WorldWideScience

Sample records for current nuclear safety

  1. Analysis of Current Global Nuclear Safety and Security Cooperation

    Institute of Scientific and Technical Information of China (English)

    Liu; Chong

    2014-01-01

    Last year, global nuclear security and safety cooperation achieved some progress. In terms of nuclear safety, too many flaws are exposed by the current severe situation of the Fukushima in Japan’s new nuclear safety regulation system, and sound the alarm for East Asia countries accelerating the regional nuclear safety cooperation. In terms of nuclear security, since the Seoul Summit in March 2012, global nuclear security cooperation has achieved new successes. IAEA has and would play the central role in pushing forward the international framework and strengthening nuclear security globally. However, there are still some obstacles to overcome in the future, which need international society to enhance communication and common understanding, especially high-level consultations.

  2. Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1989-01-01

    This document is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  3. Nuclear criticality safety guide

    Energy Technology Data Exchange (ETDEWEB)

    Pruvost, N.L.; Paxton, H.C. [eds.

    1996-09-01

    This technical reference document cites information related to nuclear criticality safety principles, experience, and practice. The document also provides general guidance for criticality safety personnel and regulators.

  4. Results of operation and current safety performance of nuclear facilities located in the Russian Federation

    Science.gov (United States)

    Kuznetsov, V. M.; Khvostova, M. S.

    2016-12-01

    After the NPP radiation accidents in Russia and Japan, a safety statu of Russian nuclear power plants causes concern. A repeated life time extension of power unit reactor plants, designed at the dawn of the nuclear power engineering in the Soviet Union, power augmentation of the plants to 104-109%, operation of power units in a daily power mode in the range of 100-70-100%, the use of untypical for NPP remixed nuclear fuel without a careful study of the results of its application (at least after two operating periods of the research nuclear installations), the aging of operating personnel, and many other management actions of the State Corporation "Rosatom", should attract the attention of the Federal Service for Ecological, Technical and Atomic Supervision (RosTekhNadzor), but this doesn't happen. The paper considers safety issues of nuclear power plants operating in the Russian Federation. The authors collected statistical information on violations in NPP operation over the past 25 years, which shows that even after repeated relaxation over this period of time of safety regulation requirements in nuclear industry and highly expensive NPP modernization, the latter have not become more safe, and the statistics confirms this. At a lower utilization factor high-power pressure-tube reactors RBMK-1000, compared to light water reactors VVER-440 and 1000, have a greater number of violations and that after annual overhauls. A number of direct and root causes of NPP mulfunctions is still high and remains stable for decades. The paper reveals bottlenecks in ensuring nuclear and radiation safety of nuclear facilities. Main outstanding issues on the storage of spent nuclear fuel are defined. Information on emissions and discharges of radioactive substances, as well as fullness of storages of solid and liquid radioactive waste, located at the NPP sites are presented. Russian NPPs stress test results are submitted, as well as data on the coming removal from operation of NPP

  5. Revitalizing Nuclear Safety Research.

    Science.gov (United States)

    National Academy of Sciences - National Research Council, Washington, DC.

    This report covers the general issues involved in nuclear safety research and points out the areas needing detailed consideration. Topics included are: (1) "Principles of Nuclear Safety Research" (examining who should fund, who should conduct, and who should set the agenda for nuclear safety research); (2) "Elements of a Future…

  6. Current state of nuclear fuel cycles in nuclear engineering and trends in their development according to the environmental safety requirements

    Science.gov (United States)

    Vislov, I. S.; Pischulin, V. P.; Kladiev, S. N.; Slobodyan, S. M.

    2016-08-01

    The state and trends in the development of nuclear fuel cycles in nuclear engineering, taking into account the ecological aspects of using nuclear power plants, are considered. An analysis of advantages and disadvantages of nuclear engineering, compared with thermal engineering based on organic fuel types, was carried out. Spent nuclear fuel (SNF) reprocessing is an important task in the nuclear industry, since fuel unloaded from modern reactors of any type contains a large amount of radioactive elements that are harmful to the environment. On the other hand, the newly generated isotopes of uranium and plutonium should be reused to fabricate new nuclear fuel. The spent nuclear fuel also includes other types of fission products. Conditions for SNF handling are determined by ecological and economic factors. When choosing a certain handling method, one should assess these factors at all stages of its implementation. There are two main methods of SNF handling: open nuclear fuel cycle, with spent nuclear fuel assemblies (NFAs) that are held in storage facilities with their consequent disposal, and closed nuclear fuel cycle, with separation of uranium and plutonium, their purification from fission products, and use for producing new fuel batches. The development of effective closed fuel cycles using mixed uranium-plutonium fuel can provide a successful development of the nuclear industry only under the conditions of implementation of novel effective technological treatment processes that meet strict requirements of environmental safety and reliability of process equipment being applied. The diversity of technological processes is determined by different types of NFA devices and construction materials being used, as well as by the composition that depends on nuclear fuel components and operational conditions for assemblies in the nuclear power reactor. This work provides an overview of technological processes of SNF treatment and methods of handling of nuclear fuel

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

    Science.gov (United States)

    Song, H C

    2016-06-01

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

  8. Ensuring Nuclear Safety

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The Fukushima accident precipitates overall safety inspection by China Guangdong Nuclear Power Holding Corp The Fukushima nuclear accident in Japan had barely made headlines around the world when China Guangdong Nuclear Power Holding Corp.(CGNPC),a nuclear power magnate in China,organized

  9. RETHINKING NUCLEAR POWER SAFETY

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The Fukushima nuclear accident sounds alarm bells in China’s nuclear power industry In the wake of the Fukushima nucleara ccident caused by the earthquake andt sunami in Japan,the safety of nuclearp ower plants and the development of nuclear power have raised concerns,

  10. Nuclear safety in perspective

    DEFF Research Database (Denmark)

    Andersson, K.; Sjöberg, B.M.D.; Lauridsen, Kurt

    2003-01-01

    The aim of the NKS/SOS-1 project has been to enhance common understanding about requirements for nuclear safety by finding improved means of communicat-ing on the subject in society. The project, which has been built around a number of seminars, wassupported by limited research in three sub......-projects: Risk assessment Safety analysis Strategies for safety management The report describes an industry in change due to societal factors. The concepts of risk and safety, safety management and systems forregulatory oversight are de-scribed in the nuclear area and also, to widen the perspective, for other...

