resulting from the Spanish nuclear program excavated in a clay host rock formation. In this report three scenarios have been analysed in detail. The first scenario represents the normal in detail. The first scenario represents the normal evolution of the repository (Reference Scenario); and includes a set of variants to investigate the relative importance of the various repository components and examine the sensitivity of the performance to parameters variations. Two altered scenarios have also been considered: deep well construction and poor sealing of the repository. This document contains a detailed description of the repository system, the methodology adopted for the scenarios generation, the process modelling approach and the results of the consequences analysis. (Author)

  12. Regulation for the radiological safety in the design and operation of industrial Gamma irradiators in Egypt

    International Nuclear Information System (INIS)

    Abdel-Ghani, A.H.; Hussein, A.Z.

    2000-01-01

    Large gamma irradiators present a high potential irradiation hazard since the amount of radioactivity is of the order of P Bq and a very high dose rate are produced during irradiation. Nevertheless, individuals may accidentally receive a lethal dose within minutes or seconds, due to failure of radiation control and safety systems. The competent authority (NCNSRC) is concerned with the impact of all radiation activities on workers as well as public health and safety. Radiation control of such large irradiation facilities can be achieved by means of strict regulatory procedures during construction, licensing, operation, inspection, maintenance and decommissioning

  13. List of reports concerning reactor safety research from BMFT, CEA, EPRI, JSTA, and USNRC

    International Nuclear Information System (INIS)

    1982-12-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technologie Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these Reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  14. Specialized consulting in radiological safety to the south central hospital of high specialty, PEMEX. VI. December of 2001

    International Nuclear Information System (INIS)

    Angeles C, A.; Vizuet G, J.; Benitez S, J.A.; Garcia A, J.; Rodriguez A, F.

    2002-01-01

    It is a report of a specialized consulting in radiological safety that to be carried the ININ to PEMEX for the South Central Hospital of High Specialty, to maintain the sanitary license for the use of X-ray equipment of medical diagnostic, and guarantee these services with a program of quality assurance. To give fulfilment to that requests it is programmed a technical assistance monthly, with reports of results during the development of the service. In this document it is carried a report of the advances and results in the month of december of the 2001, where the following documents are analyzed: Manual of radiological safety, program of quality assurance, operation procedures, procedure of maintenance team, procedure of medical radiological control of the specialized personnel; also are annotate the obtained results and their observations. (Author)

  15. Specialized consulting in radiological safety to the North Central Hospital of high specialty, PEMEX. V. November of 2001

    International Nuclear Information System (INIS)

    Angeles C, A.; Vizuet G, J.; Benitez S, J. A.; Garcia A, J.; Rodriguez A, F.

    2002-01-01

    It is a report of a specialized consulting in radiological safety that to be carried the ININ to PEMEX for the North Central Hospital of High Specialty, to maintain the sanitary license for the use of X ray equipment of medical diagnostic, and guarantee these services with a program of quality assurance. To give fulfilment to that requests it is programmed a technical assistance monthly, with reports of results during the development of the service. In this document it is carried a report of the advances and results in the month of November of the 2001, where the following documents are analyzed: Manual of radiological safety, program of quality assurance, operation procedures, procedure of maintenance team, procedure of medical radiological control of the specialized personnel; also are annotate the obtained results and their observations. (Author)

  16. Surveys of research projects concerning nuclear facility safety, financed by the Federal Ministry of the Interior

    International Nuclear Information System (INIS)

    1986-05-01

    Each progress report is a collection of individual reports, categorized by subject matter. They are a documentation of the contractor's progress, rendered by themselves on standardized forms, published, for the sake of general information on progress made in investigations concerning reactor safety, by the project attendance department of the GRS. The individual reports have serial numbers. Each report includes particulars of the objective, work carried out, results obtained and plans for project continuation. (orig./HP) [de

  17. Long-term criticality safety concerns associated with surplus fissile material disposition

    International Nuclear Information System (INIS)

    Choi, J.S.

    1995-01-01

    A substantial inventory of surplus fissile material would result from ongoing and planned dismantlement of US and Russian nuclear weapons. This surplus fissile material could be dispositioned by irradiation in nuclear reactors, and the resulting spent MOx fuel would be similar in radiation characteristics to regular LWR spent UO2 fuel. The surplus fissile material could also be immobilized into high-level waste forms, such as borosilicate glass, synroc, or metal-alloy matrix. The MOx spent fuel, or the immobilized waste forms, could then be directly disposed of in a geologic repository. Long-term criticality safety concerns arise because the fissile contents (i.e., Pu-239 and its decay daughter U-235) in these waste forms are higher than in LWR spent UO2 fuel. MOx spent fuel could contain 3 to 4 wt% of reactor-grade plutonium, compared to only 0.9 wt% of plutonium in LWR spent UO2 fuel. At some future time (tens of thousand of years), when the waste forms had deteriorated due to intruding groundwater, the water could mix with the long-lived fissile materials to form into a critical system. If the critical system is self-sustaining, somewhat like the natural-occurring reactor in OKLO, fission products produced could readily be available for dissolution and release out to the accessible environment, adversely affecting public health and safety. This paper will address ongoing activities to evaluate long-term criticality safety concerns associated with disposition of fissile material in a geologic setting. Issues to be addressed include the identification of a worst-case water-intrusion scenario and waste-form geometries which present the most concern for long-term criticality safety; and suggests of technical solutions for such concerns

  18. Engineering Hematopoietic Cells for Cancer Immunotherapy: Strategies to Address Safety and Toxicity Concerns.

    Science.gov (United States)

    Resetca, Diana; Neschadim, Anton; Medin, Jeffrey A

    2016-09-01

    Advances in cancer immunotherapies utilizing engineered hematopoietic cells have recently generated significant clinical successes. Of great promise are immunotherapies based on chimeric antigen receptor-engineered T (CAR-T) cells that are targeted toward malignant cells expressing defined tumor-associated antigens. CAR-T cells harness the effector function of the adaptive arm of the immune system and redirect it against cancer cells, overcoming the major challenges of immunotherapy, such as breaking tolerance to self-antigens and beating cancer immune system-evasion mechanisms. In early clinical trials, CAR-T cell-based therapies achieved complete and durable responses in a significant proportion of patients. Despite clinical successes and given the side effect profiles of immunotherapies based on engineered cells, potential concerns with the safety and toxicity of various therapeutic modalities remain. We discuss the concerns associated with the safety and stability of the gene delivery vehicles for cell engineering and with toxicities due to off-target and on-target, off-tumor effector functions of the engineered cells. We then overview the various strategies aimed at improving the safety of and resolving toxicities associated with cell-based immunotherapies. Integrating failsafe switches based on different suicide gene therapy systems into engineered cells engenders promising strategies toward ensuring the safety of cancer immunotherapies in the clinic.

  19. Shelf life and safety concerns of bakery products--a review.

    Science.gov (United States)

    Smith, James P; Daifas, Daphne Phillips; El-Khoury, Wassim; Koukoutsis, John; El-Khoury, Anis

    2004-01-01

    Bakery products are an important part of a balanced diet and, today, a wide variety of such products can be found on supermarket shelves. This includes unsweetened goods (bread, rolls, buns, crumpets, muffins and bagels), sweet goods (pancakes, doughnuts, waffles and cookies) and filled goods (fruit and meat pies, sausage rolls, pastries, sandwiches, cream cakes, pizza and quiche). However, bakery products, like many processed foods, are subject to physical, chemical and microbiological spoilage. While physical and chemical spoilage limits the shelf life of low and intermediate moisture bakery products, microbiological spoilage by bacteria, yeast and molds is the concern in high moisture products i.e., products with a water activity (a(w)) > 0.85. Furthermore, several bakery products also have been implicated infoodborne illnesses involving Salmonella spp., Listeria monoctyogenes and Bacillus cereus, while Clostridium botulinum is a concern in high moisture bakery products packaged under modified atmospheres. This extensive review is divided into two parts. Part I focuses on the spoilage concerns of low, intermediate and high moisture bakery products while Part II focuses on the safety concerns of high moisture bakery products only. In both parts, traditional and novel methods of food preservation that can be used by the bakery industry to extend the shelf life and enhance the safety of products are discussed in detail.

  20. Preparedness and response for a nuclear or radiological emergency. Safety requirements

    International Nuclear Information System (INIS)

    2004-01-01

    This Safety Requirements publication establishes the requirements for an adequate level of preparedness and response for a nuclear or radiological emergency in any State. Their implementation is intended to minimize the consequences for people, property and the environment of any nuclear or radiological emergency. The fulfilment of these requirements will also contribute to the harmonization of arrangements in the event of a transnational emergency. These requirements are intended to be applied by authorities at the national level by means of adopting legislation, establishing regulations and assigning responsibilities. The requirements apply to all those practices and sources that have the potential for causing radiation exposure or environmental radioactive contamination warranting an emergency intervention and that are: (a) Used in a State that chooses to adopt the requirements or that requests any of the sponsoring organizations to provide for the application of the requirements. (B) Used by States with the assistance of the FAO, IAEA, ILO, PAHO, OCHA or WHO in compliance with applicable national rules and regulations. (C) Used by the IAEA or which involve the use of materials, services, equipment, facilities and non-published information made available by the IAEA or at its request or under its control or supervision. Or (d) Used under any bilateral or multilateral arrangement whereby the parties request the IAEA to provide for the application of the requirements. The requirements also apply to the off-site jurisdictions that may need to make an emergency intervention in a State that adopts the requirements. The types of practices and sources covered by these requirements include: fixed and mobile nuclear reactors. Facilities for the mining and processing of radioactive ores. Facilities for fuel reprocessing and other fuel cycle facilities. Facilities for the management of radioactive waste. The transport of radioactive material. Sources of radiation used in

  1. Occupational Safety and Health Concerns in Logging: A Cross-Sectional Assessment in Virginia

    Directory of Open Access Journals (Sweden)

    Sunwook Kim

    2017-11-01

    Full Text Available Increased logging mechanization has helped improve logging safety and health, yet related safety risks and concerns are not well understood. A cross-sectional study was completed among Virginia loggers. Participants (n = 122 completed a self-administered questionnaire focusing on aspects of safety and health related to logging equipment. Respondents were at a high risk of workplace injuries, with reported career and 12-month injury prevalences of 51% and 14%, respectively. Further, nearly all (98% respondents reported experiencing musculoskeletal symptoms. Over half (57.4% of respondents reported symptoms related to diesel exhaust exposure in their career. Few (15.6%, however, perceived their jobs to be dangerous. Based on the opinions and suggestions of respondents, three priority areas were identified for interventions: struck-by/against hazards, situational awareness (SA during logging operations, and visibility hazards. To address these hazards, and to have a broader and more substantial positive impact on safety and health, we discuss the need for proactive approaches such as incorporating proximity technologies in a logging machine or personal equipment, and enhancing logging machine design to enhance safety, ergonomics, and SA.

  2. Advance of the National Program of Radiological Protection and Safety for medical diagnostic with X-rays

    International Nuclear Information System (INIS)

    Verdejo S, M.

    1999-01-01

    The National Program of Radiological Protection and Safety for medical diagnostic with X-ray (Programa Nacional de Proteccion y Seguridad Radiologica para diagnostico medico con rayos X) was initiated in the General Direction of Environmental Health (Direccion General de Salud Ambiental) in 1995. Task coordinated with different dependences of the Public Sector in collaboration between the Secretary of Health (Secretaria de Salud), the National Commission of Nuclear Safety and Safeguards (Comision Nacional de Seguridad Nuclear y Salvaguardias) and, the National Institute of Nuclear Research (Instituto Nacional de Investigaciones Nucleares). The surveillance to the fulfilment of the standardization in matter of Radiological Protection and Safety in the medical diagnostic with X-rays has been obtained for an important advance in the Public sector and it has been arousing interest in the Private sector. (Author)

  3. Radiological safety and GMP in the bulk batch manufacturing, formulation and dispensing of radiopharmaceuticals

    International Nuclear Information System (INIS)

    Thulasidhasan, A.; Tiwary, Bikash; Kumar, Uma Sheri; Kale, Pooja; Tiwary, Richa; Gaurav, Ananad; Shah, B.K.; Topale, P.D.; Prabhakar, G.; Sachdev, S.S.

    2010-01-01

    Full text: Radiopharmaceutical Program of BRIT is involved in the manufacturing of ready to use radiopharmaceuticals for therapy for the last three decades. Ready to use Radiopharmaceutical products include, 131 I-Sodium iodide solution and capsules for thyroid carcinoma and metastatic lesions, 131 I MIBG injection for diagnosis and therapy of adrenal medullae tumors and their mets, 153 Sm-EDTMP injection and 32 P- Sodium orthophosphate injection for bone pain palliative treatment. BRIT's radiopharmaceutical production facility is a radioisotope laboratory classified as Type-III facility for handling radioisotopes of Group-II, Group-III and Group-IV approved by AERB. This facility meets all the radiological safety requirements as per AERB guidelines. Production of above mentioned radiopharmaceuticals is carried out in Production Plants (PP), β, γ Glove boxes (GB) and Fume hoods (FH). Typical production procedure involves bulk processing, formulation, sterilization and dispensing of doses. Production Plants (PP) are exclusively designed facilities to carry out the production in a radiologically safe manner, at the same time maintaining aseptic conditions required for injectables as per the current GMP. Each production plant has a leak tight Isolator box, made up of high quality SS which has provisions for remote handling devices like, Tongs, dispensing systems, service points for vacuum, gas, compressed air, water and electric power. This Isolator box is shielded from all sides by required amount of lead (2 inch or 4 inch), and has an access port called 'Transport Port Box' with double door transport lock and is equipped with a trolley. Two filter unit systems are fitted at the top of the plant and each unit comprises of activated Charcoal filter and HEPA filter in tandem, this in turn is connected to special exhaust meant for radioactive gases. Similarly, the designs of β, γ Glove boxes (GB) and Fume hoods (FH) also incorporate all radiological safety features

  4. Report on nuclear and radiological safety in 1994; Porocilo o jedrski in radioloski varnosti v letu 1994

    Energy Technology Data Exchange (ETDEWEB)

    Lovincic, D [Slovenian Nuclear Safety Administration, Ljubljana (Slovenia)

    1995-07-01

    The Slovenian Nuclear Safety Administration (SNSA) in cooperation with the Health Inspectorate, prepared the Report on Nuclear and Radiological Safety in the Republic of Slovenia for 1994 as part of its regular practice of reporting on its activities to the Government and the Parliament of the Republic of Slovenia. The report is divided into seven thematic chapters covering the activities of the SNSA, the operation of nuclear facilities in Slovenia, the activities of the Agency for Radwaste Management (ARAO), the activities of international safety missions in Slovenia, environmental radioactivity monitoring in Slovenia, ionizing radiation sources control by Slovenian Health Inspectorate and review of the operation of nuclear facilities around the world.

  5. Source term derivation and radiological safety analysis for the TRICO II research reactor in Kinshasa

    International Nuclear Information System (INIS)

    Muswema, J.L.; Ekoko, G.B.; Lukanda, V.M.; Lobo, J.K.-K.; Darko, E.O.; Boafo, E.K.

    2015-01-01

    Highlights: • Atmospheric dispersion modeling for two credible accidents of the TRIGA Mark II research reactor in Kinshasa (TRICO II) was performed. • Radiological safety analysis after the postulated initiating events (PIE) was also carried out. • The Karlsruhe KORIGEN and the HotSpot Health Physics codes were used to achieve the objectives of this study. • All the values of effective dose obtained following the accident scenarios were below the regulatory limits for reactor staff members and the public, respectively. - Abstract: The source term from the 1 MW TRIGA Mark II research reactor core of the Democratic Republic of the Congo was derived in this study. An atmospheric dispersion modeling followed by radiation dose calculation were performed based on two possible postulated accident scenarios. This derivation was made from an inventory of peak radioisotope activities released in the core by using the Karlsruhe version of isotope generation code KORIGEN. The atmospheric dispersion modeling was performed with HotSpot code, and its application yielded to radiation dose profile around the site using meteorological parameters specific to the area under study. The two accident scenarios were picked from possible accident analyses for TRIGA and TRIGA-fueled reactors, involving the case of destruction of the fuel element with highest activity release and a plane crash on the reactor building as the worst case scenario. Deterministic effects of these scenarios are used to update the Safety Analysis Report (SAR) of the reactor, and for its current version, these scenarios are not yet incorporated. Site-specific meteorological conditions were collected from two meteorological stations: one installed within the Atomic Energy Commission and another at the National Meteorological Agency (METTELSAT), which is not far from the site. Results show that in both accident scenarios, radiation doses remain within the limits, far below the recommended maximum effective

  6. Source term derivation and radiological safety analysis for the TRICO II research reactor in Kinshasa

    Energy Technology Data Exchange (ETDEWEB)

    Muswema, J.L., E-mail: jeremie.muswem@unikin.ac.cd [Faculty of Science, University of Kinshasa, P.O. Box 190, KIN XI (Congo, The Democratic Republic of the); Ekoko, G.B. [Faculty of Science, University of Kinshasa, P.O. Box 190, KIN XI (Congo, The Democratic Republic of the); Lukanda, V.M. [Faculty of Science, University of Kinshasa, P.O. Box 190, KIN XI (Congo, The Democratic Republic of the); Democratic Republic of the Congo' s General Atomic Energy Commission, P.O. Box AE1 (Congo, The Democratic Republic of the); Lobo, J.K.-K. [Faculty of Science, University of Kinshasa, P.O. Box 190, KIN XI (Congo, The Democratic Republic of the); Darko, E.O. [Radiation Protection Institute, Ghana Atomic Energy Commission, P.O. Box LG 80, Legon, Accra (Ghana); Boafo, E.K. [University of Ontario Institute of Technology, 2000 Simcoe St. North, Oshawa, ONL1 H7K4 (Canada)

    2015-01-15

    Highlights: • Atmospheric dispersion modeling for two credible accidents of the TRIGA Mark II research reactor in Kinshasa (TRICO II) was performed. • Radiological safety analysis after the postulated initiating events (PIE) was also carried out. • The Karlsruhe KORIGEN and the HotSpot Health Physics codes were used to achieve the objectives of this study. • All the values of effective dose obtained following the accident scenarios were below the regulatory limits for reactor staff members and the public, respectively. - Abstract: The source term from the 1 MW TRIGA Mark II research reactor core of the Democratic Republic of the Congo was derived in this study. An atmospheric dispersion modeling followed by radiation dose calculation were performed based on two possible postulated accident scenarios. This derivation was made from an inventory of peak radioisotope activities released in the core by using the Karlsruhe version of isotope generation code KORIGEN. The atmospheric dispersion modeling was performed with HotSpot code, and its application yielded to radiation dose profile around the site using meteorological parameters specific to the area under study. The two accident scenarios were picked from possible accident analyses for TRIGA and TRIGA-fueled reactors, involving the case of destruction of the fuel element with highest activity release and a plane crash on the reactor building as the worst case scenario. Deterministic effects of these scenarios are used to update the Safety Analysis Report (SAR) of the reactor, and for its current version, these scenarios are not yet incorporated. Site-specific meteorological conditions were collected from two meteorological stations: one installed within the Atomic Energy Commission and another at the National Meteorological Agency (METTELSAT), which is not far from the site. Results show that in both accident scenarios, radiation doses remain within the limits, far below the recommended maximum effective

  7. Health and safety concerns os migrant workers: the experience of tunisian workers in modena, Italy

    Directory of Open Access Journals (Sweden)

    Faïçal Daly

    2004-06-01

    Full Text Available This paper examines the relatively under-researched field of healthand safety of migrant workers, with special reference to Tunisian construction workers in the city of Modena in the Italian region of Emilia-Romagna. The empirical material comes from questionnaires and interviews with Tunisian migrants, plus smaller numbers of interviews with employers and trade union representatives in Modena. The paper starts by critically reviewing the scattered literature onthe health and safety of minority workers, most of which refers to the United States and the United Kingdom. The discussion then moves to a consideration of migrant health and safety questions in the contexts of racism, discrimination, social class, working conditions, labour market segmentation and (non- regulation. Specialattention is given to the failed role of trade unions in defending the rights of minority workers, in advanced countries generally and in Italy in particular. A case study is then made of the construction sector in Italy, enriched by personal accounts of the experiences of Tunisian migrant workers in Modena. Employer and tradeunion interviews reveal a lack of concern and ability to tackle the relevant issues. Barriers to health and safety awareness training are outlined. In the conclusion, recommendations are made for policy initiatives in this area.

  8. The U.S. commercial air tour industry: a review of aviation safety concerns.

    Science.gov (United States)

    Ballard, Sarah-Blythe

    2014-02-01

    The U.S. Title 14 Code of Federal Regulations defines commercial air tours as "flight[s] conducted for compensation or hire in an airplane or helicopter where a purpose of the flight is sightseeing." The incidence of air tour crashes in the United States is disproportionately high relative to similar commercial aviation operations, and air tours operating under Part 91 governance crash significantly more than those governed by Part 135. This paper reviews the government and industry response to four specific areas of air tour safety concern: surveillance of flight operations, pilot factors, regulatory standardization, and maintenance quality assurance. It concludes that the government and industry have successfully addressed many of these tenet issues, most notably by: advancing the operations surveillance infrastructure through implementation of en route, ground-based, and technological surveillance methods; developing Aeronautical Decision Making and cue-based training programs for air tour pilots; consolidating federal air tour regulations under Part 136; and developing public-private partnerships for raising maintenance operating standards and improving quality assurance programs. However, opportunities remain to improve air tour safety by: increasing the number and efficiency of flight surveillance programs; addressing pilot fatigue with more restrictive flight hour limitations for air tour pilots; ensuring widespread uptake of maintenance quality assurance programs, especially among high-risk operators not currently affiliated with private air tour safety programs; and eliminating the 25-mile exception allowing Part 91 operators to conduct commercial air tours without the safety oversight required of Part 135 operators.

  9. Report on the handling of safety information concerning flammable gases and ferrocyanide at the Hanford waste tanks

    International Nuclear Information System (INIS)

    1990-07-01

    This report discusses concerns safety issues, and management at Hanford Tank Farm. Concerns center on the issue of flammable gas generation which could ignite, and on possible exothermic reactions of ferrocyanide compounds which were added to single shell tanks in the 1950's. It is believed that information concerning these issues has been mis-handled and the problems poorly managed

  10. Report on the handling of safety information concerning flammable gases and ferrocyanide at the Hanford waste tanks

    Energy Technology Data Exchange (ETDEWEB)

    1990-07-01

    This report discusses concerns safety issues, and management at Hanford Tank Farm. Concerns center on the issue of flammable gas generation which could ignite, and on possible exothermic reactions of ferrocyanide compounds which were added to single shell tanks in the 1950's. It is believed that information concerning these issues has been mis-handled and the problems poorly managed. (CBS)

  11. Caffeine-based food supplements and beverages: Trends of consumption for performance purposes and safety concerns.

    Science.gov (United States)

    Bessada, Sílvia M F; Alves, Rita C; Oliveira, M Beatriz P P

    2018-07-01

    Nowadays, daily food supplementation regarding the improvement of physical and mental performance is a growing trend in sport practitioners, young students and active people. Food supplements are foodstuffs, labeled under food law and not obliged to safety assessments before their commercialization. Several products are commercialized claiming ergogenic effects as marketing strategies. Caffeine is often one of their main ingredients, as it increases both physical performance and concentration. This manuscript presents a general overview of the current caffeine-based food supplements and energy drinks available in the Portuguese market, as well as the consuming trends regarding their ergogenic effects, performance purposes, and active ingredients. Product claims, recommended daily intakes, caffeine pharmacology, and safety concerns aspects are also discussed aspects. Copyright © 2018 Elsevier Ltd. All rights reserved.

  12. Socializing Young People to Ethics via Play Experience: Browser Games and Parental Concerns for Safety Online

    Directory of Open Access Journals (Sweden)

    Divina Meigs

    2009-01-01

    Full Text Available This paper considers an online game and its relation to safety and privacy, in order to examine social and ethical issues raised by parental concern over harmful content. To gain real insights on the responsibility of adults, it develops a hands-on approach that takes into account the major stakeholders, especially young people and the related circle of people around them. Therefore the research question that is raised is: how do browser games provide reassurance to parents about their children’s safety and privacy? The issue of safety online is explored in three parts, using an ethnographic research framework: it explores a specific online game, it provides a profile of participants, it analyses their types of actions in relation to safety and privacy, and discusses the results in terms of incidence of risk, peer-monitoring and community control. The findings show that there is a rather strong tendency to self-regulation, but that tendency is partly due to a strong presence of mediating adults and peers. The results are discussed in terms of incidence of risk, peer-monitoring and networked means of control on the one hand, and in terms of scientific contribution to socialization theory on the other hand. They lead to final considerations on the repertoire of ethical strategies set up online and its meaning for the concerns of adults towards online risk as well as the need for policies on regulation and self-regulation. They also lead to extensions on the socialization to norms and the appropriation of ethics by young people.

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

    International Nuclear Information System (INIS)

    Oliver, Caroline.

    1979-01-01

    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.)

  14. List of reports from the BMFT, CEA, EPRI, JSTA and USNRC concerning reactor safety research

    International Nuclear Information System (INIS)

    1981-09-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special Problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA) the Japan Science and Technology Agency (JSTA) the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Saftety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  15. Challenges in ensuring radiological safety and nuclear forensic for malicious acts involving nuclear and other radioactive material

    International Nuclear Information System (INIS)

    Sharma, Ranjit; Chatterjee, M.K.; Singh, Rajvir; Pradeepkumar, K.S.

    2010-01-01

    Nuclear and other radioactive materials may get smuggled into the country aimed at malicious acts. Radioactive material detected accidentally or during inspection at the entry points/national borders may indicate illicit trafficking for the purpose of nuclear/radiological terrorism. As country requires prevention and preparedness for response to these malicious acts, nuclear forensic techniques are to be developed incorporating radiological safety aspects. Nuclear forensics helps in determining the origin, intended use, legal owner and the smuggled route etc. by using fingerprinting as well as comparison with reference data. The suggested sequence of methods for analysis of radioactive material/samples will be radiological assessment, physical characterization, traditional forensic analysis, isotope analysis along with elemental/chemical analysis

  16. Radiological safety experience in nuclear fuel cycle operations at Bhabha Atomic Research Center, Trombay, Mumbai, India

    International Nuclear Information System (INIS)

    Pushparaja; Gopalakrishnan, R.K.; Subramaniam, G.

    2000-01-01

    Activities at Bhabha Atomic Research Centre (BARC), Mumbai, cover nuclear fuel cycle operations based on natural uranium as the fuel. The facilities include: plant for purification and production of nuclear grade uranium metal, fuel fabrication, research reactor operation, fuel reprocessing and radioactive waste management in each stage. Comprehensive radiation protection programmes for assessment and monitoring of radiological impact of these operations, both in occupational and public environment, have been operating in BARC since beginning. These programmes, based on the 1990 ICRP Recommendations as prescribed by national regulatory body, the Atomic Energy Regulatory Board (AERB), are being successfully implemented by the Health, Safety and Environment Group, BARC. Radiation Hazards Control Units attached to the nuclear fuel cycle facilities provide radiation safety surveillance to the various operations. The radiation monitoring programme consists of measurement and control of external exposures by thermoluminescent dosimeters (TLDs), hand-held and installed instruments, and internal exposures by bioassay and direct whole body counting using shadow shield counter for beta gamma emitters and phoswich detector based system for plutonium. In addition, an environmental monitoring programme is in place to assess public exposures resulting from the operation of these facilities. The programme involves analysis of various matrices in the environment such as bay water, salt, fish, sediment and computation of resulting public exposures. Based on the operating experience in these plants, improved educating and training programmes for plant operators, have been designed. This, together with the application of new technologies have brought down individual as well as average doses of occupational workers. The environmental releases remain a small fraction of the authorised limits. The operating health physics experience in some of these facilities is discussed in this paper

  17. 'On line' course for the periodical training in radiological safety of the workers of a radioactive facility

    International Nuclear Information System (INIS)

    Amador B, Z.H.; Ayra P, F.E.; Torres B, M.B.

    2006-01-01

    The results of an 'on line' course for the periodical training in radiological safety of the workers of a radioactive installation are presented. The course is developed for own specialists. The following topics are approached: the state of the art of the studies on the biological effects of the ionizing radiations, the new national regulations, the analysis of the behavior of the occupational exposure, of the obtained experiences of the radiological events, of the results of the radiological surveillance of the work positions, of the detected violations and of the behavior of the outstanding systems and the optimization. The study of the acquired experiences in the packing and the transportation of radioactive materials and the administration of the radioactive waste are included. The study of the course by one month is organized and then two convocations of theoretical exams are executed and one for the evaluation practices of the instructions and procedures. To evaluate the effectiveness of the course a survey it is applied and the later behavior of indicators of the radiological safety of the plant is analyzed. The results that are obtained show a positive balance. (Author)

  18. Medical management of radiation safety and radiological protection of patients in Armenia

    International Nuclear Information System (INIS)

    Hovhannisyan, N.M.

    2001-01-01

    The events of the last 10 years, Spitak earthquake (1988) and collapse of the Former Soviet Union, brought forth the changes of the political situation in Armenia and significant disorder in economy, industry, relations, environmental and public health, including the radiation safety (RS) and control of patients in general diagnostic radiology. In Armenia there are about 750 X-ray rooms, 10 radionuclide diagnostic laboratories, 20 gamma and X-ray units. 95 enterprises in industry, science and technology use the Ionizing Radiation Sources (IRSs) with different purposes; there are 5 electron particle accelerators of different power capacity. About 6,000 individuals have constant contact to IRS: the roentgenologists, radiologists, the staff of Armenian Nuclear Power Plant and that of the accelerators, etc. Besides, more than 3,000 liquidators of the Chernobyl NPP disaster live in Armenia. Nowadays, the precise infrastructure of RS is established in Armenia. The regulating body is the 'State Atom Authority', performing the control, coordination and licensing of both enterprises and specialists. Ministry of Health, Ministry of Internal Affairs, and Ministry of Ecology perform the control of IRSs' delivery into the Republic of Armenia and then their proper use and waste disposal in Armenia. (author)

  19. Radiological safety research of food irradiation with 7.5 MeV X-rays

    International Nuclear Information System (INIS)

    Yang Bin; Tang Weidong; Zhang Yue; Xu Tao; Jin Jianqiao; Ye Mingyang

    2012-01-01

    China and America both have 7.5 MeV high energy X-ray accelerator. The radiological safety of food irradiated with 7.5 MeV X-rays (bremsstrahlung) has been investigated. Samples of meat and meat ash were located in a large volume of fresh meat at the position of the highest photoneutron fluence and irradiated to an X-ray dose of 15 kGy, twice the maximum dose allowed by the US FDA for meat irradiation. An evaluation of the corresponding radiation exposure from ingestion of the irradiated product has been compared to natural background radiation. The paper concludes that the risk to individuals from intake of food irradiated with X-rays from 7.5 MeV electrons, even with a broad energy spectrum, would be trivial. The common target materials are Au, Ta and W. The U.S, requires only Au and Ta can be used as food irradiation target materials and China has not yet relevant provisions. The first 7.5 MeV accelerator for food irradiation in China is under built, and will do the explore research for the choice of target material. (authors)

  20. Mechanical analysis of flying robot for nuclear safety and security control by radiological monitoring

    International Nuclear Information System (INIS)

    Cho, Hyo Sung; Woo, Tae Ho

    2016-01-01

    Highlights: • Radiological monitoring of the NPPs site is performed by the flying robot. • The mechanics of drone is investigated in the NPPs. • Yaw and Pitch motions are simulated for the robotic behaviors. • The flying robot is analyzed for the nuclear safety and security successfully. - Abstract: The flying robot is investigated for the nuclear accident and security treatment. Several mechanics are introduced for the movement of the drone. The optimized motion of the drone should cover all areas of Nuclear Power Plants (NPPs) over the site where the circular and surmounting motions are needed with traverse of zigzag shapes. There is the Yaw motion in the circular moving and the Pitch motion in the climbing and downing against reactor facility. The fallout is calculated from the radiation concentration in the breaking part of the NPPs where the radioactive material leaks from the containment, coolant loop, plant facility and so on. The dose equivalents are obtained where the values are changeable following the random values of the y value, average wind speed, and dispersed concentration in the detection position. The simulation of new positions of x, y, and z are normalized from 0.0 to 1.0. The mechanics of flying robot produces the multidisciplinary converged technology incorporated with the aerial radiation monitoring information.

  1. Parental safety concerns--a barrier to sport and physical activity in children?

    Science.gov (United States)

    Boufous, Soufiane; Finch, Caroline; Bauman, Adrian

    2004-10-01

    To examine the extent to which parents and carers perceive injury and safety risks as serious enough to prevent or discourage their children, aged 5-12 years, from participating in sports/physical activity and to identify factors that influence these perceptions. An analysis of the 2001 New South Wales Child Health Survey. More than one-quarter of parents/ carers of active children aged 5-12 years reported discouraging or preventing children from playing a particular sport (34.7% for boys and 16.6% for girls) because of injury and safety concerns. In boys, the most frequently discouraged sport was rugby league (23.2%), followed by rugby union (7.5%) and Australian rules football (2.8%). Among girls, the most frequently discouraged activities were rollerblading (2.7%), rugby league (2.3%) and soccer (2.1%). Multivariate analysis shows that factors independently associated with parents' decision to prevent/discourage their child from engaging in sport/physical activity include their child's age and gender, language spoken at home, presence of disability, and the respondent's relation to the child. Efforts need to be made to modify some sports/ activities, such as football codes, in order to minimise injury and to ensure that children continue enjoying their favourite activity well into adulthood. Guidelines designed to promote physical activity among children and young adolescents need to take into account parental concerns regarding the associated risk of injury.

  2. Some information about the radiological protection concerning the TRIGA spent fuel handling at the Medical University of Hanover

    International Nuclear Information System (INIS)

    Hampel, Gabriele; Harke, Heinrich; Klaus, Uwe; Loercher, Gunther

    2008-01-01

    The Medical University of Hanover (MHH) returned its 76 spent TRIGA fuel elements to the United States in summer of 1999. For the transportation inside the MHH control areas were installed outside the reactor area, along the transfer route in the department of nuclear medicine and in the temporary building. During fuel handling at MHH a lot of radiation protection measures were necessary. This paper presents methods and results of the radiological protection measurements. (authors)

  3. Preclosure radiological safety analysis for accident conditions of the potential Yucca Mountain Repository: Underground facilities; Yucca Mountain Site Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    Ma, C.W.; Sit, R.C.; Zavoshy, S.J.; Jardine, L.J. [Bechtel National, Inc., San Francisco, CA (United States); Laub, T.W. [Sandia National Labs., Albuquerque, NM (United States)

    1992-06-01

    This preliminary preclosure radiological safety analysis assesses the scenarios, probabilities, and potential radiological consequences associated with postulated accidents in the underground facility of the potential Yucca Mountain repository. The analysis follows a probabilistic-risk-assessment approach. Twenty-one event trees resulting in 129 accident scenarios are developed. Most of the scenarios have estimated annual probabilities ranging from 10{sup {minus}11}/yr to 10{sup {minus}5}/yr. The study identifies 33 scenarios that could result in offsite doses over 50 mrem and that have annual probabilities greater than 10{sup {minus}9}/yr. The largest offsite dose is calculated to be 220 mrem, which is less than the 500 mrem value used to define items important to safety in 10 CFR 60. The study does not address an estimate of uncertainties, therefore conclusions or decisions made as a result of this report should be made with caution.

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

    International Nuclear Information System (INIS)

    Satou, Yukimitsu

    1988-01-01

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

    Energy Technology Data Exchange (ETDEWEB)

    Satou, Yukimitsu

    1988-10-01

    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.

  6. Study concerning the power plant control and safety equipment by integrated distributed systems

    International Nuclear Information System (INIS)

    Optea, I.; Oprea, M.; Stanescu, P.

    1995-01-01

    The paper deals with the trends existing in the field of nuclear control and safety equipment and systems, proposing a high-efficiency integrated system. In order to enhance the safety of the plant and reliability of the structure system and components, we present a concept based on the latest computer technology with an open, distributed system, connected by a local area network with high redundancy. A modern conception for the control and safety system is to integrate all the information related to the reactor protection, active engineered safeguard and auxiliary systems parameters, offering a fast flow of information between all the agencies concerned so that situations can be quickly assessed. The integrated distributed control is based on a high performance operating system for realtime applications, flexible enough for transparent networking and modular for demanding configurations. The general design considerations for nuclear reactors instrumentation reliability and testing methods for real-time functions under dynamic regime are presented. Taking into account the fast progress in information technology, we consider the replacement of the old instrumentation of Cernavoda-1 NPP by a modern integrated system as an economical and efficient solution for the next units. (Author) 20 Refs

  7. The root cause of patient safety concerns in an Internet pharmacy.

    Science.gov (United States)

    Montoya, Isaac D

    2008-07-01

    The Internet has become a revolutionary technology that affords worldwide opportunities never seen before. One such opportunity is the purchase of drugs over the Internet and the business of Internet pharmacies which has become prolific. Associated with this proliferation is the concern for patient safety. Numerous studies have shown that drugs purchased over the Internet come from pharmacies in a country other than the one where the patient resides and these pharmacies are not licensed, sometimes provide drugs without a prescription and that are not of the same composition as they should be, and do not provide adequate directions to the patient. In addition, the packaging of the drugs may be compromised resulting in altered medication. This paper examines the root cause of patient safety issues in Internet pharmacies. A review of the literature including the marketing literature was conducted. Healthcare marketing concepts guide business owners to identify patients' wants and distinguish them from their needs. Marketing principles detail aggressive marketing strategies within an organization's mission and in an ethical manner. Some Internet pharmacies misinterpret proven marketing principles and become overly aggressive in the market place focusing only on sales and profit rather than focusing on patient safety and long-term success of the Internet pharmacy.

  8. Genetically modified foods: safety, risks and public concerns-a review.

    Science.gov (United States)

    Bawa, A S; Anilakumar, K R

    2013-12-01

    Genetic modification is a special set of gene technology that alters the genetic machinery of such living organisms as animals, plants or microorganisms. Combining genes from different organisms is known as recombinant DNA technology and the resulting organism is said to be 'Genetically modified (GM)', 'Genetically engineered' or 'Transgenic'. The principal transgenic crops grown commercially in field are herbicide and insecticide resistant soybeans, corn, cotton and canola. Other crops grown commercially and/or field-tested are sweet potato resistant to a virus that could destroy most of the African harvest, rice with increased iron and vitamins that may alleviate chronic malnutrition in Asian countries and a variety of plants that are able to survive weather extremes. There are bananas that produce human vaccines against infectious diseases such as hepatitis B, fish that mature more quickly, fruit and nut trees that yield years earlier and plants that produce new plastics with unique properties. Technologies for genetically modifying foods offer dramatic promise for meeting some areas of greatest challenge for the 21st century. Like all new technologies, they also pose some risks, both known and unknown. Controversies and public concern surrounding GM foods and crops commonly focus on human and environmental safety, labelling and consumer choice, intellectual property rights, ethics, food security, poverty reduction and environmental conservation. With this new technology on gene manipulation what are the risks of "tampering with Mother Nature"?, what effects will this have on the environment?, what are the health concerns that consumers should be aware of? and is recombinant technology really beneficial? This review will also address some major concerns about the safety, environmental and ecological risks and health hazards involved with GM foods and recombinant technology.

  9. Regulatory oversight report 2015 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    2016-06-01

    The Swiss Federal Nuclear Safety Inspectorate (ENSI) assesses and monitors nuclear facilities in Switzerland. These include the five nuclear power plants (Beznau Units 1 and 2, Muehleberg, Goesgen and Leibstadt), the interim storage facilities based at each plant, the Central Interim Storage Facility (Zwilag) at Wuerenlingen together with the nuclear facilities at the Paul Scherrer Institute (PSI), the University of Basel and the Federal Institute of Technology in Lausanne (EPFL), as well as the transport of radioactive materials and the preparatory work for a deep geological repository for nuclear waste. Using a combination of inspections, regulatory meetings, examinations and analyses together with reports from the licensees of individual facilities, ENSI obtains the required overview of nuclear safety in these facilities. ENSI maintains its own emergency organization. It provides the public with information on particular events and findings in nuclear facilities. ENSI publishes an annual Radiological Protection Report and a Research and Experience Report. Chapters 1 to 4 of this Surveillance Report deal with operational experience, systems technology, radiological protection and management of the 5 Swiss nuclear power plants. Chapter 5 deals with Zwilag. Chapters 6 and 7 are devoted to the nuclear facilities at PSI and the research reactor at EPFL as well as the decommissioned University of Basel’s research reactor. Chapter 8 covers the transport of radioactive materials. The subject of Chapter 9 is the deep geological storage of radioactive waste including work within the framework of the Sectoral Plan. Finally, Chapter 10 deals with generic issues relevant to all facilities such as probabilistic safety analyses. In 2015, all five nuclear power plants in Switzerland were safely operated and ENSI concluded that each had adhered to its approved operating conditions. There were 34 reportable events at the nuclear power plants; 32 events were rated at Level 0 on

  10. ENSI’s synopsis concerning the enhancement of safety margins; Zusammenfassung des ENSI zur Erhöhung der Sicherheitsmargen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-06-15

    This press release issued by the Swiss Federal Nuclear Safety Inspectorate ENSI discusses the results of its probabilistic safety analysis on the safety margins for Swiss nuclear power stations that was made after the Fukushima nuclear accident. External incidents such as earthquakes and flooding and their impact on the power stations are analysed by the ERSIM project concerning the enhancement of safety margins. Three shut-down scenarios are discussed. The safety margins with respect to earthquakes and flooding for all four nuclear power station sites are discussed in detail.

  11. Radiological safety aspects during handling of adjuster rod (cobalt-60) samples at Cirus

    International Nuclear Information System (INIS)

    Yadav, R.K.B.; Prasad, S.K.; Khuspe, R.R.; Babu, K.S.; Kamble, M.K.; Deshpande, S.B.; Srivastava, Alok; Ramesh, N.; Sharma, R.C.

    2008-01-01

    Cobalt -60 produced from the irradiation of the 59 Co capsules in adjuster rod of Cirus is used in many medical and industrial applications such as radiation therapy, sterilization of agricultural products, sterilization of medical equipment, industrial gamma exposure devices, nucleonic gauging sources etc. Two adjuster rods used for adjusting small reactivity loads (3.5 mk at 40 MW) in reactor contain thirty 59 Co slugs each. The 59 Co slugs are in the form of small capsules. These slugs were irradiated for nearly 3 years of full power operation. Since the amount of activity handled in the adjuster rod is very high (35 - 40 kCi), adequate radiological safety coverage is to be provided during the transfer of adjuster rod from the reactor pile to Tray Rod Facility (TRF) and during remote handling and loading of adjuster rod samples in shipping flask at TRF. Radiation fields observed are 0.4 - 3.0 Gy/h. In Cirus, falling of Adjuster rod from vertical flask at top of pile could result in declaration of evacuation emergency due to potential hazards associated with the high radiation field (∼26 Gy/h at 1m) of 60 Co slugs. Entire process of remote handling is viewed through lead glass and movement of samples is carried out with the help of a pair of master slave manipulator (MSM) arms. TRF with full samples give a radiation background of 0.2 - 20 mGy/h, requiring control of movement of personnel in the area. This paper explains in detail about the health physics aspects during handling of adjuster rod from reactor pile to TRF and back to pile, unloading and loading of radioisotope samples, operational radiation protection experience gained and collective dose consumed for the above transfer and loading job. The collective dose consumed in the handling of two adjuster rods is 8.7 per-mSv. (author)

  12. Joint WHO/ISH workshop on efficacy and radiation safety in interventional radiology

    International Nuclear Information System (INIS)

    Baeuml, A.; Bauer, B.; Bernhardt, J.H.; Stieve, F.E.; Veit, R.; Zeitlberger, I.

    1997-02-01

    With the constantly developing technology and the opening of new fields of application, the implementation of Interventional Radiology (IR) is increasing considerably. These sophisticated procedures can frequently replace open surgery, and this is of enormous benefit for the patient. On the other hand, IR involves prolonged application of fluoroscopy and - due to the need for excellent image quality - partly very high dose-rate levels. Additionally, cine-series, and alsogreat numbers of single radiographs are necessary. Accordingly, the levels of exposure to patients and staff are very high. In order to consider possible reduction of the radiation risks of IR procedures interdiciplinary talks between representatives of manufacturers of X-ray equipment, hospital physicists and the clinical community would seem necessary in order to find ways of avoiding unproductive radiation exposure to the patient and to clinical staff. This was the aim of a workshop on IR, which was jointly organized by the World Health Organization and the Institute of Radiation Hygiene of the Federal Office for Radiation Protection in Germany in October 1995. It was intended as a forum for the discussion of issues related to IR, and to forster improved application, that is to say as an opportunity: To present the state of the art; to work out proposals for more efficient clinical protocols; to discuss on schemes of education and training and on equipment-related developments. Improvement of radiation safety for both patients and staff, was the general aim of the workshop. This volume contains the presentations given on the first day of the workshop. (orig./DG) [de

  13. Proceedings of the 5. Regional congress on radiation protection and safety; 2. Iberian and Latin American Congress on Radiological Protection Societies; Regional IRPA Congress

    International Nuclear Information System (INIS)

    2001-01-01

    The Fifth Regional Congress on Radiation Protection and Nuclear Safety has been held in Recife (Brazil), from 29th April to 4th May 2001. The congress was hosted by the Brazilian Radiation Protection Society, under the joint sponsorship of FRALC and UFPE-DEN Department of Nuclear Energy. Its designation as a Regional IRPA Congress has been requested. The main purpose of the meeting was to bring together professionals from the industry, universities and research laboratories to present and discuss the latest research results, and to review the state of the art on applied and fundamental aspects of the radiation protection. These specialists have talked about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. In their discussions, also were included 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

  14. A decade of e-cigarettes: Limited research & unresolved safety concerns.

    Science.gov (United States)

    Kaisar, Mohammad Abul; Prasad, Shikha; Liles, Tylor; Cucullo, Luca

    2016-07-15

    It is well known that tobacco consumption is a leading cause of preventable deaths worldwide and has been linked to major diseases ranging from cancer to chronic obstructive pulmonary disease, atherosclerosis, stroke and a host of neurological/neurodegenerative disorders. In the past decade a number of alternative vaping products have hit the market, rapidly gaining consumers especially among the younger population. Electronic nicotine delivery systems or e-cigarettes have become the sought-after product due to the belief that they are much safer than traditional cigarettes. However, inadequate research and lack of regulatory guidelines for both the manufacturing process and the content of the vaping solution of the e-cigarette has become a major concern. Highly debated and unresolved questions such as whether e-cigarettes may help smokers quit and whether e-cigarettes will promote the use of nicotine among non-smokers add to the confusion of the safety of e-cigarettes. In this review article, we summarize the current understanding (and lack thereof) of the potential health impacts of e-cigarettes. We will also highlight the most recent studies (in vivo/in vitro) which seem to conflict with the broad safety claims put forward by the manufacturers. Finally, we provide potential solutions to overcome the research gap of the short and long-term health impact of e-cigarettes. Published by Elsevier Ireland Ltd.

  15. A decade of e-cigarettes: Limited research & unresolved safety concerns

    International Nuclear Information System (INIS)

    Kaisar, Mohammad Abul; Prasad, Shikha; Liles, Tylor; Cucullo, Luca

    2016-01-01

    It is well known that tobacco consumption is a leading cause of preventable deaths worldwide and has been linked to major diseases ranging from cancer to chronic obstructive pulmonary disease, atherosclerosis, stroke and a host of neurological/neurodegenerative disorders. In the past decade a number of alternative vaping products have hit the market, rapidly gaining consumers especially among the younger population. Electronic nicotine delivery systems or e-cigarettes have become the sought-after product due to the belief that they are much safer than traditional cigarettes. However, inadequate research and lack of regulatory guidelines for both the manufacturing process and the content of the vaping solution of the e-cigarette has become a major concern. Highly debated and unresolved questions such as whether e-cigarettes may help smokers quit and whether e-cigarettes will promote the use of nicotine among non-smokers add to the confusion of the safety of e-cigarettes. In this review article, we summarize the current understanding (and lack thereof) of the potential health impacts of e-cigarettes. We will also highlight the most recent studies (in vivo/in vitro) which seem to conflict with the broad safety claims put forward by the manufacturers. Finally, we provide potential solutions to overcome the research gap of the short and long-term health impact of e-cigarettes.