  11. Safety and nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Gittus, John; Gunning, Angela.

    1988-05-01

    Representatives of the supporters and opponents of civil nuclear power put forward the arguments they feel the public should consider when making up their mind about the nuclear industry. The main argument in favour of nuclear power is about the low risk in comparison with other risks and the amount of radiation received on average by the population in the United Kingdom from different sources. The aim is to show that the nuclear industry is fully committed to the cause of safety and this has resulted in a healthy workforce and a safe environment for the public. The arguments against are that the nuclear industry is deceitful, secretive and politically motivated and thus its arguments about safety, risks, etc, cannot be trusted. The question of safety is considered further - in particular the perceptions, definitions and responsibility. The economic case for nuclear electricity is not accepted. (U.K.).

  12. Nuclear regulation and safety

    Energy Technology Data Exchange (ETDEWEB)

    Hendrie, J.M.

    1982-01-01

    Nuclear regulation and safety are discussed from the standpoint of a hypothetical country that is in the process of introducing a nuclear power industry and setting up a regulatory system. The national policy is assumed to be in favor of nuclear power. The regulators will have responsibility for economic, reliable electric production as well as for safety. Reactor safety is divided into three parts: shut it down, keep it covered, take out the afterheat. Emergency plans also have to be provided. Ways of keeping the core covered with water are discussed. (DLC)

  13. Elements of nuclear safety

    CERN Document Server

    Libmann, Jacques

    1996-01-01

    This basically educational book is intended for all involved in nuclear facility safety. It dissects the principles and experiences conducive to the adoption of attitudes compliant with what is now known as "safety culture". This book is accessible to a wide range of readers.

  14. Nuclear safety in perspective

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, K. [Karinta-Konsult HB (Sweden); Sjoeberg, B.M.D. [Norwegian Univ. of Scince and Technology (Norway); Larudisen, K. [Risoe National Lab., Roskilde (Denmark); Wahlstroem, B. [VTT Automation (Finland)

    2002-06-01

    The aim of the NKS/SOS-1 project has been to enhance common understanding about requirements for nuclear safety by finding improved means of communicating on the subject in society. The project, which has been built around a number of seminars, was supported by limited research in three sub-projects: 1) Risk assessment, 2) Safety analysis, and 3) Strategies for safety management. The report describes an industry in change due to societal factors. The concepts of risk and safety, safety management and systems for regulatory oversight are described in the nuclear area and also, to widen the perspective, for other industrial areas. Transparency and public participation are described as key elements in good risk communication, and case studies are given. Environmental Impact Assessment and Strategic Environmental Assessment are described as important overall processes within which risk communication can take place. Safety culture, safety indicators and quality systems are important concepts in the nuclear safety area are very useful, but also offer important challenges for the future. They have been subject to special attention in the project. (au)

  15. Nuclear safety in perspective

    Directory of Open Access Journals (Sweden)

    J. K. Basson

    1983-03-01

    Full Text Available The impending operation of South Africa’s first nuclear power station, Koeberg, necessitates a thorough analysis of nuclear safety under local conditions. More is known, worldwide, about radiation effects than about any other health hazard, and international norms have already been accepted since 1928. The widespread use of X-rays and radio-isotopes, the extraction and processing of uranium, visits by nuclear-powered ships and, especially, the nuclear-reactor operation in South Africa. Consequently, the pre-operational investigations of Koeberg could be completed thoroughly, with full confidence in its safe commissioning.

  16. Elements of a nuclear criticality safety program

    Energy Technology Data Exchange (ETDEWEB)

    Hopper, C.M.

    1995-07-01

    Nuclear criticality safety programs throughout the United States are quite successful, as compared with other safety disciplines, at protecting life and property, especially when regarded as a developing safety function with no historical perspective for the cause and effect of process nuclear criticality accidents before 1943. The programs evolved through self-imposed and regulatory-imposed incentives. They are the products of conscientious individuals, supportive corporations, obliged regulators, and intervenors (political, public, and private). The maturing of nuclear criticality safety programs throughout the United States has been spasmodic, with stability provided by the volunteer standards efforts within the American Nuclear Society. This presentation provides the status, relative to current needs, for nuclear criticality safety program elements that address organization of and assignments for nuclear criticality safety program responsibilities; personnel qualifications; and analytical capabilities for the technical definition of critical, subcritical, safety and operating limits, and program quality assurance.

  17. Nuclear safety in crisis regions

    Energy Technology Data Exchange (ETDEWEB)

    Ustohalova, Veronika; Englert, Matthias

    2017-04-12

    The use of nuclear energy demands extensive institutional and material infrastructure upon a foundation of stable intrastate conditions and interstate relations. Conflicts can result in catastrophic accidents, either deliberately or unintentionally. If there are nuclear facilities located in a crisis region, the risk of a nuclear disaster is markedly heightened. This can be explained not only in terms of the strategic relevance of the energy supply in military conflicts, but also the increased accident risks and hazards arising from collateral damage, as well as the erosion of the safety culture and institutional control in crisis regions with a nuclear infrastructure. Even just the escalation of a political dispute or the persistence of low intensity conflicts can make it generally more difficult and complex to maintain nuclear safety, if intrastate safety mechanisms come under strain or even fail as a result. So far no instance of military escalation, past or present, has led to an accident in a civil nuclear facility. Nevertheless, questions are clearly raised about the vulnerability of nuclear facilities in crisis regions and the risks associated with this vulnerability. Despite the potentially far-reaching consequences, too little attention is currently being paid to the linkage between intra- and interstate conflicts and the safety of nuclear facilities in crisis regions. The aim of the research presented here was to explore this theme and, after laying the groundwork in this manner, to raise awareness among policy-makers and the wider public. In this context the escalation of conflicts in the Ukraine is a particular focus. The first part of the report begins with a systematic look at the link between crisis regions and/or conflicts and nuclear safety. The various impact pathways relating to nuclear facility safety and the associated risks are described in relation to potential hazards induced by crises and wars. A nuclear facility can itself become a theatre

  18. Prospects for nuclear safety research

    Energy Technology Data Exchange (ETDEWEB)

    Beckjord, E.S.

    1995-04-01

    This document is the text of a paper presented by Eric S. Beckjord (Director, Nuclear Regulatory Research/NRC) at the 22nd Water Reactor Safety Meeting in Bethesda, MD in October 1994. The following topics are briefly reviewed: (1) Reactor vessel research, (2) Probabilistic risk assessment, (3) Direct containment heating, (4) Advanced LWR research, (5) Nuclear energy prospects in the US, and (6) Future nuclear safety research. Subtopics within the last category include economics, waste disposal, and health and safety.

  19. Japan reforms its nuclear safety

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2013-11-15

    The Fukushima Daiichi NPP accident deeply questioned the bases of nuclear safety and nuclear safety regulation in Japan. It also resulted in a considerable loss of public confidence in the safety of nuclear power across the world. Although the accident was caused by natural phenomena, institutional and human factors also largely contributed to its devastating consequences, as shown by the Japanese Diet's and Government's investigation reports. 'Both regulators and licensees were held responsible and decided to fully reconsider the existing approaches to nuclear safety. Consequently, the regulatory system underwent extensive reform based on the lessons learned from the accident,' Yoshihiro Nakagome, the President of Japan Nuclear Energy Safety Organisation, an ETSON member TSO, explains. (orig.)

  20. JRC activities in nuclear safety

    Directory of Open Access Journals (Sweden)

    Manna Giustino

    2009-01-01

    Full Text Available Nuclear energy is today the largest single source of carbon free and base-load electricity in Europe. While highlighting its important role in the overall energy mix, it is necessary to address sustainability, safety, and security concerns, in particular nuclear safety and nuclear waste management issues, which influence the public acceptance of nuclear energy. The present paper describes the Joint Research Centre activities in support to the EU nuclear safety policy. It describes the Joint Research Centre role in the EU institutional context, identifies the various customers to which the Joint Research Centre delivers its services, and provides some results of the Joint Research Centre scientific work inherent to nuclear safety.

  1. Nuclear criticality safety department training implementation

    Energy Technology Data Exchange (ETDEWEB)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1996-09-06

    The Nuclear Criticality Safety Department (NCSD) is committed to developing and maintaining a staff of qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. The NCSD Qualification Program is described in Y/DD-694, Qualification Program, Nuclear Criticality Safety Department This document provides a listing of the roles and responsibilities of NCSD personnel with respect to training and details of the Training Management System (TMS) programs, Mentoring Checklists and Checksheets, as well as other documentation utilized to implement the program. This document supersedes Y/DD-696, Revision 2, dated 3/27/96, Training Implementation, Nuclear Criticality Safety Department. There are no backfit requirements associated with revisions to this document.

  2. Nuclear safety research master plan

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Jae Joo; Yang, J. U.; Jun, Y. S. and others

    2001-06-01

    The SRMP (Safety Research Master Plan) is established to cope with the changes of nuclear industry environments. The tech. tree is developed according to the accident progress of the nuclear reactor. The 11 research fields are derived to cover the necessary technologies to ensure the safety of nuclear reactors. Based on the developed tech. tree, the following four main research fields are derived as the main safety research areas: 1. Integrated nuclear safety enhancement, 2. Thermal hydraulic experiment and assessment, 3. Severe accident management and experiment, and 4. The integrity of equipment and structure. The research frame and strategies are also recommended to enhance the efficiency of research activity, and to extend the applicability of research output.

  3. Progress of nuclear safety research. 2001

    Energy Technology Data Exchange (ETDEWEB)

    Anoda, Yoshinari; Sasajima, Hideo; Nishiyama, Yutaka (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

    2001-10-01

    JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy or the Safety Research Annual Plan issued by the Japanese government. The safety research at JAERI concerns the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety. This report summarizes the nuclear safety research activities of JAERI from April 1999 through March 2001. (author)

  4. NRC - regulator of nuclear safety

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    The U.S. Nuclear Regulatory Commission (NRC) was formed in 1975 to regulate the various commercial and institutional uses of nuclear energy, including nuclear power plants. The agency succeeded the Atomic Energy Commission, which previously had responsibility for both developing and regulating nuclear activities. Federal research and development work for all energy sources, as well as nuclear weapons production, is now conducted by the U.S. Department of Energy. Under its responsibility to protect public health and safety, the NRC has three principal regulatory functions: (1) establish standards and regulations, (2) issue licenses for nuclear facilities and users of nuclear materials, and (3) inspect facilities and users of nuclear materials to ensure compliance with the requirements. These regulatory functions relate to both nuclear power plants and to other uses of nuclear materials - like nuclear medicine programs at hospitals, academic activities at educational institutions, research work, and such industrial applications as gauges and testing equipment. The NRC places a high priority on keeping the public informed of its work. The agency recognizes the interest of citizens in what it does through such activities as maintaining public document rooms across the country and holding public hearings, public meetings in local areas, and discussions with individuals and organizations.