  16. A Decade of e-Cigarettes: Limited Research & Unresolved Safety Concerns

    Science.gov (United States)

    Kaisar, Mohammad Abul; Prasad, Shikha; Liles, Tylor; Cucullo, Luca

    2016-01-01

    It is well known that tobacco consumption is a leading cause of preventable deaths worldwide and has been linked to major diseases ranging from cancer to chronic obstructive pulmonary disease, atherosclerosis, stroke and a host of neurological/neurodegenerative disorders. In the past decade a number of alternative vaping products have hit the market, rapidly gaining consumers especially among the younger population. Electronic nicotine delivery systems or e-cigarettes have become the sought-after product due to the belief that they are much safer than traditional cigarettes. However, inadequate research and lack of regulatory guidelines for both the manufacturing process and the content of the vaping solution of the e-cigarette has become a major concern. Highly debated and unresolved questions such as whether e-cigarettes may help smokers quit and whether e-cigarettes will promote the use of nicotine among non-smokers add to the confusion of the safety of e-cigarettes. In this review article, we summarize the current understanding (and lack thereof) of the potential health impacts of e-cigarettes. We will also highlight the most recent studies (in vivo/in vitro) which seem to conflict with the broad safety claims put forward by the manufacturers. Finally, we provide potential solutions to overcome the research gap of the short and long-term health impact of e-cigarettes. PMID:27477296

  17. Ionising radiations. Joint consultative document. Supplementary proposals for provision on radiological protection and draft advice from the National Radiological Protection Board to the Health and Safety Commission

    International Nuclear Information System (INIS)

    1979-01-01

    The consultative document is in two parts. Part 1 indicates the amendments to the first consultative document which would be required in order to implement (in the United Kingdom) the 1978 Draft Euratom Directive (on Basic Safety Standards for the health protection of the general public and workers against the dangers of ionising radiations). Part 2 deals with the system of dose limitation contained within the Euratom Directive. This aspect is discussed, in relation to the Articles of the Directive, under the following headings: limitation of doses for controllable exposures, limits of doses for exposed workers, limitation of doses for apprentices and students, planned special exposures, dose limits for members of the public. The Commission of the European Communities proposals for a draft Directive on Radiological Protection are reproduced as an Appendix, without Annexes. (U.K.)

  18. Predictors of Likelihood of Speaking Up about Safety Concerns in Labour and Delivery

    Science.gov (United States)

    Lyndon, Audrey; Sexton, J. Bryan; Simpson, Kathleen Rice; Rosenstein, Alan; Lee, Kathryn A.; Wachter, Robert M.

    2011-01-01

    Background Despite widespread emphasis on promoting “assertive communication” by caregivers as essential to patient safety improvement efforts, fairly little is known about when and how clinicians speak up to address safety concerns. In this cross-sectional study we use a new measure of speaking up to begin exploring this issue in maternity care. Methods We developed a scenario-based measure of clinician’s assessment of potential harm and likelihood of speaking up in response to perceived harm. We embedded this scale in a survey with measures of safety climate, teamwork climate, disruptive behaviour, work stress, and personality traits of bravery and assertiveness. The survey was distributed to all registered nurses and obstetricians practicing in two US Labour & Delivery units. Results The response rate was 54% (125 of 230 potential respondents). Respondents were experienced clinicians (13.7 ± 11 years in specialty). Higher perception of harm, respondent role, specialty experience, and site predicted likelihood of speaking up when controlling for bravery and assertiveness. Physicians rated potential harm in common clinical scenarios lower than nurses did (7.5 vs. 8.4 on 2–10 scale; p<0.001). Some participants (12%) indicated they were unlikely to speak up despite perceiving high potential for harm in certain situations. Discussion This exploratory study found nurses and physicians differed in their harm ratings, and harm rating was a predictor of speaking up. This may partially explain persistent discrepancies between physicians and nurses in teamwork climate scores. Differing assessments of potential harms inherent in everyday practice may be a target for teamwork intervention in maternity care. PMID:22927492

  19. Exposures Resulting in Safety and Health Concerns for Child Laborers in Less Developed Countries

    Directory of Open Access Journals (Sweden)

    Derek G. Shendell

    2016-01-01

    Full Text Available Objectives. Worldwide, over 200 million children are involved in child labor, with another 20 million children subjected to forced labor, leading to acute and chronic exposures resulting in safety and health (S&H risks, plus removal from formal education and play. This review summarized S&H issues in child labor, including forced or indentured domestic labor as other sectors of child labor. Specifically, we focused on exposures leading to S&H risks. Methods. We used PubMed, Scopus, Science Direct, and Google Scholar. References were in English, published in 1990–2015, and included data focused on exposures and S&H concerns of child labor. Results. Seventy-six journal articles were identified, 67 met criteria, 57 focused on individual countries, and 10 focused on data from multiple countries (comparing 3–83 countries. Major themes of concern were physical exposures including ergonomic hazards, chemical exposure hazards, and missed education. Childhood labor, especially forced, exploitative labor, created a significant burden on child development, welfare, and S&H. Conclusions. More field researche data emphasizing longitudinal quantitative effects of exposures and S&H risks are needed. Findings warranted developing policies and educational interventions with proper monitoring and evaluation data collection, plus multiple governmental, international organization and global economic reform efforts, particularly in lower-income, less developed countries.

  20. 6. Regional Congress on Radiation Protection and Safety; 3. Iberian and Latin American Congress on Radiological Protection Societies; Regional IRPA Congress. Book of abstracts

    International Nuclear Information System (INIS)

    2003-11-01

    The 6th Regional Congress on Radiation Protection and Safety was organized by the Peruvian Radiation Protection Society and the Peruvian Institute of Nuclear Energy, held in Lima, Peru, between 9 and 13 of november of 2003. In this event, were presented 227 papers that were articulated in the following sessions: radiation natural exposure, biological effects of ionizing radiation, instruments and dosimetry, radiological emergency and accidents, occupational radiation protection, radiological protection in medical exposure, radiological environmental protection, legal aspects, standards and regulations, training, education and communication, radioactive waste management, radioactive material transport, nuclear safety and biological effects of non-ionizing radiation. (APC)

  1. Driving safety: concerns and experiences of parents of adolescent drivers with type 1 diabetes.

    Science.gov (United States)

    Cox, Daniel J; Gonder-Frederick, Linda A; Shepard, Jaclyn A; Campbell, Laura K; Vajda, Karen A

    2012-09-01

    Driving is a dangerous activity for adolescents, perhaps being even more precarious for adolescents with type 1 diabetes due to the possibility of extreme blood glucose (BG). There is no available data on adolescent driving safety concerns and type 1 diabetes. To begin addressing this issue, we surveyed parents regarding their observations and concerns. Seventy-two parents (87.5% mothers) of adolescent drivers aged 16-19 with type 1 diabetes provided analyzable data. Females comprised 36% of their adolescents, with 74% using pump therapy. In the past year, 13 and 84% of parents reported that their adolescent had experienced severe or moderate disruptive hypoglycemia, respectively. Over half (56%) of the parents reported moderate to extreme worry about how diabetes impacted their adolescent's driving, while only 21% of parents thought their adolescents had similar concerns (p = 0.037). Almost one third (31%) of parents thought their adolescent need not treat low BG until it fell below 70 mg/dL, 13% thought their adolescent could safely drive with BG below 65 mg/dL. And, 31 and 14% of parents, respectively, reported their adolescent had been in a collision or stopped by the police in the past year, which they attributed to both hypo- and hyperglycemia. Adolescents reportedly took steps to prevent hypo- and hyperglycemia while driving, but more aggressively avoided hypoglycemia (p < 0.001). While this data is limited, lacking a non-diabetic control group and randomized sample, it does suggest that driving and adolescent type 1 diabetes deserve further attention and investigation. © 2012 John Wiley & Sons A/S.

  2. Standarized radiological hazard analysis for a broad based operational safety program

    International Nuclear Information System (INIS)

    Wadman, W.W. III; Andrews, L.L.

    1992-01-01

    The Radiological hazard Analysis (RHA) Manual provides a methodology and detailed guidance for systematic analysis of radiological hazards over a broad spectrum of program functions, housed in a wide variety of facilities. Radiological programs at LANL include: research and experimentation; routine materials operations; production; non-destructive examination or testing; isotope and machine produced radiations; chemistry; and metallurgy. The RHA permits uniform evaluation of hazard types over a range of several orders of magnitude of hazard severity. The results are used to estimate risk, evaluate types and level or resource allocations, identify deficiencies, and plan corrective actions for safe working environments. 2 refs

  3. Standardized radiological hazard analysis for a broad based operational safety program

    International Nuclear Information System (INIS)

    Wadman, W. III; Andrews, L.

    1992-01-01

    The Radiological Hazard Analysis (RHA) Manual provides a methodology and detailed guidance for systematic analysis of radiological hazards over a broad spectrum of program functions, housed in a wide variety of facilities. Radiological programs at LANL include: research and experimentation routine materials operations; production; non-destructive examination or testing; isotope and machine produced radiations; chemistry; and metallurgy. The RHA permits uniform evaluation of hazard types over a range of several orders of magnitude of hazard severity. The results are used to estimate risk, evaluate types and level of resource allocations, identify deficiencies, and plan corrective actions for safe working environments. (author)

  4. Regulatory oversight report 2016 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    2017-06-01

    ENSI, the Swiss Federal Nuclear Safety Inspectorate, assesses and monitors safety in the Swiss nuclear facilities. These include the five nuclear power plants: Beznau Units 1 and 2 (KKB1 and KKB2), Muehleberg (KKM), Goesgen (KKG) and Leibstadt (KKL), the interim storage facilities based at each plant, the Central Interim Storage Facility (Zwilag) in Wuerenlingen together with the nuclear facilities at the Paul Scherrer Institute (PSI), the University of Basel (UniB) and the Federal Institute of Technology in Lausanne (EPFL). Using a combination of inspections, regulatory meetings, checks, analyses and the reporting of the operators of individual facilities, ENSI obtains the required overview of nuclear safety in these facilities. It ensures that they operate as required by law. ENSI's regulatory responsibilities also include the transport of radioactive materials from and to nuclear facilities and preparations for a deep geological repository for radioactive waste. ENSI maintains its own emergency organisation, which is an integral part of the national emergency structure that would be activated in the event of a serious incident at a nuclear facility in Switzerland. ENSI reports periodically on its supervisory activities. It informs the public about special events and findings in the nuclear installations. All five nuclear power plants in Switzerland operated safely during the past year. Nuclear safety at all plants in operation was rated as good or satisfactory. In 2016, there were 31 reportable events at the nuclear power plants. 30 events were rated Level 0 (event of no or low safety significance) on the International Nuclear and Radiological Event Scale (INES) and one was rated Level 1 (anomaly) at KKL. Zwilag consists of several interim storage buildings, a conditioning plant and a plasma plant (incineration/melting plant). At the end of 2016, the cask storage hall contained 56 transport/storage casks with spent fuel assemblies and vitrified residue

  5. Radiation safety concerns for pregnant or breast feeding patients. The positions of the NCRP and the ICRP

    International Nuclear Information System (INIS)

    Meinhold, C.B.

    1997-01-01

    For many years, protecting the fetus has been a concern of the National Council on Radiation Protection and Measurements (NCRP) and the International Commission on Radiological Protection (ICRP). Early recommendations focused on the possibility of a wide variety of detrimental developmental effects while later recommendations focused on the potential for severe mental retardation and/or reduction in the intelligence quotient (I.Q.). The latest recommendations also note that the risk of cancer for the fetus is probably two to three times greater per Sv than in the adult. For all these reasons, the NCRP and the ICRP have provided guidance to physicians on taking all reasonable steps to ascertain whether any woman requiring a radiological or nuclear medicine procedure is pregnant or nursing a child. The NCRP and the ICRP also advise the clinician to postpone such procedures until after delivery or cessation of nursing, if possible

  6. Radiation safety concerns for pregnant or breast feeding patients. The positions of the NCRP and the ICRP

    Energy Technology Data Exchange (ETDEWEB)

    Meinhold, C.B. [Brookhaven National Lab., Upton, NY (United States)

    1997-01-01

    For many years, protecting the fetus has been a concern of the National Council on Radiation Protection and Measurements (NCRP) and the International Commission on Radiological Protection (ICRP). Early recommendations focused on the possibility of a wide variety of detrimental developmental effects while later recommendations focused on the potential for severe mental retardation and/or reduction in the intelligence quotient (I.Q.). The latest recommendations also note that the risk of cancer for the fetus is probably two to three times greater per Sv than in the adult. For all these reasons, the NCRP and the ICRP have provided guidance to physicians on taking all reasonable steps to ascertain whether any woman requiring a radiological or nuclear medicine procedure is pregnant or nursing a child. The NCRP and the ICRP also advise the clinician to postpone such procedures until after delivery or cessation of nursing, if possible.

  7. Safety report concerning Melusine (after power increase to 4 MW). Descriptive part. Volumes 1 and 2

    International Nuclear Information System (INIS)

    Baas, C.; Delcroix, V.; Jacquemain, M.; Marouby, R.; Meunier, C.; De Robien, E.; Rossillon, F.

    1967-03-01

    Construction of Melusine was started in January 1957, It first diverged on July 1, 1958. It operated at: 1 MW from March 1959; 1.4 MW from April 1960; 2 MW from September 1961; 4 MW from December 1965. Various modifications have been made since the reactor was built. They concern: - the addition of a hot cell. - the effluents: 2 reservoirs of 15 m 3 for liquid waste have been installed. The resin regeneration equipment has been completely modified. - the building: offices have been added - experimental zones have been set up in the hall - the electrical supply. - the cooling and purification circuits (installation of a second exchanger, replacement of the primary pumps, creation of a hot layer, etc... ). - the fuel elements (at the moment of the MTR type enriched to 90 per cent). - the swimming-pool (which has been partially equipped with a stainless steel coating). - the core (placing of 'stools', of a diving-board, etc...). - the ventilation: the hall has been de-pressurized during normal working in the event of an accident, the hall can be isolated and a safety circuit can be started up. A chimney has been installed. - the hall (which has been strengthened and sealed more effectively). - the control electronics (modification of the principle, and which are now entirely transistorized). So many changes have been made that the reactor now bears only a slight resemblance to the initial model. It has appeared necessary to make a brief review of these improvements in order to be able to judge more effectively the installations present safety characteristics; these latter are furthermore fairly well known as a result of the experiments carried out not only by the Thermal Transfer Service in Grenoble but also at Cadarache (Cabri) and Toulon (the work of Mr. PASCOUET). (authors) [fr

  8. Food safety concerns deriving from the use of silver based food packaging materials: a case study.

    Directory of Open Access Journals (Sweden)

    Alessandra ePezzuto

    2015-10-01

    Full Text Available The formulation of innovative packaging solutions, exerting a functional antimicrobial role in slowing down food spoilage, is expected to have a significant impact on the food industry, allowing both the maintenance of food safety criteria for longer periods and the reduction of food waste. Different materials are considered able to exert the required antimicrobial activity, among which are materials containing silver. However, challenges exist in the application of silver to food contact materials due to knowledge gaps in the production of ingredients, stability of delivery systems in food matrices and health risks caused by the same properties which also offer the benefits. Aims of the present study were to test the effectiveness and suitability of two packaging systems, one of which contained silver, for packaging and storing Stracchino cheese, a typical Italian fresh cheese, and to investigate if there was any potential for consumers to be exposed to silver, via migration from the packaging to the cheese. Results did not show any significant difference in the effectiveness of the packaging systems on packaged Stracchino cheese, excluding that the active packaging systems exerted an inhibitory effect on the growth of spoilage microorganisms. Moreover, silver migrated into the cheese matrix throughout the storage time (24 days. Silver levels in cheese finally exceeded the maximum established level for the migration of a non-authorised substance through a functional barrier (Commission Regulation (EC No. 450/2009. This result poses safety concerns and strongly suggests the need for more research aimed at better characterizing the new packaging materials in terms of their potential impacts on human health and the environment.

  9. Regulatory overview report 2013 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2013 zur nuklearen Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-06-15

    The Swiss Federal Nuclear Safety Inspectorate (ENSI) acting as the regulatory body of the Swiss Federation assesses and monitors nuclear facilities in Switzerland: these include five nuclear power plants, the interim storage facilities based at each plant, the Central Interim Storage Facility (ZWILAG) at Wuerenlingen together with the nuclear facilities at the Paul Scherrer Institute (PSI) and the two universities of Basel and Lausanne. Using a combination of inspections, regulatory meetings, examinations and analyses together with reports from the licensees of individual facilities, ENSI obtains the overview required concerning nuclear safety. It ensures that the facilities comply with regulations. Its regulatory responsibilities include the transport of radioactive materials from and to nuclear facilities and the preparations for a deep geological repository for nuclear waste. ENSI maintains its own emergency organisation, an integral part of the national emergency structure. It provides the public with information on particular events in nuclear facilities. This Surveillance Report describes operational experience, systems technology, radiological protection and management in all the nuclear facilities. Generic issues relevant to all facilities such as probabilistic safety analyses are described. In 2013, the five nuclear power plants in Switzerland (Beznau Units 1 and 2, Muehleberg, Goesgen and Leibstadt) were all operated safely and had complied with their approved operating conditions. The nuclear safety at all plants was rated as being good. 34 events were reported. During operation, no reactor scrams were recorded. On the INES scale, ranging from 0-7, ENSI rated all reportable events as Level 0. The ENSI safety evaluation reflects both reportable events and the results of the approximately 460 inspections conducted during 2013. ZWILAG consists of several storage halls, a conditioning plant and a plasma plant. At the end of 2013, the cask storage hall

  10. Radiation safety knowledge of medical center radiology technologists in southern Taiwan

    Energy Technology Data Exchange (ETDEWEB)

    Su Wen-Chuan; Huang Ying-Fong; Chen Cheng-Chung; Chang Pao-Shu [Kaohsiung Medical University, Taiwan (China)

    2000-05-01

    People who live in Taiwan are getting more and more afraid of radiation. Sometimes the phobia results from distorted knowledge. Radiology technologists, in one hand, are more well-educated in radiation and, in the other hand, have more chance to expose to radiation when they are operating radiation producing medical instruments in their daily life. So we are interested in whether they have enough knowledge to protect themselves. We pick up the radiology technology board examination to make the questionnaire for this study. The population is the radiology technologists who work at department of diagnostic radiology, of radiation therapy and nuclear medicine in medical centers. Statistics is then used to see the relationship between knowledge and the factors including gender, age and career period. Based on statistics, we find out that there is significant correlation between the knowledge with age or education level. Elder or lower education level ones has worse knowledge. Continued education may be highly recommended for radiology technologists to avoid occupational radiation injury. (author)

  11. Radiation safety knowledge of medical center radiology technologists in southern Taiwan

    International Nuclear Information System (INIS)

    Su Wen-Chuan; Huang Ying-Fong; Chen Cheng-Chung; Chang Pao-Shu

    2000-01-01

    People who live in Taiwan are getting more and more afraid of radiation. Sometimes the phobia results from distorted knowledge. Radiology technologists, in one hand, are more well-educated in radiation and, in the other hand, have more chance to expose to radiation when they are operating radiation producing medical instruments in their daily life. So we are interested in whether they have enough knowledge to protect themselves. We pick up the radiology technology board examination to make the questionnaire for this study. The population is the radiology technologists who work at department of diagnostic radiology, of radiation therapy and nuclear medicine in medical centers. Statistics is then used to see the relationship between knowledge and the factors including gender, age and career period. Based on statistics, we find out that there is significant correlation between the knowledge with age or education level. Elder or lower education level ones has worse knowledge. Continued education may be highly recommended for radiology technologists to avoid occupational radiation injury. (author)

  12. Safety concerns and hidden agenda behind HPV vaccines: another generation of drug-dependent society?

    Science.gov (United States)

    Khatami, Mahin

    2016-12-01

    Analyses of data and hidden agenda behind repeated failed outcomes of cancer research and therapy, status of American health, safety concerns for HPV vaccines and future research considerations are summarized in this commentary. A closer look at cancer science reveals that highly power structure (system) in medical establishment vs. anti-system and chaos in cancer research ('medical/scientific ponzi schemes') is potent recipe for failed therapeutics that kills patients but generates huge corporate profit. American health status ranks last among other developed nations despite the highest amount that USA invests in healthcare. This is a wake-up call to make sure that the evil part of human being does not prevent the health services that the public deserves. Otherwise, 'it does not matter how many resources you have, if you don't know, or don't want to know, how to use them, they will never be enough'. Answer to cancer and improved public health is possible only by switching the current corruptive and abusive culture of 'who you know' to a culture of 'what you know'. Policy makers and professionals in decision making roles are urged to return to common sense and logics that our Forefathers used to serve the public.

  13. Safety assessments and public concern for genetically modified food products: the American view.

    Science.gov (United States)

    Harlander, Susan K

    2002-01-01

    In the relatively short time since their commercial introduction in 1996, genetically modified (GM) crops have been rapidly adopted in the United States GM crops are regulated through a coordinated framework developed in 1992 and administered by three agencies-the US Department of Agriculture (USDA) that ensures the products are safe to grow, the Environmental Protection Agency (EPA) that ensures the products are safe for the environment, and the Food and Drug Administration (FDA) that ensures the products are safe to eat. Rigorous food and environmental safety assessments must be completed before GM crops can be commercialized. Fifty-one products have been reviewed by the FDA, including several varieties of corn, soybeans, canola, cotton, rice, sugar beets, potatoes, tomatoes, squash, papaya, and flax. Because FDA considers these crops "substantially equivalent" to their conventional counterparts, no special labeling is required for GM crops in the United States and they are managed as commodities with no segregation or identity preservation. GM crops have thus made their way through commodity distribution channels into thousands of ingredients used in processed foods. It has been estimated that 70% to 85% of processed foods on supermarket shelves in the United States today contain one or more ingredients potentially derived from GM crops. The food industry and retail industry have been monitoring the opinions of their consumers on the GM issue for the past several years. Numerous independent groups have also surveyed consumer concerns about GM foods. The results of these surveys are shared and discussed here.

  14. Regulatory overview report 2014 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    2015-06-01

    The Swiss Federal Nuclear Safety Inspectorate (ENSI), acting as the regulatory body of the Swiss Federation, assesses and monitors nuclear facilities in Switzerland: the five nuclear power plants, the interim storage facilities based at each plant, the Central Interim Storage Facility (ZWILAG) at Wuerenlingen together with the nuclear facilities at the Paul Scherrer Institute (PSI), the University of Basel (UniB) and the Federal Institute of Technology in Lausanne (EPFL). Using a combination of inspections, regulatory meetings, examinations and analyses together with reports from the licensees of individual facilities, ENSI obtains the required overview of nuclear safety. It ensures that they comply with regulations. Its regulatory responsibilities include the transport of radioactive materials from and to nuclear facilities and the preparations for a deep geological repository for nuclear waste. ENSI maintains its own emergency organisation, an integral part of the national emergency structure. It provides the public with information on particular events in nuclear facilities. This Surveillance Report describes the operational experience, systems technology, radiological protection and management in all nuclear facilities. Generic issues relevant to all facilities such as probabilistic safety analyses are described. In 2014, all five nuclear power plants in Switzerland (Beznau Units I and 2, Muehleberg, Goesgen and Leibstadt) were operated safely. The nuclear safety at all plants was rated as good. 38 events were reported. There was one reactor scram at the Leibstadt nuclear power plant. On the International Event Scale (INES), ranging from 0--7, 37 events were rated as Level 0; one event was rated as INES 1: drill holes had penetrated the steel wall of the containment to secure two hand-held fire extinguishers. ZWILAG consists of several interim storage halls, a conditioning plant and a plasma plant. At the end of 2014, the cask storage hall contained 42

  15. Interim radiological safety standards and evaluation procedures for subseabed high-level waste disposal

    International Nuclear Information System (INIS)

    Klett, R.D.