  5. Nuclear energy safety - new challenges

    Energy Technology Data Exchange (ETDEWEB)

    Rausch, Julio Cezar; Fonseca, Renato Alves da, E-mail: jrausch@cnen.gov.b, E-mail: rfonseca@cnen.gov.b [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    2011-07-01

    Fukushima accident in March this year, the second most serious nuclear accident in the world, put in evidence a discussion that in recent years with the advent of the 'nuclear renaissance' has been relegated in the background: what factors influence the use safe nuclear energy? Organizational precursor, latent errors, reduction in specific areas of competence and maintenance of nuclear programs is a scenario where the guarantee of a sustainable development of nuclear energy becomes a major challenge for society. A deep discussion of factors that influenced the major accidents despite the nuclear industry use of the so-called 'lessons learned' is needed. Major accidents continue to happen if a radical change is not implemented in the focus of safety culture. (author)

  6. Nuclear Safety for Space Systems

    Science.gov (United States)

    Offiong, Etim

    2010-09-01

    It is trite, albeit a truism, to say that nuclear power can provide propulsion thrust needed to launch space vehicles and also, to provide electricity for powering on-board systems, especially for missions to the Moon, Mars and other deep space missions. Nuclear Power Sources(NPSs) are known to provide more capabilities than solar power, fuel cells and conventional chemical means. The worry has always been that of safety. The earliest superpowers(US and former Soviet Union) have designed and launched several nuclear-powered systems, with some failures. Nuclear failures and accidents, however little the number, could be far-reaching geographically, and are catastrophic to humans and the environment. Building on the numerous research works on nuclear power on Earth and in space, this paper seeks to bring to bear, issues relating to safety of space systems - spacecrafts, astronauts, Earth environment and extra terrestrial habitats - in the use and application of nuclear power sources. It also introduces a new formal training course in Space Systems Safety.

  7. Safety of Nuclear

    Institute of Scientific and Technical Information of China (English)

    1996-01-01

    5.1 Development of WINFT Code Package Yi Xiaoyi Li Xiaohua Wang Guoqiang Zhong Jianguo ( CNNC nuclear softeware center) Fault tree analysis method is one of important tools of a performing system reliability analysis. WINFT is a fault three analysis code package on Windows. It contains fault tree graphics editor; event tree graphics editor; set equation transfter system; fault tree page layout; fault tree view or plot; fault tree print; text editor of windows and the function description of this code. WINFT was not only verified by many benchmark samples, but also applied on level I PSA for GNPS.

  8. Autoclave nuclear criticality safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    D`Aquila, D.M. [Martin Marietta Energy Systems, Inc., Piketon, OH (United States); Tayloe, R.W. Jr. [Battelle, Columbus, OH (United States)

    1991-12-31

    Steam-heated autoclaves are used in gaseous diffusion uranium enrichment plants to heat large cylinders of UF{sub 6}. Nuclear criticality safety for these autoclaves is evaluated. To enhance criticality safety, systems are incorporated into the design of autoclaves to limit the amount of water present. These safety systems also increase the likelihood that any UF{sub 6} inadvertently released from a cylinder into an autoclave is not released to the environment. Up to 140 pounds of water can be held up in large autoclaves. This mass of water is sufficient to support a nuclear criticality when optimally combined with 125 pounds of UF{sub 6} enriched to 5 percent U{sup 235}. However, water in autoclaves is widely dispersed as condensed droplets and vapor, and is extremely unlikely to form a critical configuration with released UF{sub 6}.

  9. Nuclear Criticality Safety Data Book

    Energy Technology Data Exchange (ETDEWEB)

    Hollenbach, D. F. [Y-12 National Security Complex, Oak Ridge, TN (United States)

    2016-11-14

    The objective of this document is to support the revision of criticality safety process studies (CSPSs) for the Uranium Processing Facility (UPF) at the Y-12 National Security Complex (Y-12). This design analysis and calculation (DAC) document contains development and justification for generic inputs typically used in Nuclear Criticality Safety (NCS) DACs to model both normal and abnormal conditions of processes at UPF to support CSPSs. This will provide consistency between NCS DACs and efficiency in preparation and review of DACs, as frequently used data are provided in one reference source.

  10. Nuclear criticality safety: 2-day training course

    Energy Technology Data Exchange (ETDEWEB)

    Schlesser, J.A. [ed.] [comp.

    1997-02-01

    This compilation of notes is presented as a source reference for the criticality safety course. At the completion of this training course, the attendee will: be able to define terms commonly used in nuclear criticality safety; be able to appreciate the fundamentals of nuclear criticality safety; be able to identify factors which affect nuclear criticality safety; be able to identify examples of criticality controls as used as Los Alamos; be able to identify examples of circumstances present during criticality accidents; have participated in conducting two critical experiments; be asked to complete a critique of the nuclear criticality safety training course.

  11. Progress of nuclear safety research. 2002

    Energy Technology Data Exchange (ETDEWEB)

    Anoda, Yoshinari; Kudo, Tamotsu; Tobita, Tohru (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] (and others)

    2002-11-01

    JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2000 through April 2002 and utilized facilities. This report also summarizes the examination of the ruptured pipe performed for assistance to the Nuclear and Industrial Safety Agency (NISA) for investigation of the accident at the Hamaoka Nuclear Power Station Unit-1 on November, 2001. (author)

  12. Radiation safety in nuclear medicine procedures

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-03-15

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

  13. Radiation Safety in Nuclear Medicine Procedures.

    Science.gov (United States)

    Cho, Sang-Geon; Kim, Jahae; Song, Ho-Chun

    2017-03-01

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

  14. Safety culture in the nuclear versus non-nuclear organization

    Energy Technology Data Exchange (ETDEWEB)

    Haber, S.B.; Shurberg, D.A.

    1996-10-01

    The importance of safety culture in the safe and reliable operation of nuclear organizations is not a new concept. The greatest barriers to this area of research are twofold: (1) the definition and criteria of safety culture for a nuclear organization and (2) the measurement of those attributes in an objective and systematic fashion. This paper will discuss a proposed resolution of those barriers as demonstrated by the collection of data across nuclear and non-nuclear facilities over a two year period.

  15. Software Quality Assurance for Nuclear Safety Systems

    Energy Technology Data Exchange (ETDEWEB)

    Sparkman, D R; Lagdon, R

    2004-05-16

    The US Department of Energy has undertaken an initiative to improve the quality of software used to design and operate their nuclear facilities across the United States. One aspect of this initiative is to revise or create new directives and guides associated with quality practices for the safety software in its nuclear facilities. Safety software includes the safety structures, systems, and components software and firmware, support software and design and analysis software used to ensure the safety of the facility. DOE nuclear facilities are unique when compared to commercial nuclear or other industrial activities in terms of the types and quantities of hazards that must be controlled to protect workers, public and the environment. Because of these differences, DOE must develop an approach to software quality assurance that ensures appropriate risk mitigation by developing a framework of requirements that accomplishes the following goals: {sm_bullet} Ensures the software processes developed to address nuclear safety in design, operation, construction and maintenance of its facilities are safe {sm_bullet} Considers the larger system that uses the software and its impacts {sm_bullet} Ensures that the software failures do not create unsafe conditions Software designers for nuclear systems and processes must reduce risks in software applications by incorporating processes that recognize, detect, and mitigate software failure in safety related systems. It must also ensure that fail safe modes and component testing are incorporated into software design. For nuclear facilities, the consideration of risk is not necessarily sufficient to ensure safety. Systematic evaluation, independent verification and system safety analysis must be considered for software design, implementation, and operation. The software industry primarily uses risk analysis to determine the appropriate level of rigor applied to software practices. This risk-based approach distinguishes safety

  16. Integrated Safety Assessment for Assuring Acceptable Level of Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Kwang Sik; Choi, Young Sung [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2008-05-15

    The discussions on regulatory goal of assuring an acceptable level of nuclear safety at nuclear facilities have been made among regulators worldwide so far. Several meetings were held and documents have been also prepared on safety goal, safety objectives, regulatory safety goals and so on. In 2008, the Greenbook 'The regulatory goal of assuring nuclear safety' was published by OECD/NEA CNRA (Committee on Nuclear Regulatory Activities) task group consisting of experts from OECD/NEA member countries. In Korea, similar efforts have been made and some practices have been already implemented in regulatory activities although they are not explicitly shown up. This paper reviews discussions made so far on the safety objectives or goals of regulation, and presents some examples adopted for integrated safety assessment in Korea. Some suggestions for future directions on this discourse are made.

  17. Status of nuclear energy and nuclear safety in Slovenia

    Energy Technology Data Exchange (ETDEWEB)

    Grlicarev, I. [Slovenian Nuclear Safety Administration (Slovenia)

    2002-07-01

    Although in Slovenia there is only one nuclear power plant in operation, it represents a substantial share in the production of electrical power in the country. Nuclear fuel cycle in Slovenia comprises the nuclear power plant, a research reactor, a storage for low and intermediate level radioactive waste and uranium mine in decommissioning. The Krsko NPP operation meets the standards of the high level of nuclear safety. Considerable effort has been put into the negotiations in the field of nuclear energy and nuclear safety with the European Commission within the pre-accession activities of Slovenia to European Union. (orig.)

  18. Regulatory oversight of nuclear safety in Finland. Annual report 2011

    Energy Technology Data Exchange (ETDEWEB)

    Kainulainen, E. (ed.)

    2012-07-01

    The report constitutes the report on regulatory control in the field of nuclear energy which the Radiation and Nuclear Safety Authority (STUK) is required to submit once a year to the Ministry of Employment and the Economy pursuant to Section 121 of the Nuclear Energy Decree. The report is also delivered to the Ministry of Environment, the Finnish Environment Institute, and the regional environmental authorities of the localities in which a nuclear facility is located. The regulatory control of nuclear safety in 2011 included the design, construction and operation of nuclear facilities, as well as nuclear waste management and nuclear materials. The first parts of the report explain the basics of nuclear safety regulation included as part of STUK's responsibilities, as well as the objectives of the operations, and briefly introduce the objects of regulation. The chapter concerning the development and implementation of legislation and regulations describes changes in nuclear legislation, as well as the progress of STUK's YVL Guide revision work. The section concerning the regulation of nuclear facilities contains an overall safety assessment of the nuclear facilities currently in operation or under construction. The chapter concerning the regulation of the final disposal project for spent nuclear fuel de-scribes the preparations for the final disposal project and the related regulatory activities. The section concerning nuclear non-proliferation describes the nuclear non-proliferation control for Finnish nuclear facilities and final disposal of spent nuclear fuel, as well as measures required by the Additional Protocol of the Safeguards Agreement. The chapter describing the oversight of security arrangements in the use of nuclear energy discusses oversight of the security arrangements in nuclear power plants and other plants, institutions and functions included within the scope of STUK's regulatory oversight. The chapter also discusses the national and

  19. Advanced research workshop: nuclear materials safety

    Energy Technology Data Exchange (ETDEWEB)

    Jardine, L J; Moshkov, M M

    1999-01-28

    The Advanced Research Workshop (ARW) on Nuclear Materials Safety held June 8-10, 1998, in St. Petersburg, Russia, was attended by 27 Russian experts from 14 different Russian organizations, seven European experts from six different organizations, and 14 U.S. experts from seven different organizations. The ARW was conducted at the State Education Center (SEC), a former Minatom nuclear training center in St. Petersburg. Thirty-three technical presentations were made using simultaneous translations. These presentations are reprinted in this volume as a formal ARW Proceedings in the NATO Science Series. The representative technical papers contained here cover nuclear material safety topics on the storage and disposition of excess plutonium and high enriched uranium (HEU) fissile materials, including vitrification, mixed oxide (MOX) fuel fabrication, plutonium ceramics, reprocessing, geologic disposal, transportation, and Russian regulatory processes. This ARW completed discussions by experts of the nuclear materials safety topics that were not covered in the previous, companion ARW on Nuclear Materials Safety held in Amarillo, Texas, in March 1997. These two workshops, when viewed together as a set, have addressed most nuclear material aspects of the storage and disposition operations required for excess HEU and plutonium. As a result, specific experts in nuclear materials safety have been identified, know each other from their participation in t he two ARW interactions, and have developed a partial consensus and dialogue on the most urgent nuclear materials safety topics to be addressed in a formal bilateral program on t he subject. A strong basis now exists for maintaining and developing a continuing dialogue between Russian, European, and U.S. experts in nuclear materials safety that will improve the safety of future nuclear materials operations in all the countries involved because of t he positive synergistic effects of focusing these diverse backgrounds of