    1997-06-01

    The Seabed Disposal Project (SDP) was evaluating the technical feasibility of high-level nuclear waste disposal in deep ocean sediments. Working standards were needed for risk assessments, evaluation of alternative designs, sensitivity studies, and conceptual design guidelines. This report completes a three part program to develop radiological standards for the feasibility phase of the SDP. The characteristics of subseabed disposal and how they affect the selection of standards are discussed. General radiological protection standards are reviewed, along with some new methods, and a systematic approach to developing standards is presented. The selected interim radiological standards for the SDP and the reasons for their selection are given. These standards have no legal or regulatory status and will be replaced or modified by regulatory agencies if subseabed disposal is implemented. 56 refs., 29 figs., 15 tabs

  16. Enacting laws concerning radiation safety management for students using X-rays and electron beams under 1 MeV

    International Nuclear Information System (INIS)

    Nishizawa, Kunihide; Shibata, Michihiro; Saze, Takuya

    2004-01-01

    Laws concerning radiation safety management were analyzed from the point of view of defining precisely what is meant by radiation and what is meant by the subject. There are no laws to protect students from radiation hazards when using X-rays and electron beams under 1 MeV for research and/or education. The Law concerning Technical Standards for Preventing Radiation Hazards gives the authorities the power to enact new rules and regulations that will protect the students. The Radiation Council must take charge for enactment of all laws regarding radiation safety management. (author)

  17. Regulatory oversight report 2010 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    2011-06-01

    fuel assemblies and vitrified residue packages plus 6 casks with decommissioning waste from the experimental nuclear power plant at Lucens. About 17% of the capacity of the high level waste (HLW) store was in use and about 22% of the intermediate- and low-level (ILW) store capacity. During the year ZWILAG conducted two campaigns to incinerate and melt radioactive waste. ENSI recorded no notifiable events in ZWILAG during 2010. ENSI is also responsible for the surveillance of the nuclear facilities at PSI: the research reactor PROTEUS, the hot laboratory, the collection point for radioactive waste from medicine, industry and research. From the radiological standpoint, decommissioning work at the two research reactors DIORIT and SAPHIR continued correctly. The PROTEUS research reactor was operated in compliance with regulations. There were 2 notifiable incidents at PSI with a relevance to nuclear safety and both were rated as INES Level 0. ENSI recorded no notifiable events at the two research reactors at the Federal Institute of Technology in Lausanne and the University of Basel. In 2010, the amount of radioactive material released into the environment via waste water and gaseous exhaust from the nuclear power plants, ZWILAG, the PSI and the nuclear facilities at Basel and Lausanne was considerably lower than the limits specified in operating licenses. Analyses showed that the maximum doses, including those for residents in the immediate vicinity of a plant, were less than 1 % of the annual exposure to natural radiation. Several consignments of radioactive waste were returned to Switzerland following reprocessing at La Hague in France. All consignments of fuel assemblies and radioactive waste were transported in accordance with the regulations. In 2008, three companies each submitted a general license application to the Swiss Federal Office of Energy for a new nuclear power plant. After the accident at Fukushima (Japan) in March 2011, the Swiss Federal Council suspended

  18. A cascade method of training for the revised CEGB Radiological Safety Rules and the Ionising Radiations Regulations 1985

    International Nuclear Information System (INIS)

    Jackson, J.R.; John, P.G.L.

    1986-01-01

    In order to achieve compliance with the Ionising Radiations Regulations 1985 the CEGB has introduced a revised set of Radiological Safety Rule. These Rules are for implementation at all sites under the Board's control where ionising radiations are used. It was a requirement that the new Safety Rules be brought into operation on a common date and to a consistent standard of performance throughout the industry; this necessitated a considerable training programme to familiarise and inform some 8,000 staff working at a large number of locations. The training week of identified groups of staff varied widely, according to their different levels of authority and responsibility. The paper sets out the means by which the chosen cascade method of training was selected and developed, and gives details of the modular package of training material which was produced. It also relates how the management objectives were met within the constraints of an uncompromising time schedule. (author)

  19. Radiological safety system based on real-time tritium-in-air monitoring in room and effluents

    Energy Technology Data Exchange (ETDEWEB)

    Bidica, N.; Sofalca, N.; Balteanu, O.; Stefan, I. [National Institute of Cryogenics and Isotopes Technologies, Ramnicu Valcea (Romania)

    2006-07-01

    The conceptual design of the radiological safety system based on real time-in-air monitoring in room and effluents is intended to provide the maximum achievable safety level, basing no the ALARA concept. the capabilities of this system are not only to inform any time personnel about tritium in air concentration level, but it will be able to: initiate the shut down procedure and drain off the plant, as well to start the Air cleaning System when the tritium-in-air concentration exceed pre-established threshold; estimate tritium effective dose rate before starting an activity into the monitored area, or during this activity, or soon as the activity was finished; estimate tritium effective dose and instantly record and update individual effective doses, using a special computer application called 'dose record'; lock access into the radiological area for individuals when tritium dose rate in the monitoring area will exceed the pre-established thresholds, or when any individual dose data provided by 'dose records' application ask for, or for other protection consideration; calculate the total tritium activity released to the environment (per day, week, or month). (N.C.)

  20. Radiological safety system based on real-time tritium-in-air monitoring in room and effluents

    International Nuclear Information System (INIS)

    Bidica, N.; Sofalca, N.; Balteanu, O.; Stefan, I.

    2006-01-01

    The conceptual design of the radiological safety system based on real time-in-air monitoring in room and effluents is intended to provide the maximum achievable safety level, basing no the ALARA concept. the capabilities of this system are not only to inform any time personnel about tritium in air concentration level, but it will be able to: initiate the shut down procedure and drain off the plant, as well to start the Air cleaning System when the tritium-in-air concentration exceed pre-established threshold; estimate tritium effective dose rate before starting an activity into the monitored area, or during this activity, or soon as the activity was finished; estimate tritium effective dose and instantly record and update individual effective doses, using a special computer application called 'dose record'; lock access into the radiological area for individuals when tritium dose rate in the monitoring area will exceed the pre-established thresholds, or when any individual dose data provided by 'dose records' application ask for, or for other protection consideration; calculate the total tritium activity released to the environment (per day, week, or month). (N.C.)

  1. Regulatory oversight report 2011 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    2012-06-01

    as well as 6 casks with decommissioned waste from the experimental nuclear power plant at Lucens. About 17 % of the capacity of the high-level radioactive waste store had been used and about 23 % of the low- and intermediate-level waste store. During the year, ZWILAG conducted two campaigns to incinerate and melt radioactive waste. ENSI recorded no reportable events at ZWILAG during 2011. ENSI is also responsible for the surveillance of the nuclear facilities at PSI: the research reactor PROTEUS, the hot laboratory, the collection point for radioactive waste from medicine, industry and research, and ZWILAG. From the radiological standpoint, decommissioning work at the two research reactors DIORIT and SAPHIR progressed correctly. There were no further irradiation experiments during 2011 at PROTEUS and operational activities were restricted to routine maintenance and checks. During 2011, there were three reportable events at PSI relevant to nuclear safety. All were rated as INES Level 0. ENSI recorded one reportable event at the research reactor at the Federal Institute of Technology in Lausanne and none at the University of Basel. ENSI concluded that the nuclear facilities at PSI and the research reactors at Lausanne and Basel had complied with their approved operating conditions during 2011. Last year the amount of radioactive material released into the environment via waste water and exhaust air from nuclear power plants, ZWILAG, the PSI and the nuclear facilities at Basel and Lausanne was considerably less than the limits specified in the operating licenses. They resulted in maximum calculated doses, including for those residents in the immediate vicinity of a plant, of less than 1 % of the annual exposure to natural radiation. During 2011, two consignments of compacted reprocessing waste were transported from La Hague in France to ZWILAG. The consignments of fuel assemblies and radioactive waste were transported in accordance with the limits specified in the

  2. Radiological controls and worker and public health and safety: An independent safety assessment of Department of Energy nuclear reactor facilities

    International Nuclear Information System (INIS)

    Tew, J.L.; Miles, M.E.; Knuth, D.; Boyd, R.

    1981-02-01

    DOE has formed a Nuclear Facilities Personnel Qualification and Training (NFPQT) Committee to assess the implications of the Report of the President's Commission on the Accident at Three Mile Island that are applicable to DOE's nuclear reactor operations. Thirteen DOE nuclear reactors were reviewed by the Committee. This report was prepared to provide a measure of how the radiological control and environmental practices at the 13 individual DOE reactor facilities measure up to (1) the recommendations contained in the Report of the President's Commission on the Accident at Three Mile Island, (2) the requirements and guidelines contained, and (3) the requirements of the applicable Title and Part of the Code of Federal Regulations

  3. Specialized consultant in radiological safety to the Salamanca regional hospital, PEMEX. III. - September of 2001

    International Nuclear Information System (INIS)

    Angeles C, A.; Vizuet G, J.; Benitez S, J. A.; Garcia A, J.; Rodriguez A, F.

    2002-01-01

    The Salamanca regional hospital, dependent of PEMEX, It request consultant of the ININ to be able to maintain their sanitary license for the use of X-ray equipment for the radiologic diagnostic.The proposal of the ININ was to be a program of technical attendance, schedule monthly to be able to solve the observations that are presented in the use of those equipment, and that the hospital can conserve its respective sanitary license.(Author)

  4. Specialized consultant in radiological safety to the Tula general hospital, PEMEX. VI. - December of 2001

    International Nuclear Information System (INIS)

    Angeles C, A.; Vizuet G, J.; Benitez S, J. A.; Garcia A, J.; Rodriguez A, F.

    2002-01-01

    The Tula general hospital, dependent of PEMEX, It request consultant of the ININ to be able to maintain their sanitary license for the use of X-ray equipment for the radiologic diagnostic.The proposal of the ININ was to be a program of technical attendance, schedule monthly to be able to solve the observations that are presented in the use of those equipment, and that the hospital can conserve its respective sanitary license.(Author)

  5. Specialized consultant in radiological safety to the Tula general hospital, PEMEX. IV. - October of 2001

    International Nuclear Information System (INIS)

    Angeles C, A.; Vizuet G, J.; Benitez S, J. A.; Garcia A, J.; Rodriguez A, F.

    2002-01-01

    The Tula general hospital, dependent of PEMEX, It request consultant of the ININ to be able to maintain their sanitary license for the use of X-ray equipment for the radiologic diagnostic.The proposal of the ININ was to be a program of technical attendance, schedule monthly to be able to solve the observations that are presented in the use of those equipment, and that the hospital can conserve its respective sanitary license.(Author)

  6. Specialized consultant in radiological safety to the Ciudad del Carmen general hospital, PEMEX

    International Nuclear Information System (INIS)

    Angeles C, A.; Hernandez C, J. E.; Rodriguez A, F.; Garcia A, J.

    2003-02-01

    The Ciudad del Carmen general hospital, dependent of PEMEX, It request consultant of the ININ to be able to maintain their sanitary license for the use of X-ray equipment for the radiologic diagnostic.The proposal of the ININ was to be a program of technical attendance, schedule monthly to be able to solve the observations that are presented in the use of those equipment, and that the hospital can conserve its respective sanitary license.(Author)

  7. Specialized consultant in radiological safety to the Salamanca regional hospital, PEMEX. V. - November of 2001

    International Nuclear Information System (INIS)

    Angeles C, A.; Vizuet G, J.; Benitez S, J. A.; Garcia A, J.; Rodriguez A, F.

    2002-01-01

    The Salamanca regional hospital, dependent of PEMEX, It request consultant of the ININ to be able to maintain their sanitary license for the use of X-ray equipment for the radiologic diagnostic.The proposal of the ININ was to be a program of technical attendance, schedule monthly to be able to solve the observations that are presented in the use of those equipment, and that the hospital can conserve its respective sanitary license.(Author)

  8. Specialized consultant in radiological safety to the Salamanca regional hospital, PEMEX. VI. - December of 2001

    International Nuclear Information System (INIS)

    Angeles C, A.; Vizuet G, J.; Benitez S, J. A.; Garcia A, J.; Rodriguez A, F.

    2002-01-01

    The Salamanca regional hospital, dependent of PEMEX, It request consultant of the ININ to be able to maintain their sanitary license for the use of X-ray equipment for the radiologic diagnostic.The proposal of the ININ was to be a program of technical attendance, schedule monthly to be able to solve the observations that are presented in the use of those equipment, and that the hospital can conserve its respective sanitary license.(Author)

  9. NCRP Program Area Committee 3: Nuclear and Radiological Security and Safety.

    Science.gov (United States)

    Taylor, Tammy P; Buddemeier, Brooke

    2016-02-01

    Program Area Committee (PAC) 3 provides guidance and recommendations for response to nuclear and radiological incidents of both an accidental and deliberate nature. Leadership of PAC 3 was transitioned in March 2015, and the newly composed PAC has been working to delineate and then prioritize the landscape of possible activities for PAC 3. The major activity of PAC 3 during the past year was the establishment of Scientific Committee 3-1 to begin producing a report on Guidance for Emergency Responder Dosimetry.

  10. Specialized consultant in radiological safety to the Tula general hospital, PEMEX. I.- July of 2001

    International Nuclear Information System (INIS)

    Angeles C, A.; Vizuet G, J.

    2001-09-01

    The Tula general hospital, dependent of PEMEX, It request consultant of the ININ to be able to maintain their sanitary license for the use of X-ray equipment for the radiologic diagnostic. The proposal of the ININ was to be a program of technical attendance, schedule monthly to be able to solve the observations that are presented in the use of those equipment, and that the hospital can conserve its respective sanitary license.(Author)

  11. Specialized consultant in radiological safety to the Salamanca regional hospital, PEMEX. I. - July of 2001

    International Nuclear Information System (INIS)

    Angeles C, A.; Vizuet G, J.; Benitez S, J. A.

    2001-09-01

    The Salamanca regional hospital, dependent of PEMEX, It request consultant of the ININ to be able to maintain their sanitary license for the use of X-ray equipment for the radiologic diagnostic.The proposal of the ININ was to be a program of technical attendance, schedule monthly to be able to solve the observations that are presented in the use of those equipment, and that the hospital can conserve its respective sanitary license.(Author)

  12. Specialized consultant in radiological safety to the Tula general hospital, PEMEX. II.- August of 2001

    International Nuclear Information System (INIS)

    Angeles C, A.; Vizuet G, J.; Benitez S, J. A.; Rodriguez A, F.; Garcia A, J.

    2001-10-01

    The Tula general hospital, dependent of PEMEX, It request consultant of the ININ to be able to maintain their sanitary license for the use of X-ray equipment for the radiologic diagnostic.The proposal of the ININ was to be a program of technical attendance, schedule monthly to be able to solve the observations that are presented in the use of those equipment, and that the hospital can conserve its respective sanitary license.(Author)

  13. Specialized consultant in radiological safety to the Salamanca regional hospital, PEMEX. IV. - October of 2001

    International Nuclear Information System (INIS)

    Angeles C, A.; Vizuet G, J.; Benitez S, J. A.; Garcia A, J.; Rodriguez A, F.

    2002-01-01

    The Salamanca regional hospital, dependent of PEMEX, It request consultant of the ININ to be able to maintain their sanitary license for the use of X-ray equipment for the radiologic diagnostic.The proposal of the ININ was to be a program of technical attendance, schedule monthly to be able to solve the observations that are presented in the use of those equipment, and that the hospital can conserve its respective sanitary license.(Author)

  14. Specialized consultant in radiological safety to the Salamanca regional hospital, PEMEX. II. - August of 2001

    International Nuclear Information System (INIS)

    Angeles C, A.; Vizuet G, J.; Benitez S, J. A.; Garcia A, J.; Rodriguez A, F.

    2002-01-01

    The Salamanca regional hospital, dependent of PEMEX, It request consultant of the ININ to be able to maintain their sanitary license for the use of X-ray equipment for the radiologic diagnostic.The proposal of the ININ was to be a program of technical attendance, schedule monthly to be able to solve the observations that are presented in the use of those equipment, and that the hospital can conserve its respective sanitary license.(Author)

  15. Specialized consultant in radiological safety to the Tula general hospital, PEMEX. III.- September of 2001

    International Nuclear Information System (INIS)

    Angeles C, A.; Vizuet G, J.; Benitez S, J. A.; Rodriguez A, F.; Garcia A, J.

    2001-12-01

    The Tula general hospital, dependent of PEMEX, It request consultant of the ININ to be able to maintain their sanitary license for the use of X-ray equipment for the radiologic diagnostic.The proposal of the ININ was to be a program of technical attendance, schedule monthly to be able to solve the observations that are presented in the use of those equipment, and that the hospital can conserve its respective sanitary license.(Author)

  16. Specialized consultant in radiological safety to the Tula general hospital, PEMEX. V. - November of 2001

    International Nuclear Information System (INIS)

    Angeles C, A.; Vizuet G, J.; Benitez S, J. A.; Garcia A, J.; Rodriguez A, F.

    2002-01-01

    The Tula general hospital, dependent of PEMEX, It request consultant of the ININ to be able to maintain their sanitary license for the use of X-ray equipment for the radiologic diagnostic.The proposal of the ININ was to be a program of technical attendance, schedule monthly to be able to solve the observations that are presented in the use of those equipment, and that the hospital can conserve its respective sanitary license.(Author)

  17. Radiological benchmarks for screening contaminants of potential concern for effects on aquatic biota at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    A hazardous waste site may contain hundreds of contaminants; therefore, it is important to screen contaminants of potential concern for the ecological risk assessment. Often this screening is done as part of a screening assessment, the purpose of which is to evaluate the available data, identify data gaps, and screen contaminants of potential concern. Screening may be accomplished by using a set of toxicological benchmarks. These benchmarks are helpful in determining whether contaminants warrant further assessment or are at a level that requires no further attention. Unlike exposures to chemicals, which are expressed as the concentration in water or sediment, exposures to radionuclides are expressed as the dose rate received by the organism. The recommended acceptable dose rate to natural populations of aquatic biota is 1 rad d{sup {minus}1}. Blaylock, Frank, and O`Neal provide formulas and exposure factors for estimating the dose rates to representative aquatic organisms. Those formulas were used herein to calculate the water and sediment concentrations that result in a total dose rate of 1 rad d{sup {minus}1} to fish for selected radionuclides. These radiological benchmarks are intended for use at the US Department of Energy`s (DOE`s) Oak Ridge Reservation and at the Portsmouth and Paducah gaseous diffusion plants as screening values only to show the nature and extent of contamination and identify the need for additional site-specific investigation.

  18. Radiological benchmarks for screening contaminants of potential concern for effects on aquatic biota at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1998-07-01

    A hazardous waste site may contain hundreds of contaminants; therefore, it is important to screen contaminants of potential concern for the ecological risk assessment. Often this screening is done as part of a screening assessment, the purpose of which is to evaluate the available data, identify data gaps, and screen contaminants of potential concern. Screening may be accomplished by using a set of toxicological benchmarks. These benchmarks are helpful in determining whether contaminants warrant further assessment or are at a level that requires no further attention. Unlike exposures to chemicals, which are expressed as the concentration in water or sediment, exposures to radionuclides are expressed as the dose rate received by the organism. The recommended acceptable dose rate to natural populations of aquatic biota is 1 rad d -1 . Blaylock, Frank, and O'Neal provide formulas and exposure factors for estimating the dose rates to representative aquatic organisms. Those formulas were used herein to calculate the water and sediment concentrations that result in a total dose rate of 1 rad d -1 to fish for selected radionuclides. These radiological benchmarks are intended for use at the US Department of Energy's (DOE's) Oak Ridge Reservation and at the Portsmouth and Paducah gaseous diffusion plants as screening values only to show the nature and extent of contamination and identify the need for additional site-specific investigation

  19. Proceedings of the 15th nuclear safety research association symposium ICRP's 2005 Recommendations on radiological protection

    International Nuclear Information System (INIS)

    2003-02-01

    This is the document of the Symposium in the title, held in Tokyo, 2003. The document contains the greeting by chairperson (Toshiso Kosako, International Commission of Radiological Protection (ICRP) member, Tokyo University): lecture 1; for the title subject presented as ''ICRP's 2005 Recommendations on Radiological Protection'' with its slides entitled ''The Evolution of the System of Radiological Protection-The Justification for ICRP's 2005 Recommendations'' by L.-E. Holm (ICRP Vice-Chairman, Swedish Radiation Protection Authority): lecture 2; ''Protection of the Environment: from Ethics to Genetics''' with slides, ''Ionising Radiation and the Environment'', by R. J. Pentreath (ICRP member, The University of Reading, the United Kingdom (UK)): respectively followed by discussion with 3 Japanese panelists for each lecture: and chairperson's summary. The chair's greeting is about the rise of interest in environmental radiation protection, its background, and related trends in The Organization for Economic Co-operation and Development (OECD)/Nuclear Energy Agency (NEA) Committee on Radiation Protection and Public Health (CRPPH). L-EH's presentation involves sections of the background of the recommendations and protection of the environment, mentioning some of the proposed changes in the Commission's recommendations for its 2005 Recommendations. RJP's presentation involves sections of a philosophical platform, environmental management, relevance to radiation and its effects, points of reference and discussion where the impact of radionuclides and radiation in environment on various biological systems is mentioned in view for future. (R.T.)

  20. All-terrain vehicles (ATVs) on the road: a serious traffic safety and public health concern.

    Science.gov (United States)

    Denning, Gerene; Jennissen, Charles; Harland, Karisa; Ellis, David; Buresh, Christopher

    2013-01-01

    On-road all-terrain vehicle (ATV) crashes are frequent occurrences that disproportionately impact rural communities. These crashes occur despite most states having laws restricting on-road ATV use. A number of overall risk factors for ATV-related injuries have been identified (e.g., lack of helmet, carrying passengers). However, few studies have determined the relative contribution of these and other factors to on-road crashes and injuries. The objective of our study was to determine whether there were differences between on- and off-road ATV crashes in their demographics and/or mechanisms and outcomes of injuries. Data were derived from our statewide ATV injury surveillance database (2002-2009). Crash location and crash and injury mechanisms were coded using a modification of the Department of Transportation (DOT) coding system. Descriptive analyses and statistical comparisons (chi-square test) of variables were performed. Multivariate logistic regression analysis was used to determine relative risk. 976 records were included in the final analysis, with 38 percent of the injured individuals from on-road crashes. Demographics were similar for crashes at each location, with approximately 80 percent males, 30 percent under the age of 16, and 15 percent passengers. However, females and youths under 16 were over 4 times more likely to be passengers (P ≤ 0.0001), regardless of crash location. Compared to those off-road, on-road crash victims were approximately 10 times more likely to be involved in a vehicle-vehicle collision (P road crashes were also twice as likely to test positive for alcohol as those off-road (P road victims were only half as likely to be helmeted (P road crashes involved a collision with another vehicle, suggesting that ATVs on the road represent a potential traffic safety concern. Of note, helmets were associated with reduced risk for the number and severity of brain injuries, providing further support for the importance of helmet use. Finally

  1. 75 FR 4305 - Regulatory Guidance Concerning the Applicability of the Federal Motor Carrier Safety Regulations...

    Science.gov (United States)

    2010-01-27

    ... review of, or preparation and transmission of, typed messages via wireless phones. Because of the safety... Secretary broad power in carrying out motor carrier safety statutes and regulations to ``prescribe.... Handheld or other wireless electronic devices that are brought into a CMV are considered ``additional...

  2. Food Safety as a contributor to Food Security: global policy concerns & challenges

    Directory of Open Access Journals (Sweden)

    Vijay Kumar Chattu

    2015-12-01

    Microphysical particles such as glass and metal can be hazardous and cause serious injury to consumers. Pathogenic bacteria, viruses and toxins produced by microorganisms are all possible contaminants of food and impact food safety. Like food security, food safety is also effected by poverty and climate change. Hence Foo

  3. We have to eat, right? : food safety concerns and shopping for daily vegetables in modernizing Vietnam

    NARCIS (Netherlands)

    Wertheim-Heck, S.C.O.

    2015-01-01

    This thesis analyses how people during everyday life confront real food safety risks that are difficult to influence and come to grips with and focuses on food safety risks in modernizing Vietnam.

    Over the past 40 years Vietnam has developed from war torn country with a highly centralized

  4. Radiological optimization

    International Nuclear Information System (INIS)

    Zeevaert, T.

    1998-01-01

    Radiological optimization is one of the basic principles in each radiation-protection system and it is a basic requirement in the safety standards for radiation protection in the European Communities. The objectives of the research, performed in this field at the Belgian Nuclear Research Centre SCK-CEN, are: (1) to implement the ALARA principles in activities with radiological consequences; (2) to develop methodologies for optimization techniques in decision-aiding; (3) to optimize radiological assessment models by validation and intercomparison; (4) to improve methods to assess in real time the radiological hazards in the environment in case of an accident; (5) to develop methods and programmes to assist decision-makers during a nuclear emergency; (6) to support the policy of radioactive waste management authorities in the field of radiation protection; (7) to investigate existing software programmes in the domain of multi criteria analysis. The main achievements for 1997 are given

  5. Nirex Safety Assessment Research Programme bibliography, 1990

    International Nuclear Information System (INIS)

    Cooper, M.J.

    1990-10-01

    This bibliography lists reports and papers written as part of the Nirex Safety Assessment Research Programme, which is concerned with disposal of low-level and intermediate-level waste (LLW and ILW) and associated radiological assessments. (author)

  6. Parental concern about vaccine safety in Canadian children partially immunized at age 2: a multivariable model including system level factors.

    Science.gov (United States)

    MacDonald, Shannon E; Schopflocher, Donald P; Vaudry, Wendy

    2014-01-01

    Children who begin but do not fully complete the recommended series of childhood vaccines by 2 y of age are a much larger group than those who receive no vaccines. While parents who refuse all vaccines typically express concern about vaccine safety, it is critical to determine what influences parents of 'partially' immunized children. This case-control study examined whether parental concern about vaccine safety was responsible for partial immunization, and whether other personal or system-level factors played an important role. A random sample of parents of partially and completely immunized 2 y old children were selected from a Canadian regional immunization registry and completed a postal survey assessing various personal and system-level factors. Unadjusted odds ratios (OR) and adjusted ORs (aOR) were calculated with logistic regression. While vaccine safety concern was associated with partial immunization (OR 7.338, 95% CI 4.138-13.012), other variables were more strongly associated and reduced the strength of the relationship between concern and partial immunization in multivariable analysis (aOR 2.829, 95% CI 1.151-6.957). Other important factors included perceived disease susceptibility and severity (aOR 4.629, 95% CI 2.017-10.625), residential mobility (aOR 3.908, 95% CI 2.075-7.358), daycare use (aOR 0.310, 95% CI 0.144-0.671), number of needles administered at each visit (aOR 7.734, 95% CI 2.598-23.025) and access to a regular physician (aOR 0.219, 95% CI 0.057-0.846). While concern about vaccine safety may be addressed through educational strategies, this study suggests that additional program and policy-level strategies may positively impact immunization uptake.

  7. Report of radiological safety for a micro PET; Informe de seguridad radiologica para un microPET

    Energy Technology Data Exchange (ETDEWEB)

    Gallegos M, R.; Ruiz T, C. G.; Martinez D, A.; Rodriguez V, M., E-mail: romeo@fisica.unam.m [UNAM, Instituto de Fisica, Circuito de la Investigacion Cientifica, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2010-09-15

    Considering one of the guides emitted by the National Commission of Nuclear Security and Safeguards, was realized the report of radiological safety for a micro tomography by positrons emission that is part of Bimodal System of Images developed in their entirety for personnel of the Physics Institute of UNAM. With this system is sought to obtain tomography images of small animals using non destructive methods, such as computerized micro tomography and micro tomography by positrons emission. In this work each one of the report points is enumerated and only it is described, to big features on that consist, due to the great extension of each one of them. The report has two parts; the first is denominated -Of the installation and the Organization- and is given to know the interior and external characteristics of the installation, besides how and under which authority the activities will be executed inside the laboratory. The second part is called -of the Radiological Protection- and has for objective to describe the radiation sources that will be used, as well as the measures of radiological protection foreseen inside the laboratory. The most important part in the report consists on the description of the three radionuclides to use: {sup 18}F, {sup 11}C and {sup 13}N, as well as the methods for the shielding calculation and for the estimate of the dose equivalent during the normal operation of the equipment. These methods were applied three times, because the calculation was made for each radionuclide. The results of these calculations show that: 1) it not is necessary to have a structural shielding, due to the activity sources very reduced, and 2) the dose limit per year (according to the ICRP-60) it will not be surpassed neither in the case of the occupationally exposed personnel, neither on the public in general. (Author

  8. Probabilistic consequence study of residual radiological effects from a hypothetical ten-ton inadvertent nuclear yield. Weapons Safety Program

    International Nuclear Information System (INIS)

    Harvey, T.; Peters, L.; Serduke, F.; Edwards, L.

    1994-01-01

    In this paper we study the potential radiological consequences of a strategic bomber accident, in which one of the assumed on-board nuclear weapons explodes with an arbitrarily chosen 10-ton nuclear yield. The frequency of such an occurrence is infinitesimal. The safety design features in today s nuclear weapons' systems essentially forbid its occurrence. We have a chosen a military base which has the feature of being a representative combination of urban and rural populations. The assumed ''crash site'' is near the northwest comer of the military base, close to civilian housing located just across the street from the base. A worst case wind would be from the ESE (east south east). This would cause fission debris to be dispersed toward the largest population centers and, thus, would lead to the largest Pu ''collective'' doses (i.e., a dose integrated over time and summed over individuals). Also, if an ESE wind were blowing at accident time, some people in nearby housing could receive lethal gamma-ray doses from fallout before evacuation could occur. It is assumed only one weapon undergoes nuclear yield; the other on-board weapons would HE detonate and the Pu would be aerosolized and lofted. We assume an activity-size distribution and lofting similar to those used to predict fallout measured at NTS. The main thrust of our study is to provide estimates of probabilistic radiological risks to the population local to a strategic bomber crash site. The studied radiological consequences are: cloud-passage doses from Pu inhalation; doses from groundshine due to gamma-producing radionuclides; and areal contamination from Pu and the long-lived fission products Cs-137 and Sr-90

  9. Radiological Protection of the Environment and its Implementation into IAEA Safety Standards

    Directory of Open Access Journals (Sweden)

    D. Telleria

    2013-12-01

    Full Text Available Radiological protection of the environment has been intensively discussed in recent years. Much progress has been made recently with regard to the development of models: (i to estimate the uptake of radionuclides by flora and fauna in different habitats and ecosystems; (ii to calculate internal and external exposures for a wide range of terrestrial and aquatic organisms; and (iii in investigating and analyzing the effects of radiation exposures to biota. This paper gives an overview of the current status of this work. Furthermore, the current status of the integration of environmental protection into the radiation protection system is also summarized.

  10. Toxicological and radiological safety of chicken meat irradiated with 7.5 MeV X-rays

    Science.gov (United States)

    Song, Beom-Seok; Lee, Yunjong; Park, Jong-Heum; Kim, Jae-Kyung; Park, Ha-Young; Kim, Dong-Ho; Kim, Chang-Jong; Kang, Il-Jun

    2018-03-01

    This study was conducted to evaluate the toxicological and radiological safety of chicken meat that had been irradiated at 30 kGy with 7.5 MeV X-rays. In a sub-chronic toxicity study, ICR mice were fed X-ray-irradiated chicken meat at 2500 mg/kg body weight daily for 90 days, and no mortality or abnormal clinical signs were observed throughout the study period. However, several hematological and serum biochemical parameters of the ICR mice differed significantly from those in the control group; nevertheless, the observed values were all within the normal range for the respective parameters. In addition, no toxicological effects were determined in male or female mice. Furthermore, no differences in gamma-ray spectrometric patterns were detected between the non-irradiated and irradiated samples, indicating that the radioactivity induced by 7.5 MeV X-ray irradiation was below the detection limit. These results tentatively suggest that chicken meat irradiated with 7.5 MeV X-rays would be safe for human consumption in terms of toxicology and radiology.

  11. Radiologic considerations

    International Nuclear Information System (INIS)

    Judge, L.O.

    1987-01-01

    An increasing variety of imaging modalities as well as refinements of interventional techniques have led to a resurgence of radiologic interest and participation in urolithiasis management. Judicious selection of the diagnostic examination, close monitoring during the procedure, consultation with urologic colleagues, and a careful regard for radiation safety guidelines define the role of the radiologist in renal stone disease

  12. Radiological safety and environmental surveillance during the mining and milling of beach minerals and processing of monazite

    International Nuclear Information System (INIS)

    Pillai, P.M.B.; Khan, A.H.

    2003-01-01

    This paper highlights the occupational and environmental radiological safety aspects and surveillance activities associated with mining and milling of beach minerals and processing of monazite, based on the experience gained over more than three decades of operations of the plants of Indian Rare Earths Ltd, at Chavara (Kerala), Manavalakurichi (Tamilnadu) and Udyogamandal (Kerala). The mining of beach sands, mineral separation and chemical processing of monazite for the recovery of Th and U involve occupational radiation hazards and safety problems of varying magnitudes. This part of the front end of the nuclear fuel cycle involves average per-capita occupational exposures ranging from 1.0 mSv to 8 mSv per year. The collective doses involved work out to 4.5 to 5.4 Person Sieverts per year and involve nearly 1000 radiation workers. Internal exposure contributes to nearly half of the exposure. Mechanization of the operations, process modifications, administrative controls and constant safety surveillance have over the years helped to reduce the exposures and to maintain them at levels as low as reasonably achievable (ALARA). Environmental releases resulting from the operations are well within the limits stipulated by competent authorities and exposures to public from the mining, mineral separation and monazite processing are not significant. (author)

  13. The assessment of the safety and the radiological risks associated with the transport of radioactive wastes in Romania

    International Nuclear Information System (INIS)

    Vieru, G.

    2000-01-01

    Problems related to the handling, treatment, packaging, storage, transportation, and disposal of radioactive wastes (radwastes) are very important and the responsibility for the safe management of radioactive wastes for the protection of human health and the environment has long been recognized. Safety and public welfare are to be considered within the radioactive waste management, particularly in the field of transportation because of the potential risk that it could pose to the public and to the environment. The IAEA regulations ensure safety in the transport of Radioactive Materials (RAM) by laying down detailed requirements, appropriate to the degree of hazard represented by the respective material, taking into account its form and quantity. Risk assessment provides a basis for routing radwastes and developing mitigation plans, prioritizing initiatives and enacting legislation to protect human beings and the environment. Factors such as shipment cost, distance, population exposed, environmental impacts or sensitivity, time in transit and infrastructure related issues, could be included in the terms of safety and risk. The paper presents risk assessment activities aimed to evaluate risk categories and the radiological consequences that may arise during normal (accident free) transport and those resulting from transport accidents involving waste shipments in Romania. (author)

  14. Radiological safety system based on real-time tritium-in-air monitoring indoors and in effluents

    International Nuclear Information System (INIS)

    Bidica, N.; Sofalca, N; Balteanu, O.; Srefan, I.

    2006-01-01

    Exposure to tritium is an important health hazard in any tritium processing facility so that implementing a real-time tritium monitoring system is necessary for its operation in safety conditions. The tritium processing facility operators need to be informed at any time about the in-air tritium concentration indoors or in the stack effluents, in order to detect immediately any leaks in tritium containments, or any releases inside the buildings or to the environment. This information is very important for adopting if necessary protection measures and correcting actions as quickly as possible. In this paper we describe an improved real-time tritium monitoring system designed for the Heavy Water Detritiation Pilot Plant of National Institute for Cryogenics and Isotopes Separation, Rm. Valcea, Romania. The design of the Radiological Safety System implemented for the ICIT Water Detritiation Pilot Plant is intended to provide the maximum safety level based on the ALARA concept. The main functions of tritium monitoring system are: - monitoring the working areas and gaseous effluents by determination of the tritium-in-air activity concentration; - local and remote data display; - assessing of environment dose equivalent rates and dose equivalents in the working environment (for personnel exposure control and work planning); - assessing the total tritium activity released to the environment through ventilation exhaust stack; - safety functions, i.e., local and remote, locking/unlocking personnel access, process shut-down in emergency conditions and start of the air cleaning systems. With all these features our tritium monitoring system is really a safety system adequate for personnel and environmental protection. (authors)

  15. Current regulatory developments concerning the implementation of probabilistic safety analyses for external hazards in Germany

    International Nuclear Information System (INIS)

    Krauss, Matias; Berg, Heinz-Peter

    2014-01-01

    The Federal Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU) initiated in September 2003 a comprehensive program for the revision of the national nuclear safety regulations which has been successfully completed in November 2012. These nuclear regulations take into account the current recommendations of the International Atomic Energy Agency (IAEA) and Western European Nuclear Regulators Association (WENRA). In this context, the recommendations and guidelines of the Nuclear Safety Standards Commission (KTA) and the technical documents elaborated by the respective expert group on Probabilistic Safety Analysis for Nuclear Power Plants (FAK PSA) are being updated or in the final process of completion. A main topic of the revision was the issue external hazards. As part of this process and in the light of the accident at Fukushima and the findings of the related actions resulting in safety reviews of nuclear power plants at national level in Germany and on European level, a revision of all relevant standards and documents has been made, especially the recommendations of KTA and FAK PSA. In that context, not only design issues with respect to events such as earthquakes and floods have been discussed, but also methodological issues regarding the implementation of improved probabilistic safety analyses on this topic. As a result of the revision of the KTA 2201 series 'Design of Nuclear Power Plants against Seismic Events' with their parts 1 to 6, part 1 'Principles' was published as the first standard in November 2011, followed by the revised versions of KTA 2201.2 (soil) and 2201.4 (systems and components) in 2012. The modified the standard KTA 2201.3 (structures) is expected to be issued before the end of 2013. In case of part 5 (seismic instrumentation) and part 6 (post>seismic actions) draft amendments are expected in 2013. The expert group 'Probabilistic Safety Assessments for Nuclear Power Plants' (FAK PSA) is an advisory body of the Federal

  16. Proceedings of the 15th workshop of the Mexican Society of Radiological Safety C.A

    International Nuclear Information System (INIS)

    Martinez C, T.M.C.; Garcia, L.M.

    1996-01-01

    The basic safety standards have the purpose to establish the fundamental requirements in order to protect vs. ionizing radiations derived of the risks by exposure to the radiations and to maintain the safety of the radiation sources which can generate such exposure. With base on principles thoroughly accepted, like the established for the ICRP and the IAEA, it pretend to maintain the safety of the several types of radiation sources and as complement for other standards, already established, destined to specific facilities like reactors, irradiators and radioactive waste store, regarding which they are appropriate. (author)

  17. Critical evaluation of safety and radiological protection requirements adopted for the transport of uranium and thorium ores and concentrates

    International Nuclear Information System (INIS)

    Mezrahi, Arnaldo; Crispim, Verginia R.

    2009-01-01

    This work evaluates in a critical way the safety and radiological protection recommendations established by the International Atomic Energy Agency - IAEA and adopted national and internationally, for the transport of uranium and thorium ores and concentrates, known according the transport regulations, as being of the Low Specific Activity Material Type-I, LSA-I, basing on more realistic scenarios than the presently existent, aiming at the determination of maximum exposure levels of radiation as well as the maximal contents of those materials in packages and conveyance. A general overview taking into account the scenarios foreseen by the regulations of the IAEA pointed out for a need of a better justification of the requirements edited by the Agency or should be used to support a request of revision of those regulations, national and internationally adopted, in the pertinent aspects to the transport of uranium and thorium ores and concentrates. (author)

  18. Information management system for the control of the data of the safety and radiological protection on a national scale

    International Nuclear Information System (INIS)

    Valdes Ramos, Maryzury; Prendes Alonso, Miguel; Arnau Fernadez, Alma

    2005-01-01

    The Center for Radiation Protection and Hygiene (CPHR) and the National Center for Nuclear Safety (CNSN), have been working in the last years in the design and improvement of a computing tool that allows the management of all the important information, which should be controlled by the Regulatory Authority. The results obtained with the design and implementation of the Integrated System of Data (RASSYN) for the management of the National Regulatory Authority's information in the country are shown in this paper. The software allows an efficient management of the information related to several regulatory aspects such as: the radiation sources in the national territory; the practices associated to the sources; the personnel associated to the practices and their doses; the instruments for the measurement; the waste management; the radiological events; the conditions and requirements of the given authorizations and the inspections results

  19. Safety requirements and radiological protection for ore installations; Requisitos de seguranca e protecao radiologica para instalacoes minero-industriais

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-06-15

    This norm establishes the safety and radiological protection requirements for mining installations which manipulates, process and storing ores, raw materials, steriles, slags and wastes containing radionuclides of the uranium and thorium natural series, simultaneously or separated, and which can cause undue exposures to the public and workers, at anytime of the functioning or pos operational stage. This norm applies to the mining installations activities, suspended or which have ceased their activities before the issue date of this norm, destined to the mining, physical, chemical and metallurgical processing, and the industrialization of raw materials and residues containing associated radionuclides from the natural series of uranium and thorium, including the stages of implantation, operation and decommissioning of the installation.

  20. Importance of the lower limit of detection in radiological safety; Importancia del limite inferior de deteccion en seguridad radiologica

    Energy Technology Data Exchange (ETDEWEB)

    Rafael, Terol T; Hermenegildo, Maldonado M [Comision Nacional de Seguridad Nuclear y Salvaguardias (Mexico)

    1991-07-01

    The concept of the Lower Limit of Detection (LLD) it contributes in the solution of some problems related with the radiological safety, such as the realization of the tests of flight of the sealed radioactive sources; the determination of radioisotopes in environmental samples; the estimate of present radionuclides in polluted foods; in general, the detection of small quantities of radioactive materials present in materials of use or consumption by part of the man in his daily life; as the one Lower Limit of Detection is related with topics of statistics, in this work a small review of them is made, it was superficially discussed the mensuration problems related with the establishment of the Lower Limit of Detection.

  1. The Sub-directorate of Operational Radiological Protection is an area of the CSN that oversees the safety of the workers; La Subdireccion de Proteccion Radiologica Operacional, un area del CSN que vela por la Seguridad de los trabajadores

    Energy Technology Data Exchange (ETDEWEB)

    Scialdone Garcia, A.

    2016-08-01

    The safety of radioactive facilities is an essential part of the radiological protection of the more than 100,000 workers who are professionally exposed to ionising radiations. The Sub-directorate of Operational Radiological Protection is in charge of this task and of authorising the more than 1,340 radioactive facilities that are distributed across the country and ensuring their safety. (Author)

  2. Optimization method concerning target conflicts between safety aspects and occupational safety aspects in nuclear power plant operations

    International Nuclear Information System (INIS)

    Mueller, W.

    1991-01-01

    The simplified cost-benefit analysis has not been considered for applications in nuclear engineering with complex decisions between safety aspects and occupational safety aspects. The extended cost-benefit analysis encounters problems with non-monetary criteria. Solutions are in sight, however with a subjective element. A major problem in implementing the method is the psychological barrier as against an evaluation of human life. The multi-attribute utility analysis overcomes the difficulties of the extended cost-benefit analysis, however, it also creates new problems on account of the complicated construction of the utility functions. The problems are solved most elegantly with the multi-criteria outranking analysis, the only disadvantage possibly being less transparency at first sight. (orig./HP) [de

  3. A review of the radiological safety of the ISIS accelerator - A paper prepared for the advanced reactor safety topical meeting, Orlando, Florida (USA) June 1997

    International Nuclear Information System (INIS)

    Wright, P.

    1997-01-01

    This paper describes the current radiological safety aspects of operation of ISIS accelerator components and spallation targets. Improvements in the design of a new facility with higher power are also suggested for each main component. General comments on the regulatory and organisational aspects are made. Regulation is by European Union and British Legislation. Specific ISIS components described are the ion source, linear accelerator, synchrotron, target station, experimental beam lines and radioactive materials stores. The reliability of tantalum and uranium targets is discussed. Environmental discharges of tritium and other nuclides can become a limiting factor in accelerator operation. Methods of discharge monitoring at ISIS are explained and suggestions for improvements are outlined. Waste accumulation, associated doses and costs are described. 3 refs

  4. Food Safety as a contributor to Food Security: global policy concerns & challenges

    Directory of Open Access Journals (Sweden)

    Vijay Kumar Chattu

    2015-12-01

    Full Text Available The theme for World Health Day campaign for this year 2015 is “Food safety: from farm to plate, make food safe”. The day focuses on demonstrating the importance of food safety along the whole length of the food chain in a globalized world, from production and transport, to preparation and consumption (1. Everyone needs food and needs it every day either plant sources or animal sources or both. The food we eat must be nutritious and safe but we often ignore or overlook the issue of food safety. Many cases of food borne diseases either acute poisoning or chronic exposure are largely under reported. In this globalized world, though the food chain extends over thousands of miles from different continents, an error or contamination in one country can affect the health of consumers on the other part of the world. To ensure full impact, these actions must build on principles of government stewardship, engagement of civil society, (2.According to UN, access to a safe and secure food supply is a basic human right. Food safety and food security are interrelated concepts which have an impact on the health outcomes and quality of human lives. As per Food and Agricultural Organization (FAO, Food security is a situation that exists when all people, at all times, have physical, social and economic access to sufficient, safe and nutritious food that meets their dietary needs and food preferences for an active and healthy life, (3. Based on the definition of Food security, four food security dimensions can be identified: food availability, economic and physical access to food, food utilization and stability over time. Apart from that food security is also affected by Poverty and Climate change.Food safety is an umbrella term that encompasses many aspects like food items handling, preparation and storage of food to prevent illness and injury. The other important issues are chemical, microphysical and microbiological aspects of food safety, (4. Control of

  5. Radiological protection at particle accelerators: An overview

    International Nuclear Information System (INIS)

    Thomas, R.H.

    1991-01-01

    Radiological protection began with particle accelerators. Many of the concerns in the health physics profession today were discovered at accelerator laboratories. Since the mid-1940s, our understanding has progressed through seven stages: observation of high radiation levels; shielding; development of dosimetric techniques; studies of induced activity and environmental impact; legislative and regulatory concerns; and disposal. The technical and scientific aspects of accelerator radiation safety are well in hand. In the US, there is an urgent need to move away from a ''best available technology'' philosophy to risk-based health protection standards. The newer accelerators will present interesting radiological protection issues, including copious muon production and high LET (neutron) environments

  6. Regulatory oversight report 2008 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    2009-04-01

    This annual report issued by the Swiss Federal Nuclear Inspectorate (ENSI) reports on the work carried out by the Inspectorate in 2008. This report reviews the regulatory activities in the four Swiss nuclear power stations and in four further nuclear installations in various Swiss research facilities. It deals with topics such as operational details, technologies in use, radiation protection, radioactive wastes, emergency dispositions, personnel and provides an assessment of operations from the safety point of view. Also, the transportation of nuclear materials - both nuclear fuels and nuclear wastes - is reported on. General topics discussed include probabilistic safety analyses and accident management, earthquake damage analysis and agreements on nuclear safety. The underground disposal of highly-radioactive nuclear wastes and work done in the rock laboratories are discussed, as are proposals for additional nuclear power stations

  7. The TSN bill concerning transparency and safety in the nuclear sector

    International Nuclear Information System (INIS)

    Leger, M.; Lahorgue, M.B.; Strohl, P.