  20. Regulatory control of nuclear safety in Finland. Annual report 1997

    Energy Technology Data Exchange (ETDEWEB)

    Tossavainen, K. [ed.

    1998-08-01

    The report describes regulatory control of the use of nuclear energy by the Radiation and Nuclear Safety Authority (STUK) in Finland in 1997. Nuclear regulatory control ascertained that the operation of Finnish NPPs was in compliance with the conditions set out in operating licences and current regulations. In addition to NPP normal operation, STUK oversaw projects at the plant units relating to power uprating and safety improvements. STUK prepared statements for the Ministry of Trade and Industry about the applications for renewing the operating licenses of Loviisa and Olkiluoto NPPs. The most important items of supervision in nuclear waste management were studies relating to the final disposal of spent fuel from NPPs and the review of the licence application for a repository for low- and intermediate-level reactor waste from Loviisa NPP. Preparation of general safety regulations for the final disposal of spent nuclear fuel, to be published in the form of a Council of State Decision, was started. By safeguards control, the use of nuclear materials was verified to be in compliance with current regulations and that the whereabouts of every batch of nuclear material were always known. Nuclear material safeguards were stepped up to prevent illicit trafficking of nuclear materials and other radioactive materials. In co-operation with the Ministry for Foreign Affairs and the Institute of Seismology (University of Helsinki), preparations were undertaken to implement the Comprehensive Nuclear Test Ban Treaty (CTBT). For enforcement of the Treaty and as part of the international regulatory approach, STUK is currently developing laboratory analyses relating to airborne radioactivity measurements. The focus of co-operation funded by external sources was as follows: improvement of the safety of Kola and Leningrad NPPs, improvement of nuclear waste management in North-West Russia, development of the organizations of nuclear safety authorities in Eastern Europe and development

  1. Safety Cultural Competency Modeling in Nuclear Organizations

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sa Kil; Oh, Yeon Ju; Luo, Meiling; Lee, Yong Hee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The nuclear safety cultural competency model should be supplemented through a bottom-up approach such as behavioral event interview. The developed model, however, is meaningful for determining what should be dealt for enhancing safety cultural competency of nuclear organizations. The more details of the developing process, results, and applications will be introduced later. Organizational culture include safety culture in terms of its organizational characteristics.

  2. Nuclear safety culture in Finland and Sweden - Developments and challenges

    Energy Technology Data Exchange (ETDEWEB)

    Reiman, T.; Pietikaeinen, E. (Technical Research Centre of Finland, VTT (Finland)); Kahlbom, U. (RiskPilot AB (Sweden)); Rollenhagen, C. (Royal Institute of Technology (KTH) (Sweden))

    2011-02-15

    The project aimed at studying the concept of nuclear safety culture and the Nordic nuclear branch safety culture. The project also aimed at looking how the power companies and the regulators view the current responsibilities and role of subcontractors in the Nordic nuclear safety culture as well as to inspect the special demands for safety culture in subcontracting chains. Interview data was collected in Sweden (n = 14) and Finland (n = 16) during 2009. Interviewees represented the major actors in the nuclear field (regulators, power companies, expert organizations, waste management organizations). Results gave insight into the nature and evaluation of safety culture in the nuclear industry. Results illustrated that there is a wide variety of views on matters that are considered important for nuclear safety within the Nordic nuclear community. However, the interviewees considered quite uniformly such psychological states as motivation, mindfulness, sense of control, understanding of hazards and sense of responsibility as important for nuclear safety. Results also gave insight into the characteristics of Nordic nuclear culture. Various differences in safety cultures in Finland and Sweden were uncovered. In addition to the differences, historical reasons for the development of the nuclear safety cultures in Finland and Sweden were pointed out. Finally, results gave implications that on the one hand subcontractors can bring new ideas and improvements to the plants' practices, but on the other hand the assurance of necessary safety attitudes and competence of the subcontracting companies and their employees is considered as a challenge. The report concludes that a good safety culture requires a deep and wide understanding of nuclear safety including the various accident mechanisms of the power plants as well as a willingness to continuously develop one's competence and understanding. An effective and resilient nuclear safety culture has to foster a constant

  3. Nuclear safety policy working group recommendations on nuclear propulsion safety for the space exploration initiative

    Science.gov (United States)

    Marshall, Albert C.; Lee, James H.; Mcculloch, William H.; Sawyer, J. Charles, Jr.; Bari, Robert A.; Cullingford, Hatice S.; Hardy, Alva C.; Niederauer, George F.; Remp, Kerry; Rice, John W.

    1993-01-01

    An interagency Nuclear Safety Working Group (NSPWG) was chartered to recommend nuclear safety policy, requirements, and guidelines for the Space Exploration Initiative (SEI) nuclear propulsion program. These recommendations, which are contained in this report, should facilitate the implementation of mission planning and conceptual design studies. The NSPWG has recommended a top-level policy to provide the guiding principles for the development and implementation of the SEI nuclear propulsion safety program. In addition, the NSPWG has reviewed safety issues for nuclear propulsion and recommended top-level safety requirements and guidelines to address these issues. These recommendations should be useful for the development of the program's top-level requirements for safety functions (referred to as Safety Functional Requirements). The safety requirements and guidelines address the following topics: reactor start-up, inadvertent criticality, radiological release and exposure, disposal, entry, safeguards, risk/reliability, operational safety, ground testing, and other considerations.