    2009-01-01

    This document gathers together 3 articles whose common purpose is to shed light on the 13. June 2006 French law on transparency and safety in the nuclear sector. This law is fundamental because it gave, for the first time, the legal definitions of basic concepts like nuclear safety, public information or transparency. It also gave a series of principles on which the right in nuclear activities, has to rely: the principle of precaution, the principle of prevention, the principle of remedial action, the principle of who pollutes has to pay, and the principle of public information. The law gives also a clear scheme of the roles and responsibilities in the nuclear sector: the state, the government, the nuclear safety authority, the nuclear facility operator and the land (on which the nuclear facility stands) owner. (A.C.)

  8. Description of present practice concerning the safety criteria for nuclear power plants

    International Nuclear Information System (INIS)

    1977-01-01

    In the description at hand, the authors portray how the aims defined in the safety criteria are reached, and they make proposals for improvement. Basic principles, acceptances and requirements, with which the experts of TUeV and GRS involved in licensing procedures work at the moment, are compiled. This description of present practice has to be adapted perhaps to the existing scientific knowledge at the time. In order that an optimal behaviour as regards safety is reached by the employees in nuclear power plants, criterion 2.5 requires the following measures: the places of work and the work routine in nuclear power plants are to be organized in such a way, that they offer the conditions for the optimal behaviour of employees as regards safety. (orig./HP) [de

  9. Food Safety as a contributor to Food Security: global policy concerns & challenges

    OpenAIRE

    Vijay Kumar Chattu

    2015-01-01

    The theme for World Health Day campaign for this year 2015 is “Food safety: from farm to plate, make food safe”. The day focuses on demonstrating the importance of food safety along the whole length of the food chain in a globalized world, from production and transport, to preparation and consumption (1). Everyone needs food and needs it every day either plant sources or animal sources or both. The food we eat must be nutritious and safe but we often ignore or overlook the issue of food safet...

  10. Ensuring the nuclear safety of VVER-440 reactor pressure vessels in Skoda, Concern Enterprise, Plzen

    International Nuclear Information System (INIS)

    Hrbek, Z.

    1985-01-01

    Various types of routine inspections are described of reactor pressure vessels with the aim of identifying residual lifetime and overall safety. The inspection programme includes: choice of systems and instruments, type of tests, test frequency, safety criteria, measures to be taken in case of unsatisfactory results, documentation. The criteria are given for periodical inspections and requirements listed for instruments and equipment. The main three groups of tests are: visual inspection and dimension tests, surface inspection and volumetric inspection. Briefly described is some of the equipment used. (M.D.)

  11. Surveys of research projects concerning nuclear facility safety, financed by the Federal Ministry for the Environment, Nature Protection and Reactor Safety, 1988

    International Nuclear Information System (INIS)

    1989-11-01

    Each progress report is a collection of individual reports, categorized by subject matter. They are a documentation of the contractor's progress, rendered by themselves on standardized forms, published, for the sake of general information on progress made in investigations concerning reactor safety, by the project attendance department of the GRS. The individual reports have serial numbers. Each report includes particulars of the objective, work carried out, results obtained and plans for project continuation. (orig.) [de

  12. Surveys of research projects concerning nuclear facility safety, financed by the Federal Ministry for the Environment, Nature Protection and Reactor Safety, 1987

    International Nuclear Information System (INIS)

    1988-06-01

    Each progress report is a collection of individual reports, categorized by subject matter. They are a documentation of the contractor's progress, rendered by themselves on standardized forms, published, for the sake of general information on progress made in investigations concerning reactor safety, by the project attendance department of the GRS. The individual reports have serial numbers. Each report includes particulars of the objective, work carried out, results obtained and plans for project continuation. (orig.) [de

  13. Surveys of research projects concerning nuclear facility safety financed by the Federal Ministry for the Environment, Nature Protection and Reactor Safety, 1991

    International Nuclear Information System (INIS)

    1992-09-01

    Each progress report is a collection of individual reports, categorized by subject matter. They are a documentation of the contractor's progress, rendered by themselves on standardized forms, published, for the sake of general information on progress made in investigations concerning reactor safety, by the project attendance department of the GRS. The individual reports have serial numbers. Each report includes particulars of the objective, work carried out, results obtained and plans for project continuation. (orig.) [de

  14. Geological disposal of nuclear waste: II. From laboratory data to the safety analysis – Addressing societal concerns

    International Nuclear Information System (INIS)

    Grambow, Bernd; Bretesché, Sophie

    2014-01-01

    Highlights: • Models for repository safety can only partly be validated. • Long term risks need to be translated in the context of societal temporalities. • Social sciences need to be more strongly involved into safety assessment. - Abstract: After more than 30 years of international research and development, there is a broad technical consensus that geologic disposal of highly-radioactive waste will provide for the safety of humankind and the environment, now, and far into the future. Safety analyses have demonstrated that the risk, as measured by exposure to radiation, will be of little consequence. Still, there is not yet an operating geologic repository for highly-radioactive waste, and there remains substantial public concern about the long-term safety of geologic disposal. In these two linked papers, we argue for a stronger connection between the scientific data (paper I, Grambow et al., 2014) and the safety analysis, particularly in the context of societal expectations (paper II). In this paper (II), we assess the meaning of the technical results and derived models (paper I) for the determination of the long-term safety of a repository. We consider issues of model validity and their credibility in the context of a much broader historical, epistemological and societal context. Safety analysis is treated in its social and temporal dimensions. This perspective provides new insights into the societal dimension of scenarios and risk analysis. Surprisingly, there is certainly no direct link between increased scientific understanding and a public position for or against different strategies of nuclear waste disposal. This is not due to the public being poorly informed, but rather due to cultural cognition of expertise and historical and cultural perception of hazards to regions selected to host a geologic repository. The societal and cultural dimension does not diminish the role of science, as scientific results become even more important in distinguishing

  15. Assessment of radiological safety of some new diagnostic agents used in nuclear medicine investigations

    International Nuclear Information System (INIS)

    Gupta, M.M.; Nagaratnam, A.

    1993-01-01

    Effective dose estimations have been carried out for some newer technetium-99m labelled diagnostic agents employed for myocardial and regional cerebral perfusion studies. Mean absorbed doses due to these preparations were taken from published literature. Effective dose was calculated by multiplying mean absorbed dose to an organ or tissue by the value of tissue weighting factor assigned to that organ or tissue in the recommendations of the international Commission on Radiological Protection and integrating over all organs or tissues of interest. The process was repeated considering revised values of tissue weighting factors as recommended recently. A method for approximate effective dose calculation is described in cases where complete data on mean absorbed dose or tissue weighting factor for an organ or tissue are not available. Revised values of tissue weighting factor normally result in a lowering of estimated effective doses due to these radiopharmaceuticals. It was also demonstrated that additional total stochastic risk will only be marginal. (author)

  16. Safety report concerning the reactor Pegase - volume 1 - Description of the installation - volume 2 - Safety of the installations

    International Nuclear Information System (INIS)

    Lacour, J.

    1964-01-01

    In the first volume: This report is a description of the reactor Pegase, given with a view to examine the safety of the installations. The Cadarache site at which they are situated is briefly described, in particular because of the consequences on the techniques employed for building Pegase. A description is also given of the original aspects of the reactor. The independent loops which are designed for full-scale testing of fuel elements used in natural uranium-gas-graphite reactor systems are described in this report, together with their operational and control equipment. In the second volume: In the present report are examined the accidents which could cause damage to the Pegase reactor installation. Among possible causes of accidents considered are the seismicity of the region, an excessive power excursion of the reactor and a fracture in the sealing of an independent loop. Although all possible precautions have been taken to offset the effects of such accidents, their ultimate consequences are considered here. The importance is stressed of the security action and regulations which, added to the precautions taken for the construction, ensure the safety of the installations. (authors) [fr

  17. Current statistical tools, systems and bodies concerned with safety and accident statistics.

    NARCIS (Netherlands)

    Koornstra, M.J.

    1996-01-01

    There are a wide range of differences in the methods used nationally to classify and record road accidents. The current use of road safety information systems and the few systems available for international use are discussed. Recommendations are made for a more efficient, less costly, and improved

  18. Preclosure radiological safety assessment for the ground support system in the exploratory studies facility

    International Nuclear Information System (INIS)

    Smith, A.J.; Tsai, F.C.

    1995-01-01

    An initial probabilistic safety assessment was performed for the exploratory studies facility underground opening to determine whether the ground support system should be classified as an item important to safety. The initiating event was taken to be a rock fall in an operational facility impacting a loaded waste transporter. Rock fall probability rates were estimated from data reported by commercial mining operations. This information was retrieved from the data base compiled by the Mining Safety and Health Administration from the mandatory reporting of incidents. The statistical distribution of the rock fall magnitude was estimated from the horizontal and vertical spacing fractures measured at the Yucca Mountain repository horizon. Simple models were developed to estimate container deformation and radionuclide releases arising from the projected distribution of impacts. Accepted techniques were used to calculate atmospheric dispersion and obtain the committed dose to individuals

  19. Radiological safety considerations in the design and operation of the ORNL Transuranium Research Laboratory (TRL)

    International Nuclear Information System (INIS)

    Haynes, C.E.

    1976-01-01

    The Transuranium Research Laboratory (TRL) is the central facility at Oak Ridge National Laboratory (ORNL) for chemical and physical research involving transuranium elements. Transuranium Research Laboratory investigations are about equally divided between studies of inorganic and structural chemistry of the heavy elements and nuclear structure and properties of their isotopes. Elements studied include neptunium, plutonium, americium, curium, berkelium, californium, and einsteinium, each in microgram-to-gram quantities depending upon availability and experimental requirements. This paper describes an eight-step safety procedure followed in planning and approving individual research projects. This procedure should provide an optimum margin of safety and should permit the accomplishment of successful research

  20. Radiological error: analysis, standard setting, targeted instruction and teamworking

    International Nuclear Information System (INIS)

    FitzGerald, Richard

    2005-01-01

    Diagnostic radiology does not have objective benchmarks for acceptable levels of missed diagnoses [1]. Until now, data collection of radiological discrepancies has been very time consuming. The culture within the specialty did not encourage it. However, public concern about patient safety is increasing. There have been recent innovations in compiling radiological interpretive discrepancy rates which may facilitate radiological standard setting. However standard setting alone will not optimise radiologists' performance or patient safety. We must use these new techniques in radiological discrepancy detection to stimulate greater knowledge sharing, targeted instruction and teamworking among radiologists. Not all radiological discrepancies are errors. Radiological discrepancy programmes must not be abused as an instrument for discrediting individual radiologists. Discrepancy rates must not be distorted as a weapon in turf battles. Radiological errors may be due to many causes and are often multifactorial. A systems approach to radiological error is required. Meaningful analysis of radiological discrepancies and errors is challenging. Valid standard setting will take time. Meanwhile, we need to develop top-up training, mentoring and rehabilitation programmes. (orig.)

  1. Nuclear Safety

    International Nuclear Information System (INIS)

    1978-09-01

    In this short paper it has only been possible to deal in a rather general way with the standards of safety used in the UK nuclear industry. The record of the industry extending over at least twenty years is impressive and, indeed, unique. No other industry has been so painstaking in protection of its workers and in its avoidance of damage to the environment. Headings are: introduction; how a nuclear power station works; radiation and its effects (including reference to ICRP, the UK National Radiological Protection Board, and safety standards); typical radiation doses (natural radiation, therapy, nuclear power programme and other sources); safety of nuclear reactors - design; key questions (matters of concern which arise in the public mind); safety of operators; safety of people in the vicinity of a nuclear power station; safety of the general public; safety bodies. (U.K.)

  2. Position Paper. Safety for K-12 students: United States policy concerning LGBT student safety must provide inclusion

    Directory of Open Access Journals (Sweden)

    April Sanders

    2013-07-01

    Full Text Available Students who identify as lesbian, gay, bisexual, or transgender (LGBT are at risk for harassment due to their sexual orientation or gender identification with over 85% of LGBT students in the United States (US reporting such harassment. These statistics demonstrate one aspect of the significance of this issue, but the cost of human life in some instances has revealed another layer of importance related to a need for safety policies for LGBT students. Even though a need exists for such policies, the practice of heteronormativity found in US policymaking regarding bullying does not protect victims or curb the violence. This essay highlights several recent developments in anti-bullying policy in US schools that shows the existence of heteronormativity, which is not helping to pro-tect LGBT students. By understanding the discrimination encouraged by current policy, future policy can be better shaped to protect LGBT students.

  3. The responsible by the radiological safety in the industry. Among the labour environment and the today technology

    International Nuclear Information System (INIS)

    Adrian T, W.

    2006-01-01

    Inside the industrial applications of the sealed radioactive sources, there are clearly exist two defined branches for which these materials are used: radioactive sources used in fixed equipment and in mobile ones. These devices are used in a countless of applications and every time with more advanced technological systems. This requires a permanent improvement inside the training of the responsible one and in turn it introduces an obligatory change to other intervention groups during the useful life of the device. The accident risks to those that are associate the use of these equipment, they are errors during the operation, undue use, maintenance carried out by personal without knowledge, flaws of human type or negligence and incidents happened during the transport. All these 'risks' its are surrounded of different groups of factors that influence during the safe use of the radioactive material, inside the installation of one way or another. Then it stands out the importance of implanting aspects of 'Safety Culture', evaluations of aptitude of the responsible one for the radiological safety, introduction of improvements in aspects of quality and communication of risks, chord to what indicates the normative of the Argentine Republic and the international requirements, which will be approached in the present work. (Author)

  4. The Swedish Nuclear Power Inspectorate's Regulations concerning Safety in connection with the Disposal of Nuclear Material and Nuclear Waste. General Recommendations concerning the Application of the Swedish Nuclear Power Inspectorate's Regulations above

    International Nuclear Information System (INIS)

    2002-06-01

    An english translation of the original Swedish regulations concerning the safety in disposal of nuclear wastes is published in this booklet, together with recommendations on how these regulations can be applied

  5. Risks of drowning and safety concerns at the beaches of Karachi--perspective from lifeguards.

    Science.gov (United States)

    Shaikh, Masood Ali

    2014-05-01

    Going to beaches is a popular pastime for many people in Karachi. Lifeguards have been deployed on many beaches for the safety and protection of beachgoers. This cross-sectional survey was conducted to study the opinions and experiences of lifeguards posted at eight beaches of Karachi. Ignorance among beachgoers about how dangerous it could be at seaside, was reported by 19 (61.3%) out of 31 lifeguards interviewed. Lifeguards had to put up with verbal and physical abuse while discharging their duties, with verbal abuse being the universal experience. Improved record keeping of drowning and near-drowning data would help make better evidence-informed beach-safety decisions in Karachi for reducing the morbidity and mortality burden owing to drowning.

  6. Regulatory oversight report 2007 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    2008-04-01

    This annual report issued by the Swiss Federal Nuclear Inspectorate (HSK) reports on the work carried out by the Inspectorate in 2007. This report reviews the regulatory activities in the four Swiss nuclear power stations and in four further nuclear installations in various Swiss research facilities. It deals with topics such as operational details, technologies in use, radiation protection, radioactive wastes, emergency dispositions and personnel and provides an assessment of operations from the point of view of safety. Also, the transportation of nuclear materials - both nuclear fuels and nuclear wastes - is reported on. General topics discussed include probabilistic safety analyses and accident management. Finally, the disposal of nuclear wastes and work done in the rock laboratories in Switzerland is commented on

  7. Safety basis for selected activities in single-shell tanks with flammable gas concerns. Revision 1

    International Nuclear Information System (INIS)

    Schlosser, R.L.

    1996-01-01

    This is full revision to Revision 0 of this report. The purpose of this report is to provide a summary of analyses done to support activities performed for single-shell tanks. These activities are encompassed by the flammable gas Unreviewed Safety Question (USQ). The basic controls required to perform these activities involve the identification, elimination and/or control of ignition sources and monitoring for flammable gases. Controls are implemented through the Interim Safety Basis (ISB), IOSRs, and OSDs. Since this report only provides a historical compendium of issues and activities, it is not to be used as a basis to perform USQ screenings and evaluations. Furthermore, these analyses and others in process will be used as the basis for developing the Flammable Gas Topical Report for the ISB Upgrade

  8. Competition and safety as reflected in the legislation concerning technical supervision - are they incompatible

    International Nuclear Information System (INIS)

    Roth, H.A.

    1986-01-01

    The author discusses the conflicts between competition and safety in the legislation on technical supervision, the requirements on specific sectors, and the consequences of the concentration of the functions of technical supervision in the hands of the Technical Supervisory Board (TUEV). The demand to give more room for competition is found to have no legal basis in fundamental law. It therefore rests with the legislator to concert the one with the other. (orig./HP) [de

  9. Simulation experiments concerning functioning tests of technical safety devices with process computers. Pt. 2

    International Nuclear Information System (INIS)

    Hawickhorst, W.

    1976-12-01

    Computerized inspection techniques of engineered safety systems improve the diagnosis capability, relative to the presently used techniques, even if anticipated system disturbances can only be qualitatively predicted. To achieve this, the system to be inspected must be partitioned into small subsystems, which can be treated independently from each other. This report contains the formulation of a standardized inspection concept based on system decomposition. Its performance is discussed by means of simulation experiments. (orig.) [de

  10. Radiological safety for the public during nuclear emergencies: application of intervention levels and derived intervention levels

    International Nuclear Information System (INIS)

    Thomas, G.; Kumar, K.S.

    2006-01-01

    public from a practice is relatively small, the intervention level based on averted dose may have to be high, as significant reduction in exposure is required to justify the intervention. For intervention after a major nuclear / radiological accident, the non-radiological risk could be much larger, particularly if it is necessary to evacuate a large number of people. The variation between intervention levels for different nuclear/ radiological emergency situation could also differ quite significantly. In case of intervention, the doses received before the countermeasures are implemented should not be counted for balancing the detriment and benefit as these doses will be received whether or not the intervention is carried out. At the same time, applying the concept of averted dose involves lot of uncertainty in predicting and advising the time of intervention. The initial planning for various emergencies should include a choice of intervention levels, as discussed in this paper, in terms of averted doses, that will be justified and reasonably well optimized. Each protective action should therefore be considered on its own merits and the doses that would be incurred via all relevant pathways of exposure should also be assessed. (authors)

  11. 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)

    Dieguez, Lazaro

    2000-05-01

    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

  12. Items to be reflected to the nuclear power safety measures in Japan (concerning the examination, design and operation management) (excluding the items to be reflected to the standards)

    Energy Technology Data Exchange (ETDEWEB)

    1980-10-01

    In connection with the Three Mile Island nuclear power accident in March, 1979, in the United States, in order to introduce the lessons from it in the nuclear power safety regulations in Japan, 52 items to be reflected to the nuclear power safety measures were chosen by the Nuclear Safety Commission. Of these, 16 items were examined by the Committee on Examination of Reactor Safety. It was decided that these results would be introduced in the nuclear safety regulations, by the Nuclear Safety Commission. The following 16 items are described. For the examination, four items concerning the automatic operation of safety systems and others; for the design, five items concerning a small rupture accident, the monitoring of the state of primary coolant, control room layout and others; for the operation management, seven items concerning the inspection at the time of repair, the prevention of faulty handlings by operators and others.

  13. Items to be reflected to the nuclear power safety measures in Japan (concerning the examination, design and operation management) (excluding the items to be reflected to the standards)

    International Nuclear Information System (INIS)

    1980-01-01

    In connection with the Three Mile Island nuclear power accident in March, 1979, in the United States, in order to introduce the lessons from it in the nuclear power safety regulations in Japan, 52 items to be reflected to the nuclear power safety measures were chosen by the Nuclear Safety Commission. Of these, 16 items were examined by the Committee on Examination of Reactor Safety. It was decided that these results would be introduced in the nuclear safety regulations, by the Nuclear Safety Commission. The following 16 items are described. For the examination, four items concerning the automatic operation of safety systems and others; for the design, five items concerning a small rupture accident, the monitoring of the state of primary coolant, control room layout and others; for the operation management, seven items concerning the inspection at the time of repair, the prevention of faulty handlings by operators and others. (J.P.N.)

  14. Development of a management system of radiological safety with application to hospitals; Desarrollo de un sistema de gestion de seguridad radiologica con aplicacion a hospitales

    Energy Technology Data Exchange (ETDEWEB)

    Velazquez M, J.D.; Rivera M, T. [CICATA, IPN, Av. Legaria 694, 11500 Mexico D.F. (Mexico); Santos R, J.R. [SEPI, ESIME, IPN, 07738 Mexico D.F. (Mexico)

    2008-07-01

    The medicine is the area that more it has benefited with the implementation of the radiation. However, a great number of incidents/accidents they have happened in hospitals in recent years. The above-mentioned stands out the necessity to improve the acting of the radiological safety management systems in Hospitals. This work presents a Management System of Radiological Safety (SGSR). The SGSR has as fundamental objective the one of maintaining the radiological risks inside acceptable levels. The SGSR is generic and it can be applied in the nuclear medicine, radiodiagnostic, radiotherapy, and in other areas of the health sector where it is required to prevent accidents or incidents that affect the health or the well-being of the worker or user. Also it was diagnosed a Specialties Hospital of the Mexico City using some characteristics of the SGSR. The obtained results show that the SGSR can contribute significantly in the improvement of the quality of the service in the attention to the patients and in the radiological safety. (Author)

  15. The development of a surface hydrology model for use in radiological safety assessments

    International Nuclear Information System (INIS)

    Little, R.H.; Ashton, J.

    1991-01-01

    A detailed understanding and quantification of geosphere and biosphere water movements is vital when assessing the impact of a radioactive waste repository. Not only is water important in the transport of radionuclides from the repository into the geosphere and hence into the biosphere, but it is also important in the transport of radionuclides within the biosphere and their transport to humans. Although geosphere water fluxes have traditionally been rigorously quantified, the quantification of biosphere water fluxes has been far less rigorous. In order to redress the balance, Associated Nuclear Services Ltd (ANS) have proposed to develop a surface hydrology model for use within radiological assessments undertaken by Her Majesty's Inspectorate of Pollution (HMIP) of the United Kingdom Department of the Environment (UKDoE). It is proposed that the deterministic, lumped, quasi-physical/semi-empirical approach of conceptual models should be adopted for the model. The model will be sufficiently flexible to be applicable to a wide range of catchments, as well as a variety of temporal and spatial scales. It is envisaged that the model will have a variety of uses within the HMIP assessment methodology including the identification of significant surface hydrological processes, the provision of input data for assessment codes and the study of the biosphere-geosphere interface. (17 refs., 4 figs.)

  16. Decree No. 78/84 of 5 September 1984 regulating safety and radiological protection in mines and related ore treatment and uranium recovery

    International Nuclear Information System (INIS)

    1984-01-01

    This Decree was issued in pursuance of Decree-Law No. 426/83 of 7 December 1983 which provides that safety and radiological protection regulations shall be made for activities involving the mining of uranium and related treatment of uranium. It lays down definitions of technical radiation protection terms and sets out the requirements for permissible concentrations and internal and sets out the requirements for permissible concentrations and internal and external dose-limits for workers and members of the public. The Decree also sets up a Radiological Protection Service responsible for ensuring that the provisions of the Decree are observed. (NEA) [fr

  17. Radiological Safety Aspects of the operation of the Electron Linear Accelerator Linac CIRCE III 10 MeV

    International Nuclear Information System (INIS)

    Naceur, Ahmed

    2014-01-01

    This document is a report about safety and security for the electron accelerator Linac-CIRCE III of the National Center for Nuclear Sciences and Technologies of Tunis. The paper aims to introduce the standards of the International Atomic Energy Agency (IAEA) to the installation in question. Overall, it draws its profit from the official security reports of the IAEA. First, we study the anatomy of the accelerator by breaking it down into various compartments and examining the case of leaks that may arise. This part introduces the particularity of this installation and allows us to meet and provide procedures for some typical scenarios of mechanical malfunction. Second, we recall and adapt some theoretical concepts related to the quantification of the radioactivity, the thickness of the armoring, the utilization factor, and the quality factor. Thus, we become able to list of types of these radiations, dangers, risks and their sources. We also examine the phenomenon of compartments activation, toxic gases production (including ozone), the process of elimination, the danger associated with X-rays generated by high voltage system and the risk of electrocution. In light of this study, we handle mathematically the question of the armoring and the concept of radiation protection. Therefore, we present a practical methodology to implement a monitoring system and a technicality in the interpretation of the measurements. Finally, we discuss the practical aspect by introducing security governance to CIRCE III, and establishing a program of general, radiological and specific security. Then, we evaluate the areas of typical security, and present a comparative radiological study between the results obtained by the IAEA standards and those by the German DIN 6847 standard for direct Bremsstrahlung radiation and scattered radiation.

  18. Gender differences and demographic influences in perceived concern for driver safety and support for impaired driving countermeasures.

    Science.gov (United States)

    Butters, Jennifer; Mann, Robert E; Wickens, Christine M; Boase, Paul

    2012-12-01

    Driving safety, impaired driving, and legislation to address these concerns remain important issues. It is imperative countermeasures be targeted toward the most appropriate groups. This paper explores the potential relationship between gender and driving attitudes toward safety issues and impaired-driving countermeasures. The data are from the 2007 Impaired Driving Survey commissioned by Transport Canada and Mothers Against Drunk Driving (MADD) Canada. The survey is a, stratified by region, telephone survey of 1,514 Canadian drivers 18years of age and older with a valid driver's license who had driven within the past 30days. The findings illustrate a consistent impact of gender on these issues. Other variables were also identified as relevant factors although less consistently. Current findings suggest that strategies for building support for interventions, or for changing risk perception/concern for risky driving behaviors should be tailored by gender to maximize the potential for behavior change. This information may assist program and policy developers through the identification of more or less receptive target groups. Future research directions are also presented. Copyright © 2012 National Safety Council and Elsevier Ltd. All rights reserved.

  19. THE INFLUENCE OF MEDIA EXPOSURE, SAFETY AND HEALTH CONCERNS, AND SELF-EFFICACY ON ENVIRONMENTAL ATTITUDES TOWARDS ELECTRONIC GREEN PRODUCTS

    Directory of Open Access Journals (Sweden)

    Iman Khalid A. Qader

    2011-07-01

    Full Text Available As the high-tech industry evolves at a rapid pace, vast amounts of hazardous materials are used in fuelling its global expansion. These rapid changes in production processes are significantly depleting natural resources. With the surge of popular interest and awareness pertaining to environmental issues, organisations may be in peril if consumers' attitudes towards their products are ignored. This study intends to understand consumers' environmental attitudes towards electronic green products and to identify the effect of three factors, namely, media exposure, safety and health concerns, and self- efficacy, on this attitude. Data were collected via a self-administered questionnaire among 170 respondents in a public university. The results of the study indicated that safety and health concerns as well as self-efficacy had significant positive impacts on consumers' environmental attitudes. Surprisingly, however, media exposure did not exhibit any significant influence on consumers' environmental attitude. It is recommended that campaign and awareness projects focus on safety and health issues. Additionally, media should play a more active role in increasing environmental awareness among consumers.

  20. EURISOL-DS Multi‐MW Target: Radiological Protection, Radiation Safety and Shielding Aspects

    CERN Document Server

    Y. Romanets and R. Luís (ITN)

    The objective of this work was to carry out a detailed study and analysis of all aspects related toradioprotection and radiation safety of the spallation target area and the whole spaces reservedfor the fission targets and spallation target maintenance. Operational and no‐operationalconditions were considered for an evaluation of the radiation safety conditions.An analysis of the proposed shielding dimensions and configuration was performed for thesystem during operation time. Parameters as activation, dose rate, energy deposition, etc. aremore important for the no‐operation period, in order to evaluate the hazard level anddetermine the staff access type to the maintenance areas (direct or remote control).Such elements as the fission targets and the whole structure involved on it were studied in moredetail because of the disposal issues, after operation. Activation, dose rate and residual nuclideswere studied for each element of the assembly. All parameters were analyzed according to their...

  1. Preclosure radiological safety analysis for the exploratory shaft facilities; Yucca Mountain Site Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    Ma, C.W.; Miller, D.D.; Jardine, L.J. [Bechtel National, Inc., San Francisco, CA (United States)

    1992-06-01

    This study assesses which structures, systems, and components of the exploratory shaft facility (ESF) are important to safety when the ESF is converted to become part of the operating waste repository. The assessment follows the methodology required by DOE Procedure AP-6.10Q. Failures of the converted ESF during the preclosure period have been evaluated, along with other underground accidents, to determine the potential offsite radiation doses and associated probabilities. The assessment indicates that failures of the ESF will not result in radiation doses greater than 0.5 rem at the nearest unrestricted area boundary. Furthermore, credible accidents in other underground facilities will not result in radiation doses larger than 0.5 rem, even if any structure, system, or component of the converted ESF fails at the same time. Therefore, no structure, system, or component of the converted ESF is important to safety.

  2. Manual on radiological safety in uranium and thorium mines and mills

    International Nuclear Information System (INIS)

    1976-01-01

    The manual describes the personnel radiation hazards in uranium and thorium mines and mills. Measures which should be taken in order to protect the workers are outlined. The problems of air born radioactivity, external radiation, surface contamination and radioactive waste are treated. Safety standards in relation to the above mentioned subjects are given. An outline is given for monitoring programme. Monitoring methods, control methods and means of medical control are given

  3. Experiences in the promotion of the safety culture in radiological activities in Cuba

    International Nuclear Information System (INIS)

    Ferro, Ruben; Guillen, Alba; Ilizastigui, Fidel

    2001-01-01

    During the last decade, the need to promote and achieve high safety culture levels has been one of the priorities in the nuclear sector around the world, although it has been focused basically on nuclear power. Nevertheless, it is an important and current topic for any risk related activity, since it results in a greater involvement and commitment of managers and personnel to safety, thereby reducing the so called 'organizational failures', one of the most frequent contributors to several of the major industrial disasters in the recent years. The International Atomic Energy Agency (IAEA) has also pointed that out and in some of its recent publications and meetings has recognized the need for extending this concept to the area of radioactive source. In Cuba, the Regulatory Body has been working in this direction during several years, promoting national research and studies in this field, issuing documents and organizing events and other activities. With this it is expected to introduce new work methods and practices to be applied by management and personnel involved in the use of radioactive sources, reflecting a higher safety culture level. This paper summarizes the experience of Cuban Regulatory Body in this field. (author)

  4. Concerns related to Safety Management of Engineered Nanomaterials in research environment

    International Nuclear Information System (INIS)

    Groso, A; Meyer, Th

    2013-01-01

    Since the rise of occupational safety and health research on nanomaterials a lot of progress has been made in generating health effects and exposure data. However, when detailed quantitative risk analysis is in question, more research is needed, especially quantitative measures of workers exposure and standards to categorize toxicity/hazardousness data. In the absence of dose-response relationships and quantitative exposure measurements, control banding (CB) has been widely adopted by OHS community as a pragmatic tool in implementing a risk management strategy based on a precautionary approach. Being in charge of health and safety in a Swiss university, where nanomaterials are largely used and produced, we are also faced with the challenge related to nanomaterials' occupational safety. In this work, we discuss the field application of an in-house risk management methodology similar to CB as well as some other methodologies. The challenges and issues related to the process will be discussed. Since exact data on nanomaterials hazardousness are missing for most of the situations, we deduce that the outcome of the analysis for a particular process is essentially the same with a simple methodology that determines only exposure potential and the one taking into account the hazardousness of ENPs. It is evident that when reliable data on hazardousness factors (as surface chemistry, solubility, carcinogenicity, toxicity etc.) will be available, more differentiation will be possible in determining the risk for different materials. On the protective measures side, all CB methodologies are inclined to overprotection side, only that some of them suggest comprehensive protective/preventive measures and others remain with basic advices. The implementation and control of protective measures in research environment will also be discussed.

  5. Concerns related to Safety Management of Engineered Nanomaterials in research environment

    Science.gov (United States)

    Groso, A.; Meyer, Th

    2013-04-01

    Since the rise of occupational safety and health research on nanomaterials a lot of progress has been made in generating health effects and exposure data. However, when detailed quantitative risk analysis is in question, more research is needed, especially quantitative measures of workers exposure and standards to categorize toxicity/hazardousness data. In the absence of dose-response relationships and quantitative exposure measurements, control banding (CB) has been widely adopted by OHS community as a pragmatic tool in implementing a risk management strategy based on a precautionary approach. Being in charge of health and safety in a Swiss university, where nanomaterials are largely used and produced, we are also faced with the challenge related to nanomaterials' occupational safety. In this work, we discuss the field application of an in-house risk management methodology similar to CB as well as some other methodologies. The challenges and issues related to the process will be discussed. Since exact data on nanomaterials hazardousness are missing for most of the situations, we deduce that the outcome of the analysis for a particular process is essentially the same with a simple methodology that determines only exposure potential and the one taking into account the hazardousness of ENPs. It is evident that when reliable data on hazardousness factors (as surface chemistry, solubility, carcinogenicity, toxicity etc.) will be available, more differentiation will be possible in determining the risk for different materials. On the protective measures side, all CB methodologies are inclined to overprotection side, only that some of them suggest comprehensive protective/preventive measures and others remain with basic advices. The implementation and control of protective measures in research environment will also be discussed.

  6. Problems and concerns in radiation safety management related with decommissioning of tritium facility

    International Nuclear Information System (INIS)

    Kawano, Takao

    2005-01-01

    The tritium facility at the National Institute for Fusion Science has been closed in 2002 after decommissioning procedure. A number of works have been completed including technical measures and administrative documentations to be reported to the Ministry of Education, Culture, Sport, Science and Technology. All the operations were carried out in three successive terms; 1) survey and preparations, 2) actual decommissioning works, and 3) report of all procedures to the Minister. A valuable experience we had during this project has been summarized, and some problems have also been pointed out from a viewpoint of radiation safety management. (author)

  7. Safety

    International Nuclear Information System (INIS)

    2001-01-01

    This annual report of the Senior Inspector for the Nuclear Safety, analyses the nuclear safety at EDF for the year 1999 and proposes twelve subjects of consideration to progress. Five technical documents are also provided and discussed concerning the nuclear power plants maintenance and safety (thermal fatigue, vibration fatigue, assisted control and instrumentation of the N4 bearing, 1300 MW reactors containment and time of life of power plants). (A.L.B.)

  8. Safety concerns of herbal products and traditional Chinese herbal medicines: dehydropyrrolizidine alkaloids and aristolochic acid.

    Science.gov (United States)

    Stegelmeier, Bryan L; Brown, Ammon W; Welch, Kevin D

    2015-12-01

    In many countries, including the United States, herbal supplements, tisanes and vegetable products, including traditional Chinese medicines, are largely unregulated and their content is not registered, monitored or verified. Consequently, potent plant toxins including dehydropyrrolizidine alkaloids and other potential carcinogens can contaminate these products. As herbal and food supplement producers are left to their own means to determine the safety and purity of their products prior to marketing, disturbingly often good marketing practices currently in place are ignored and content is largely undocumented. Historical examples of poisoning and health issues relating to plant material containing dehydopyrrolizidine alkaloids and aristolochic acids were used as examples to demonstrate the risk and potential toxicity of herbal products, food supplements, or traditional medicines. More work is needed to educate consumers of the potential risk and require the industry to be more responsible to verify the content and insure the safety of their products. Published 2015. This article is a U.S. Government work and is in the public domain in the USA.

  9. Crash safety concerns for out-of-position occupant postures: A look toward safety in highly automated vehicles.

    Science.gov (United States)

    McMurry, Timothy L; Poplin, Gerald S; Shaw, Greg; Panzer, Matthew B

    2018-04-09

    Highly automated vehicle occupants will all be passengers and may be free to ride while in postures for which existing occupant safety systems such as seat belts and airbags were not originally designed. These occupants could therefore face increased risk of injury when a crash occurs. Given that current vehicles are capable of supporting a variety of occupant postures outside of the normal design position, such as reclined or turned passengers, an evaluation of current field data was performed to better understand the risks of being out of position. We investigated the frequency, demographics, and injury outcomes for out-of-position occupants using NASS-CDS. A matched analysis was performed to compare injury outcomes for out-of-position passengers with in-position drivers involved in similar crashes. Finally, case studies for out-of-position occupants were examined in the Crash Injury Research (CIREN) database. Only 0.5% of occupants in NASS-CDS with a coded posture were out of position at the time of crash. Of the out-of-position occupants, being turned or seated sideways was almost as likely as being reclined. Out-of-position occupants were younger and less likely to be belted than their in-position counterparts. Analysis of the injury data indicated a trend that being out of position was associated with an elevated risk for serious injury. However, the number of out-of-position occupants was too small to provide a definitive or statistically significant conclusion on injury outcome. Though highly automated vehicles may eventually reduce the number of crashes and traffic fatalities in the future, there will be a transition period when these vehicles remain at risk from collisions with human-driven vehicles. These crashes could cause higher than anticipated rates of injury if occupants are less likely to be belted or tend to be in positions for which restraints are not optimized. This study highlights the need for future research on occupant response and

  10. Regulatory oversight report 2012 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    2013-04-01

    The Swiss Federal Nuclear Safety Inspectorate (ENSI) assesses and monitors nuclear facilities in Switzerland. These include the five nuclear power plants, the interim storage facilities based at each plant, the Central Interim Storage Facility (ZWILAG) and the nuclear facilities at the Paul Scherrer Institute (PSI), at the Federal Institute of Technology in Lausanne (EPFL) and at the University of Basel. Using a combination of inspections, regulatory meetings, examinations and analyses together with reports from the licensees of individual facilities, ENSI obtains the required overview of nuclear safety in the relevant facilities. It ensures that the facilities comply with the regulations and operate as required by law. Its regulatory responsibilities also include the transport of radioactive materials from and to nuclear facilities and the preparations for a deep geological repository for nuclear waste. ENSI maintains its own emergency organisation. It formulates and updates its own guidelines which stipulate the criteria for evaluating the current activities and future plans of the operators of nuclear facilities. ENSI produces regular reports on its regulatory activities and nuclear safety in Swiss nuclear facilities. It fulfils its statutory obligation to provide the public with information on particular events and findings in nuclear facilities. In 2012, the five nuclear power plants in Switzerland were all operated safely. 34 events were reported; on the international INES scale of 0 to 7, ENSI rated 33 events as Level 0 and 1 as Level 1. ENSI evaluates the safety of each nuclear power plant as part of a systematic safety evaluation taking account of both reportable events and other findings, in particular the results of more than 400 inspections conducted by ENSI during 2012. ZWILAG consists of several interim storage halls, a conditioning plant and an incineration/melting plant. At the end of 2012, the cask storage hall contained 40 transport/storage casks

  11. Food Safety Concerns and other Factors Affecting Iran’s Pistachio Exports to EU, Australia, and Japan

    OpenAIRE

    Ashktorab, Niloofar; Saghaian, Sayed Hossein; Shahnoushi, Naser

    2013-01-01

    In this paper, the impact of food safety concerns on Iran’s pistachio export demand was investigated. Panel data and panel cointegration analyses were used to estimate the export demand function of Iran’s pistachio nuts to the European Union (EU), Japan, and Australia for the period of 1997 to 2006 so that the relationship between factors affecting Iran’s pistachio exports can be examined. The results show the existence of long-run relationships among the variables that have a significant imp...

  12. Safety and Security Concerns of Nurses Working in the Intensive Care Unit: A Qualitative Study.

    Science.gov (United States)

    Keys, Yolanda; Stichler, Jaynelle F

    Intensive care units (ICUs) exist to serve as a safe place for critically ill patients to receive care from skilled practitioners. In this qualitative study, ICU nurses shared their perspectives on elements that promote safety and security on their units. After obtaining institutional review board approval, participants participated in telephone interviews with a nurse researcher who has experience as a bedside ICU nurse. Five categories and 14 themes were identified and then confirmed using member checking. Results indicate that participants prefer to provide care in ICUs with no more than 12 to 14 beds and provide the following: visibility of patients and coworkers; more than 1 way to exit; and can be locked in case of emergency or threat. Nearly all respondents mentioned adequate staffing as the most important attribute of a safe, secure care environment for patients and families. More research is needed to identify design features that make the most impact on providing a safe, secure ICU environment.

  13. Assessment of regulations set up under public law concerning questions of safety technology

    International Nuclear Information System (INIS)

    Steiff, A.; Althaus, W.; Dietz, B.; Gross, H.J.; Stasiczek, M.; Salzwedel, J.; Reinhardt, M.

    1992-02-01

    A goal of the preliminary study was to assess the need for a data-processing system, to analyze the goals of such a system, to conceptualize it and examine possibilities for implementing it and to do a cost-benefit analysis of it. It serves as a means of assistance for - licensing and supervisory authorities, - the manufacturers and operators of plants, - the control institutions, - the communes, the governments of the Laender and the federal government, - trade associations and professional associations, - employers' organizations and employees' organizations in their efforts to solve problems and carry out tasks regarding safety technology. Such problems arise during the planning, construction, operation, alteration, closure and removal of plants as well as during the transport and storing of materials and goods. (orig./DG) [de

  14. Raspberry ketone in food supplements – High intake, few toxicity data – A cause for safety concern?

    DEFF Research Database (Denmark)

    Bredsdorff, Lea; Wedebye, Eva Bay; Nikolov, Nikolai Georgiev

    2015-01-01

    Raspberry ketone (4-(4-hydroxyphenyl)-2-butanone) is marketed on the Internet as a food supplement. The recommended intake is between 100 and 1400 mg per day. The substance is naturally occurring in raspberries (up to 4.3 mg/kg) and is used as a flavouring substance. Toxicological studies...... on raspberry ketone are limited to acute and subchronic studies in rats. When the lowest recommended daily dose of raspberry ketone (100 mg) as a food supplement is consumed, it is 56 times the established threshold of toxicological concern (TTC) of 1800 μg/day for Class 1 substances. The margin of safety (MOS......) based on a NOAEL of 280 mg/kg bw/day for lower weight gain in rats is 165 at 100 mg and 12 at 1400 mg. The recommended doses are a concern taking into account the TTC and MOS. Investigations of raspberry ketone in quantitative structure-activity relationship (QSAR) models indicated potential cardiotoxic...

  15. Enhancement of color and clarity in topaz and diamonds by nuclear radiation, safety and security concerns

    International Nuclear Information System (INIS)

    Shamshad Ahmed

    2009-01-01

    Inducement of color and clarity in gemstone Topaz, otherwise devoid of these attributes, has been achieved by synergistic utilization of neutron irradiation, electron beam irradiation and heat. The transformation of the colorless, cheaply available topaz into desirable deep blue topaz is a significant value addition, not achievable by other contending techniques .Likewise colorless and unclear diamonds, available in trade at throw away price, have been transformed by neutron irradiation into colored diamonds, known as fancy diamonds. The enhanced gems may possess stable or unstable colors depending on the nature of the color centers produced. In the case of blue topaz and fancy diamonds the colors produced were stable and heating at elevated temperatures can only lead to fading of colors. The enhancement of gems by neutron irradiation is commercially viable provided appropriate equipment and tools are used .In the paper are described the processes of the enhancement of topaz and diamonds along with the instrumentation involved. However, in view of the radioactivity generated as a result of the exposure of gems to the neutrons, and the likelihood of undue exposure of the users, operators etc to the radioactive gems, safety aspects command serious attention. In the paper, the strategies to avoid or to mitigate the radioactivity generated have been discussed. Also documented are the methodologies and the controls to ensure that the radioactive gems are not released before ensuring that the radioactivity, if any, in the irradiated materials is not above the permissible levels in conformity with the international standards. Safety, security and safeguard of these materials are thus appropriately addressed. (Authors)

  16. The responsible for the radiological safety in the industry. Between the environment work and the technology

    International Nuclear Information System (INIS)

    Truppa, Walter Adrian

    2005-01-01

    Within the industrial applications of sealed radioactive sources, there are two clearly defined branches for which these materials are used: radioactive sources used in fixed and mobile equipment. These devices are used in a myriad of applications and each time with more technological advanced systems. This requires a permanent improvement on the training of the responsible, and introduces a mandatory exchange to other groups of intervention during the useful life of the device. Accident risks during the use of the equipment, although its rate of occurrence is low, are related to mistakes during operation, improper use, maintenance performed by staff without knowledge, human failures or oversights and incidents occurring during transport. All these risks are surrounded by different groups of factors that influence during the safe use of radioactive material within the installation. So, it is evidenced the importance of implementing aspects of the 'Safety Culture' and evaluations of suitability of the person responsible for radiation safety. In this paper we will refer to all the concepts that surround the election of the head of radioactive material, the factors involved during the operation, their training, the obligations of the installation, and responsible for environment and the technology

  17. Training Programs on Radiological Safety for users of Ionizing Radiations in Peru; Programas de formacion en proteccion radiologica para usuarios de radiaciones ionizantes en el Peru

    Energy Technology Data Exchange (ETDEWEB)

    Medina Gironzini, E.

    2003-07-01

    In Peru, people who work with ionizing radiations must have an authorization (Individual License) as established in the Radiological Safety Regulations, which are the mandatory rules. The Technical Office of the National Authority (OTAN), which is the technical organ of the Peruvian Institute of Nuclear Energy (IPEN) in charge of controlling radiations within the country, grants the authorization after the candidate demonstrates that he/she knows the specific use of the technique using radiations, as well as the aspects related to safety and radiological protection. Since it was created in 1972, the Superior Center of Nuclear Studies (VSEN) from IPEN has carried out different training courses so that people can work safety with ionizing radiations in medicine, industry and investigation. The analysis of the radiological safety programs carried out by CSEN during the last 30 years, which allowed the training of more than 2200 people in the country and, at the same time, made possible the securing of the respective Individual License, is presented in this work. The courses, nuclear medicine, radiotherapy, industrial radiography, nuclear gauges gamma irradiator, etc..., are part of the continuous education program of CSEN. (Author)

  18. Environmental Health Impacts of Nuclear Fuel Cycle With Emphasis to Monitoring and Radiological Safety Control System

    International Nuclear Information System (INIS)

    Gad Allah, A.A.; El- Shanshory, A.I.

    2010-01-01

    facilities, as well as their health impacts instruments and monitors systems for radiological control have been reviewed and evaluated

  19. 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...

  20. Pharmaceutical quality of "party pills" raises additional safety concerns in the use of illicit recreational drugs.

    Science.gov (United States)

    Young, Simon A; Thrimawithana, Thilini R; Antia, Ushtana; Fredatovich, John D; Na, Yonky; Neale, Peter T; Roberts, Amy F; Zhou, Huanyi; Russell, Bruce

    2013-06-14

    To determine the content and release kinetics of 1-benzylpiperazine (BZP) and 1-(3-trifluoromethyl-phenyl)piperazine (TFMPP) from "party pill" formulations. From these data, the possible impact of pharmaceutical quality upon the safety of such illicit formulations may be inferred. The amount of BZP and TFMPP in party pill formulations was determined using a validated HPLC method. The in-vitro release kinetics of selected party pill brands were determined using a USP dissolution apparatus (75 rpm, 37.5 degrees Celsius). The release data were then fitted to a first order release model using PLOT software and the time taken to achieve 90% release reported. Many of the tested party pill brands contained amounts of BZP and TFMPP that varied considerably from that stated on the packaging; including considerable TFMPP content in some brands not labelled to contain this drug. Dissolution studies revealed that there was considerable variability in the release kinetics between brands; in one case 90% release required >30 minutes. Lack of quality control in party pill manufacture may have led to the toxic effects reported by users unaware of the true content and release of drug from pills. More stringent regulation in the manufacture and quality control of "new generation party pills" is essential to the harm reduction campaign.