  4. 78 FR 67206 - Qualification Tests for Safety-Related Actuators in Nuclear Power Plants

    Science.gov (United States)

    2013-11-08

    ... COMMISSION Qualification Tests for Safety-Related Actuators in Nuclear Power Plants AGENCY: Nuclear...-Related Actuators in Nuclear Power Plants.'' This RG is being revised to provide applicants and licensees with the most current information on testing safety-related actuators in nuclear power plants. This...

  5. Reevaluating nuclear safety and security in a post 9/11 era.

    Energy Technology Data Exchange (ETDEWEB)

    Booker, Paul M.; Brown, Lisa M.

    2005-07-01

    This report has the following topics: (1) Changing perspectives on nuclear safety and security; (2) Evolving needs in a post-9/11 era; (3) Nuclear Weapons--An attractive terrorist target; (4) The case for increased safety; (5) Evolution of current nuclear weapons safety and security; (6) Integrated surety; (7) The role of safety and security in enabling responsiveness; (8) Advances in surety technologies; and (9) Reevaluating safety.

  6. New reactor technology: safety improvements in nuclear power systems.

    Science.gov (United States)

    Corradini, M L

    2007-11-01

    Almost 450 nuclear power plants are currently operating throughout the world and supplying about 17% of the world's electricity. These plants perform safely, reliably, and have no free-release of byproducts to the environment. Given the current rate of growth in electricity demand and the ever growing concerns for the environment, nuclear power can only satisfy the need for electricity and other energy-intensive products if it can demonstrate (1) enhanced safety and system reliability, (2) minimal environmental impact via sustainable system designs, and (3) competitive economics. The U.S. Department of Energy with the international community has begun research on the next generation of nuclear energy systems that can be made available to the market by 2030 or earlier, and that can offer significant advances toward these challenging goals; in particular, six candidate reactor system designs have been identified. These future nuclear power systems will require advances in materials, reactor physics, as well as thermal-hydraulics to realize their full potential. However, all of these designs must demonstrate enhanced safety above and beyond current light water reactor systems if the next generation of nuclear power plants is to grow in number far beyond the current population. This paper reviews the advanced Generation-IV reactor systems and the key safety phenomena that must be considered to guarantee that enhanced safety can be assured in future nuclear reactor systems.

  7. Nuclear safety in EU candidate countries

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-10-01

    Nuclear safety in the candidate countries to the European Union is a major issue that needs to be addressed in the framework of the enlargement process. Therefore WENRA members considered it was their duty to offer their technical assistance to their Governments and the European Union Institutions. They decided to express their collective opinion on nuclear safety in those candidate countries having at least one nuclear power plant: Bulgaria, the Czech Republic, Hungary, Lithuania, Romania, Slovakia and Slovenia. The report is structured as follows: A foreword including background information, structure of the report and the methodology used, General conclusions of WENRA members reflecting their collective opinion, For each candidate country, an executive summary, a chapter on the status of the regulatory regime and regulatory body, and a chapter on the nuclear power plant safety status. Two annexes are added to address the generic safety characteristics and safety issues for RBMK and VVER plants. The report does not cover radiation protection and decommissioning issues, while safety aspects of spent fuel and radioactive waste management are only covered as regards on-site provisions. In order to produce this report, WENRA used different means: For the chapters on the regulatory regimes and regulatory bodies, experts from WENRA did the work. For the chapters on nuclear power plant safety status, experts from WENRA and from French and German technical support organisations did the work. Taking into account the contents of these chapters, WENRA has formulated its general conclusions in this report.

  8. Nuclear Safety Research Department annual report 2000

    DEFF Research Database (Denmark)

    Majborn, B.; Nielsen, Sven Poul; Damkjær, A.

    2001-01-01

    The report presents a summary of the work of the Nuclear Safety Research Department in 2000. The department's research and development activities were organized in two research programmes: "Radiation Protection and Reactor Safety" and "Radioecology andTracer Studies". In addtion the department...

  9. Nuclear Safety Research Department annual report 2001

    DEFF Research Database (Denmark)

    Majborn, B.; Damkjær, A.; Nielsen, Sven Poul

    2002-01-01

    The report presents a summary of the work of the Nuclear Safety Research Department in 2001. The department's research and development activities were organized in two research programmes: "Radiation Protection and Reactor Safety" and "Radioecology andTracer Studies". In addition the department...

  10. Safety in nuclear power plants in India

    OpenAIRE

    Deolalikar R

    2008-01-01

    Safety in nuclear power plants (NPPs) in India is a very important topic and it is necessary to dissipate correct information to all the readers and the public at large. In this article, I have briefly described how the safety in our NPPs is maintained. Safety is accorded overriding priority in all the activities. NPPs in India are not only safe but are also well regulated, have proper radiological protection of workers and the public, regular surveillance, dosimetry, approved standard operat...

  11. Some views on nuclear reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    Tanguy, P.Y. [Electricite de France, Paris (France)

    1995-04-01

    This document is the text of a speech given by Pierre Y. Tanguy (Electricite de France) at the 22nd Water Reactor Safety Meeting held in Bethesda, MD in 1994. He describes the EDF nuclear program in broad terms and proceeds to discuss operational safety results with EDF plants. The speaker also outlines actions to enhance safety planned for the future, and he briefly mentions French cooperation with the Chinese on the Daya Bay project.