  1. Infectious respiratory disease outbreaks and pregnancy: occupational health and safety concerns of Canadian nurses.

    Science.gov (United States)

    Phillips, Karen P; O'Sullivan, Tracey L; Dow, Darcie; Amaratunga, Carol A

    2011-04-01

    This paper is a report of a qualitative study of emergency and critical care nurses' perceptions of occupational response and preparedness during infectious respiratory disease outbreaks including severe acute respiratory syndrome (SARS) and influenza. Healthcare workers, predominantly female, face occupational and personal challenges in their roles as first responders/first receivers. Exposure to SARS or other respiratory pathogens during pregnancy represents additional occupational risk for healthcare workers. Perceptions of occupational reproductive risk during response to infectious respiratory disease outbreaks were assessed qualitatively by five focus groups comprised of 100 Canadian nurses conducted between 2005 and 2006. Occupational health and safety issues anticipated by Canadian nurses for future infectious respiratory disease outbreaks were grouped into four major themes: (1) apprehension about occupational risks to pregnant nurses; (2) unknown pregnancy risks of anti-infective therapy/prophylaxis; (3) occupational risk communication for pregnant nurses; and (4) human resource strategies required for pregnant nurses during outbreaks. The reproductive risk perceptions voiced by Canadian nurses generally were consistent with reported case reports of pregnant women infected with SARS or emerging influenza strains. Nurses' fears of fertility risks posed by exposure to infectious agents or anti-infective therapy and prophylaxis are not well supported by the literature, with the former not biologically plausible and the latter lacking sufficient data. Reproductive risk assessments should be performed for each infectious respiratory disease outbreak to provide female healthcare workers and in particular pregnant women with guidelines regarding infection control and use of anti-infective therapy and prophylaxis.

  2. Evaluation of the radiological safety of the working area in the installation of experimental fuel elements in 2010

    International Nuclear Information System (INIS)

    Nudia Barenzani

    2011-01-01

    Evaluations of radiological safety in working areas in IEBE during 2010 have been conducted. The purpose of this evaluation was to determine that the working area in IEBE is safe for workers to conducting research and development of nuclear fuel. The evaluation is done by analyzing the results of routine monitoring in the laboratory of IEBE during the year 2010, such as gamma exposure, alpha radioactivity in air and surface contamination. The result is the highest gamma exposure (3.213 ± 0.121) µSv/h at the desk-work-B in HR-05, alpha Radioactivity in air at (4.980 ± 0.444) Bq/m 3 and the average surface contamination (0.090 ± 0.008) Bq/cm 2 . The result is still above Permissible Maximum Concentration (MPC) and in the Lower Dose Limit Value established by the Regulatory Body. So it can be concluded that IEBE laboratory is safe for workers in conducting research and development nuclear fuel. (author)

  3. Radiological safety aspects associated with the handling, storage and disposal of self power neutron detectors in TAPS - 3 and 4

    International Nuclear Information System (INIS)

    Parida, B.K.; Mudgal, B.; Ghadigoankar, V.R.; Niraj; Ashok; Pati, C.K.; Patil, P.M.; Pawar, S.K.; Varadhan, R.S.

    2006-01-01

    At Tarapur Atomic Power Station 3 and 4, 540 MWe Pressurised Heavy Water Reactors, core being large in size requires a continuous in core monitoring for local flux disturbances. Nearly 200 Self Powered Neutron Detectors (SPNDs) of the Straight Individually Replaceable (SIR) type are distributed in the reactor core. For purpose of reactor regulation and protection, cobalt SPNDs that have a prompt response for changes in power is used for in-core flux mapping, vanadium SPNDs that provide accurate measure of neutron flux, even though having slow response is used In core SPNDs are placed in Vertical Flux Units (VFU) and Horizontal Flux Units (HFUs). These SPNDs were to be replaced at regular intervals to meet the design intent. Cobalt SPNDs have dose rates of the order of 1000 Gy/h and the Mineral Insulated (MI) cables of Vanadium SPNDs have dose rates of the order of 100 Gy/h. So far 3 Cobalt SPNDs were removed from HFUs and are being stored in lead shielding inside spent fuel storage facility. These high active components were handled with meticulous planning with lowest exposures to the maintainers. Radiological safety aspects of handling and storage of SPNDs are discussed in this report. (author)

  4. The responsible by the radiological safety in the industry. Between the occupational environment and the today technology

    International Nuclear Information System (INIS)

    Truppa, Walter A.

    2006-01-01

    In industrial applications of the sealed radioactive sources, there are two clearly definite branches for which these materials are utilized: radioactive sources utilized in fixed and in portable equipment. These devices are utilized in an endless number of applications and each time with more advanced technological systems. This requires a permanent improvement in the training of the responsible, and at the same time introduces an obligatory change to other intervention groups during the useful life of the device. The risks of accident, to the ones associated with the use of these equipment, though their rate of occurrence is low, they are errors during the operation, undue use, maintenance by personnel without knowledge, human type failures or carelessness and incidents occurred during the transportation. All these risks are surrounded by different groups of factors that influence during the sure use of the radioactive material inside the installation. Therefore the importance to establish aspects of Safety Culture, aptitude evaluations of the radiological security responsible, improvements introduction in quality and risks communication aspects, in agreement with the Argentine Republic regulations and the international requests, is emphasized. In the present paper all concepts about the radioactive material responsible election, the training, the factors that intervene during the operation, the installation obligations, insecurity situations and the changes or improvements that technology introduces, are referenced. (author) [es

  5. Nanotoxicity: emerging concerns regarding nanomaterial safety and occupational hard metal (WC-Co) nanoparticle exposure.

    Science.gov (United States)

    Armstead, Andrea L; Li, Bingyun

    As the number of commercial and consumer products containing engineered nanomaterials (ENMs) continually rises, the increased use and production of these ENMs presents an important toxicological concern. Although ENMs offer a number of advantages over traditional materials, their extremely small size and associated characteristics may also greatly enhance their toxic potentials. ENM exposure can occur in various consumer and industrial settings through inhalation, ingestion, or dermal routes. Although the importance of accurate ENM characterization, effective dosage metrics, and selection of appropriate cell or animal-based models are universally agreed upon as important factors in ENM research, at present, there is no "standardized" approach used to assess ENM toxicity in the research community. Of particular interest is occupational exposure to tungsten carbide cobalt (WC-Co) "dusts," composed of nano- and micro-sized particles, in hard metal manufacturing facilities and mining and drilling industries. Inhalation of WC-Co dust is known to cause "hard metal lung disease" and an increased risk of lung cancer; however, the mechanisms underlying WC-Co toxicity, the inflammatory disease state and progression to cancer are poorly understood. Herein, a discussion of ENM toxicity is followed by a review of the known literature regarding the effects of WC-Co particle exposure. The risk of WC-Co exposure in occupational settings and the updates of in vitro and in vivo studies of both micro- and nano-WC-Co particles are discussed.

  6. The role of the Health and Safety Division of DNPDE

    International Nuclear Information System (INIS)

    Arkley, J.

    1985-01-01

    The paper concerns the role of the Health and Safety Division of the Dounreay Nuclear Power Development Establishment, Scotland. Radiological conditions in the workplace; dosimetry; off-site monitoring; and accidents and emergencies, are all discussed. (U.K.)

  7. Herbal products containing Hibiscus sabdariffa L., Crataegus spp., and Panax spp.: Labeling and safety concerns.

    Science.gov (United States)

    Nunes, Maria Antónia; Rodrigues, Francisca; Alves, Rita C; Oliveira, Maria Beatriz P P

    2017-10-01

    Herbs have been used from ancient times for infusion preparation based on their potential health effects. In particular, the consumption of Hibiscus sabdariffa L., Crataegus spp. and Panax spp. has been largely associated to cardiovascular benefits. In this work, the label information of 52 herbal products for infusion preparation containing the referred herbs was analyzed and discussed, taking into consideration the European Union regulation for herbal products, which intends to protect public health and harmonize the legal framework in Member States. Details about the cardiovascular-related statements and warning notifications about consumption were considered. Also, regulatory issues and possible herb-drug interactions were explored and discussed. A total of 14 of the 52 herbal products selected presented health claims/statements on the label. Hibiscus was present in the majority of the products and, in some cases, it was mentioned only in the ingredients list and not on the product front-of-pack. Despite the promising outcomes of these plants to modulate cardiovascular risk markers, consumers with some sort of cardiovascular dysfunction and/or under medication treatments should be aware to carefully analyze the labels and consult additional information related to these herbal products. Manufacturers have also a huge responsibility to inform consumers by presenting awareness statements. Lastly, health professionals must advise and alert their patients about possible interactions that could occur between the concomitant consumption of drugs and herbs. Overall, there is still a real need of additional studies and clinical trials to better understand herbs effects and establish a science-based guidance to assess their safety. Copyright © 2017 Elsevier Ltd. All rights reserved.

  8. Course of radiological protection and safety in the medical diagnostic with X-rays; Curso de proteccion y seguridad radiologica en el diagnostico medico con rayos X

    Energy Technology Data Exchange (ETDEWEB)

    Dominguez A, C.E. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    1997-07-01

    The obtention of images of human body to the medical diagnostic is one of the more old and generalized applications for X-ray. Therefore the design and performance of equipment and installations as well as the operation procedures must be oriented toward safety with the purpose to guarantee this radiological practice will bring a net positive benefit to the society. Given that in Mexico only exists the standardization related to source and equipment generators of ionizing radiation in the industrial area and medical therapy, but not so to the medical diagnostic area it is the purpose of this work to present those standards related with this application branch. Also it is presented the preparation of a manual for the course named Formation of teachers in radiological protection and safety in the X-ray medical diagnostic in 1997 which was imparted at ININ. (Author)

  9. A safety concern related to CANDU moderator subcooling and status of KAERI moderator circulation test (MCT) experiments

    International Nuclear Information System (INIS)

    Rhee, Bo W.; Kim, Hyoung T.; Kim, Tongbeum; Im, Sunghyuk

    2015-01-01

    The flow inside the moderator tank of a CANDU-6 reactor during full power steady state operation has been suspected to be operating in the buoyancy/inertial driven mixed convection regime as illustrated in the middle figure. At some regions of the moderator tank where the buoyancy driven upward flow and the inertial momentum driven downward flows interface counter-currently, there exist some interface regions between these two flows like the middle one, and the local temperatures at these interface regions are known to oscillate with different amplitude at various fluctuation frequencies as shown. According to a numerical simulation of the moderator flow and temperature distribution at full power steady state carried out by previous researches showed that any small disturbances in the flow or temperature may initiate the system unstable and aggravate the asymmetric flow and temperature patterns. The tests at the 3-D Moderator Test Facility (MTF) that is a representative scaled-down of CANDU reactors, reproduced the expected and observed moderator behavior in the reactor as well as the local temperature fluctuations arising from the delicate balance of forced and buoyancy induced flow. This observation raised a safety concern as the local moderator temperature at some regions showed fluctuations with an amplitude that may jeopardize the safety margin, i.e. the difference between the available subcooling and the subcooling requirement. The scope of this paper is to review the basis of the safety concern related to this moderator subcooling and local temperature fluctuation and describe the current status of MCT erection and some of the experiments carried so far

  10. Radiological and environmental safety aspects of uranium fuel fabrication plants at Nuclear Fuel Complex, Hyderabad

    International Nuclear Information System (INIS)

    Viswanathan, S.; Surya Rao, B.; Lakshmanan, A.R.; Krishna Rao, T.

    1991-01-01

    Nuclear Fuel Complex, Hyderabad manufactures uranium dioxide fuel assemblies for PHWRs and BWRs operating in India. Starting materials are magnesium diuranate received from UCIL, Jaduguda and imported UF. Both of these are converted to UO 2 pellets by identical chemical processes and mechanical compacting. Since the uranium handled here is free of daughter product activities, external radiation is not a problem. Inhalation of airborne U compounds is one of the main source of exposure. Engineered protective measures like enclosures around U bearing powder handling equipment and local exhausts reduce worker's exposure. Installation of pre-filters, wet rotoclones and electrostatic precipitators in the ventillation system reduces the release of U into the environment. The criticality hazard in handling slightly enriched uranium is very low due to the built-in control based on geometry and inventory. Where airborne uranium is significant, workers are provided with protective respirators. The workers are regularly monitored for external exposure and also for internal exposure. The environmental releases from the NFC facility is well controlled. Soil, water and air from the NFC environment are routinely collected and analysed for all the possible pollutants. The paper describes the Health Physics experience during the last five years on occupational exposures and on environmental surveillance which reveals the high quality of safety observed in our nuclear fuel fabricating installations. (author). 4 refs., 6 tabs

  11. Nanotoxicity: emerging concerns regarding nanomaterial safety and occupational hard metal (WC-Co nanoparticle exposure

    Directory of Open Access Journals (Sweden)

    Armstead AL

    2016-12-01

    Full Text Available Andrea L Armstead,1,2 Bingyun Li1–3 1Department of Orthopaedics, School of Medicine, 2School of Pharmacy, West Virginia University, 3Mary Babb Randolph Cancer Center, Morgantown, WV, USA Abstract: As the number of commercial and consumer products containing engineered nanomaterials (ENMs continually rises, the increased use and production of these ENMs presents an important toxicological concern. Although ENMs offer a number of advantages over traditional materials, their extremely small size and associated characteristics may also greatly enhance their toxic potentials. ENM exposure can occur in various consumer and industrial settings through inhalation, ingestion, or dermal routes. Although the importance of accurate ENM characterization, effective dosage metrics, and selection of appropriate cell or animal-based models are universally agreed upon as important factors in ENM research, at present, there is no “standardized” approach used to assess ENM toxicity in the research community. Of particular interest is occupational exposure to tungsten carbide cobalt (WC-Co “dusts,” composed of nano- and micro-sized particles, in hard metal manufacturing facilities and mining and drilling industries. Inhalation of WC-Co dust is known to cause “hard metal lung disease” and an increased risk of lung cancer; however, the mechanisms underlying WC-Co toxicity, the inflammatory disease state and progression to cancer are poorly understood. Herein, a discussion of ENM toxicity is followed by a review of the known literature regarding the effects of WC-Co particle exposure. The risk of WC-Co exposure in occupational settings and the updates of in vitro and in vivo studies of both micro- and nano-WC-Co particles are discussed. Keywords: engineered nanomaterial, occupational exposure, lung disease, cancer, toxicity, particle

  12. Assessments of global drivers of vaccine hesitancy in 2014-Looking beyond safety concerns.

    Directory of Open Access Journals (Sweden)

    Melanie Marti

    Full Text Available Vaccine hesitancy has become the focus of growing attention and concern globally despite overwhelming evidence of the value of vaccines in preventing disease and saving the lives of millions of individuals every year. Measuring vaccine hesitancy and its determinants worldwide is important in order to understand the scope of the problem and for the development of evidence-based targeted strategies to reduce hesitancy. Two indicators to assess vaccine hesitancy were developed to capture its nature and scope at the national and subnational level to collect data in 2014: 1 The top 3 reasons for not accepting vaccines according to the national schedule in the past year and whether the response was opinion- or assessment-based and 2 Whether an assessment (or measurement of the level of confidence in vaccination had taken place at national or subnational level in the previous 5 years. The most frequently cited reasons for vaccine hesitancy globally related to (1 the risk-benefit of vaccines, (2 knowledge and awareness issues, (3 religious, cultural, gender or socio-economic factors. Major issues were fear of side effects, distrust in vaccination and lack of information on immunization or immunization services. The analysis revealed that 29% of all countries had done an assessment of the level of confidence in their country, suggesting that vaccine confidence was an issue of importance. Monitoring vaccine hesitancy is critical because of its influence on the success of immunization programs. To our knowledge, the proposed indicators provide the first global snapshot of reasons driving vaccine hesitancy and depicting its widespread nature, as well as the extent of assessments conducted by countries.

  13. Who was concerned about radiation, food safety, and natural disasters after the great East Japan earthquake and Fukushima catastrophe? A nationwide cross-sectional survey in 2012.

    Science.gov (United States)

    Sugimoto, Takashi; Shinozaki, Tomohiro; Naruse, Takashi; Miyamoto, Yuki

    2014-01-01

    Disaster-related concerns by sub-populations have not been clarified after the great East Japan earthquake and the Fukushima nuclear power plant incidents. This paper assesses who was concerned about radiation, food safety, and natural disasters among the general population in order to buffer such concerns effectively. The hypothesis that women, parents, and family caregivers were most concerned about radiation, food safety, and natural disaster was tested using a varying-intercept multivariable logistic regression with 5809 responses from a nationwide cross-sectional survey random-sampled in March 2012. Many people were at least occasionally concerned about radiation (53.5%), food safety (47.3%), and about natural disaster (69.5%). Women were more concerned than men about radiation (OR = 1.67; 95% CI = 1.35-2.06), food safety (1.70; 1.38-2.10), and natural disasters (1.74; 1.39-2.19). Parents and family care needs were not significant. Married couples were more concerned about radiation (1.53; 1.33-1.77), food safety (1.38; 1.20-1.59), and natural disasters (1.30; 1.12-1.52). Age, child-cohabitation, college-completion, retirement status, homemaker status, and the house-damage certificate of the last disaster were also associated with at least one concern. Participants from the Kanto region were more concerned about radiation (2.08; 1.58-2.74) and food safety (1.30; 1.07-1.59), which demonstrate similar positive associations to participants from Tohoku where a disaster relief act was invoked (3.36; 2.25-5.01 about radiation, 1.49; 1.08-2.06 about food safety). Sectioning the populations by gender and other demographics will clarify prospective targets for interventions, allow for a better understanding of post-disaster concerns, and help communicate relevant information effectively.

  14. Regulatory oversight report 2015 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2015 zur nuklearen Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2016-06-15

    The Swiss Federal Nuclear Safety Inspectorate (ENSI) assesses and monitors nuclear facilities in Switzerland. These include the five nuclear power plants (Beznau Units 1 and 2, Muehleberg, Goesgen and Leibstadt), the interim storage facilities based at each plant, the Central Interim Storage Facility (Zwilag) at Wuerenlingen together with the nuclear facilities at the Paul Scherrer Institute (PSI), the University of Basel and the Federal Institute of Technology in Lausanne (EPFL), as well as the transport of radioactive materials and the preparatory work for a deep geological repository for nuclear waste. Using a combination of inspections, regulatory meetings, examinations and analyses together with reports from the licensees of individual facilities, ENSI obtains the required overview of nuclear safety in these facilities. ENSI maintains its own emergency organization. It provides the public with information on particular events and findings in nuclear facilities. ENSI publishes an annual Radiological Protection Report and a Research and Experience Report. Chapters 1 to 4 of this Surveillance Report deal with operational experience, systems technology, radiological protection and management of the 5 Swiss nuclear power plants. Chapter 5 deals with Zwilag. Chapters 6 and 7 are devoted to the nuclear facilities at PSI and the research reactor at EPFL as well as the decommissioned University of Basel’s research reactor. Chapter 8 covers the transport of radioactive materials. The subject of Chapter 9 is the deep geological storage of radioactive waste including work within the framework of the Sectoral Plan. Finally, Chapter 10 deals with generic issues relevant to all facilities such as probabilistic safety analyses. In 2015, all five nuclear power plants in Switzerland were safely operated and ENSI concluded that each had adhered to its approved operating conditions. There were 34 reportable events at the nuclear power plants; 32 events were rated at Level 0 on

  15. Pediatric radiology for medical-technical radiology assistants/radiologists

    International Nuclear Information System (INIS)

    Oppelt, Birgit

    2010-01-01

    The book on pediatric radiology includes the following chapter: differences between adults and children; psycho-social aspects concerning the patient child in radiology; relevant radiation doses in radiology; help for self-help: simple phantoms for image quality estimation in pediatric radiology; general information; immobilization of the patient; pediatric features for radiological settings; traumatology; contrast agents; biomedical radiography; computerized tomography; NMR imaging; diagnostic ultrasonography; handling of stress practical recommendations; medical displays.

  16. Mobilization suited for each radiological emergency

    International Nuclear Information System (INIS)

    Chambrette, V.

    2013-01-01

    This poster presents the role played by IRSN (French Institute for Radiation protection and Nuclear Safety) in case of radiological alert. This alert can be sent by the administration, a fire brigade, a nuclear operator or a remote monitor of radioactivity. In case of an emergency situation: IRSN provides radiological intervention and assistance on the site. In case of national crisis organization, IRSN will implement the emergency technical center and will send a mobile cell to the Operational Command Station of the Prefecture concerned. In both cases IRSN will be in charge of assessing the individuals' exposure and the impact on the environment

  17. Posiva's application for a decision in principle concerning a disposal facility for spent nuclear fuel. STUK's statement and preliminary safety appraisal

    International Nuclear Information System (INIS)

    Ruokola, E.

    2000-03-01

    In May 1999, Posiva Ltd submitted to the Government an application, pursuant to the Nuclear Energy Act, for a Decision in Principle on a disposal facility for spent nuclear fuel from the Finnish nuclear power plants. The Ministry of Trade and Industry requested the Radiation and Nuclear Safety Authority (STUK) to draw up a preliminary safety appraisal concerning the proposed disposal facility. In the beginning of this report, STUK's statement to the Ministry and Industry concerning the proposed disposal facility is given. In that statement, STUK concludes that the Decision in Principle is currently justified from the standpoint of safety. The statement is followed by a safety appraisal, where STUK deems, how the proposed disposal concept, site and facility comply with the safety requirements included in the Government's Decision (478/1999). STUK's preliminary safety appraisal was supported by contributions from a number of outside experts. A collective opinion by an international group of ten distinguished experts is appended to this report. (orig.)

  18. Cause for Concern: A Mixed-Methods Study of Campus Safety and Security Practices in United States-Mexico Border Institutions of Higher Education

    Science.gov (United States)

    Holmes, Ryan Clevis

    2014-01-01

    Campus safety has been a source of concern since the 1990s. However, in 2007, the tragedy at the Virginia Polytechnic and State University sent a sense of alarm through many institutions of higher education. Immediately following this tragedy, institutions across the country began to evaluate and question their safety and security practices. While…

  19. Lumbar epidural catheter placement in the presence of low back tattoos: a review of the safety concerns.

    Science.gov (United States)

    Welliver, Dawn; Welliver, Mark; Carroll, Tammy; James, Peggy

    2010-06-01

    Current fashion in body art includes low back tattoos of varying designs and colors, a trend that presents unique concerns for anesthesia providers. Does the placement of epidural catheters risk the introduction of tattoo pigment dyes into the epidural space through the process of coring? Are there specific risks associated with tattoo dyes and epidural needle placement? We performed a comprehensive review of the literature using multiple search databases with the intent to form guidelines for practice using a level of evidence taxonomy. The available evidence does not identify any specific risks associated with epidural catheter placement through low back tattoos, although tissue coring with tissue transport to deeper sites has been confirmed. Continued investigation is necessary before comprehensive practice guidelines regarding the practice of placing epidural needles and catheters through lumbar tattoos can be developed. We suggest avoidance of piercing tattoos when performing epidural punctures until there is sound evidence of short-term and long-term safety.

  20. Atmospheric dispersion modeling and radiological safety analysis for a hypothetical accident of Ghana Research Reactor -1 (GHARR-1)

    International Nuclear Information System (INIS)

    Lunguya, J. M.

    2013-06-01

    This work presents the environmental impact analysis of some selected radionuclides released from the Ghana Research Reactor- 1 (GHARR-1) after a hypothetical postulated accidents scenario. The source term was identified and generated from an inventory of radioisotopes released during the accident. Atmospheric transport model was then applied to calculate the total effective dose and how it would be distributed to different organs of the human body as a function of distance downwind. All accident scenarios were selected from GHARR-1 Safety Analysis Report. After the source term was identified the MCNPX code was used to perform the core burnup/depletion analysis. The assumption was made that the activities were released to the atmosphere under a horse design basis accident scenario. The gaussian dose calculation method was applied, coded in Hotspot, a Healthy Physics computer code. This served as the computational tool to perform the atmospheric dispersion modeling and was used to calculate radionuclide concentration at downwind location. Based upon predominant meteorological conditions at the site, the adopted strategy was to use site-specific meteorological data and dispersion modeling to analyze the hypothetical release to the environment of radionuclides and evaluate to what extent such a release may have radiological effects on the public. Final data were processed and presented as Total Effective Dose Equivalent as a function of time and distance of deposition. The results indicate that all the values of Effective dose obtained are far below the regulatory limits, making the use of the reactor safe, even in the case of worst accident scenario where all the fission products were released into the atmosphere. (au)