  12. Nuclear Safety. 1997; Surete Nucleaire. 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-19

    A quick review of the nuclear safety at EDF may be summarized as follows: - the nuclear safety at EDF maintains at a rather good standard; - none of the incidents that took place has had any direct impact upon safety; - the availability remained good; - initiation of the floor 4 reactor generation (N4 unit - 1450 MW) ensued without major difficulties (the Civaux 1 NPP has been coupled to the power network at 24 december 1997); - the analysis of the incidents interesting from the safety point of view presents many similarities with earlier ones. Significant progress has been recorded in promoting actively and directly a safe operation by making visible, evident and concrete the exertion of the nuclear operation responsibility and its control by the hierarchy. The report develops the following chapters and subjects: 1. An overview on 1997; 1.1. The technical issues of the nuclear sector; 1.2. General performances in safety; 1.3. The main incidents; 1.4. Wastes and radiation protection; 2. Nuclear safety management; 2.1. Dynamics and results; 2.2. Ameliorations to be consolidated; 3. Other important issues in safety; 3.1. Probabilistic safety studies; 3.2. Approach for safety re-evaluation; 3.3. The network safety; 3.4. Crisis management; 3.5. The Lifetime program; 3.6. PWR; 3.7. Documentation; 3.8. Competence; 4. Safety management in the future; 4.1. An open future; 4.2. The fast neutron NPP at Creys-Malville; 4.3. Stabilization of the PWR reference frame; 4.4. Implementing the EURATOM directive regarding the radiation protection standards; 4.5. Development of biomedical research and epidemiological studies; 4.6. New regulations concerning the liquid and gaseous effluents; 5. Visions of an open future; 5.1. Alternative views upon safety ay EDF; 5.2. Safety authority; 5.3. International considerations; 5.4. What happens abroad; 5.5. References from non-nuclear domain. Four appendices are added referring to policy of safety management, policy of human factors in NPPs

  13. Atomic Information Technology Safety and Economy of Nuclear Power Plants

    CERN Document Server

    Woo, Taeho

    2012-01-01

    Atomic Information Technology revaluates current conceptions of the information technology aspects of the nuclear industry. Economic and safety research in the nuclear energy sector are explored, considering statistical methods which incorporate Monte-Carlo simulations for practical applications. Divided into three sections, Atomic Information Technology covers: • Atomic economics and management, • Atomic safety and reliability, and • Atomic safeguarding and security. Either as a standalone volume or as a companion to conventional nuclear safety and reliability books, Atomic Information Technology acts as a concise and thorough reference on statistical assessment technology in the nuclear industry. Students and industry professionals alike will find this a key tool in expanding and updating their understanding of this industry and the applications of information technology within it.

  14. Siting of nuclear facilities. Selections from Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.

    1976-07-01

    The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria.

  15. EUROSAFE Forum for nuclear safety. Towards Convergence of Technical Nuclear Safety Practices in Europe. Safety Improvements - Reasons, Strategies, Implementation

    Energy Technology Data Exchange (ETDEWEB)

    Erven, Ulrich (ed.) [Gesellschaft fuer Anlagen- und Reaktorsicherheit, GRS mbH, Schwertnergasse 1, 50667 Koeln (Germany); Cherie, Jean-Bernard (ed.) [Institut de Radioprotection et de Surete Nucleaire, IRSN, BP 17, 92262 Fontenay-aux-Roses Cedex (France); Boeck, Benoit De (ed.) [Association Vincotte Nuclear, AVN, Rue Walcourt 148, 1070 Bruxelles (Belgium)

    2005-07-01

    The EUROSAFE Forum for Nuclear Safety is part of the EUROSAFE approach, which consists of two further elements: the EUROSAFE Tribune and the EUROSAFE Web site. The general aim of EUROSAFE is to contribute to fostering the convergence of technical nuclear safety practices in a broad European context. This is done by providing technical safety and research organisations, safety authorities, power utilities, the rest of the industry and non-governmental organisations mainly from the European Union and East-European countries, and international organisations with a platform for the presentation of recent analyses and R and D in the field of nuclear safety. The goal is to share experiences, to exchange technical and scientific opinions, and to conduct debates on key issues in the fields of nuclear safety and radiation protection. The EUROSAFE Forum on 2005 focused on Safety Improvements, Reasons - Strategies - Implementation, from the point of view of the authorities, TSOs and industry. Latest work in nuclear installation safety and research, waste management, radiation safety as well as nuclear material and nuclear facilities security carried out by GRS, IRSN, AVN and their partners in the European Union, Switzerland and Eastern Europe are presented. A high level of nuclear safety is a priority for the countries of Europe. The technical safety organisations play an important role in contributing to that objective through appropriate approaches to major safety issues as part of their assessments and research activities. The challenges to nuclear safety are international. Changes in underlying technologies such as instrumentation and control, the impact of electricity market deregulation, demands for improved safety and safety management, the ageing of nuclear facilities, waste management, maintaining and improving scientific and technical knowledge, and the need for greater transparency - these are all issues where the value of an international approach is gaining

  16. Accurate fission data for nuclear safety

    CERN Document Server

    Solders, A; Jokinen, A; Kolhinen, V S; Lantz, M; Mattera, A; Penttila, H; Pomp, S; Rakopoulos, V; Rinta-Antila, S

    2013-01-01

    The Accurate fission data for nuclear safety (AlFONS) project aims at high precision measurements of fission yields, using the renewed IGISOL mass separator facility in combination with a new high current light ion cyclotron at the University of Jyvaskyla. The 30 MeV proton beam will be used to create fast and thermal neutron spectra for the study of neutron induced fission yields. Thanks to a series of mass separating elements, culminating with the JYFLTRAP Penning trap, it is possible to achieve a mass resolving power in the order of a few hundred thousands. In this paper we present the experimental setup and the design of a neutron converter target for IGISOL. The goal is to have a flexible design. For studies of exotic nuclei far from stability a high neutron flux (10^12 neutrons/s) at energies 1 - 30 MeV is desired while for reactor applications neutron spectra that resembles those of thermal and fast nuclear reactors are preferred. It is also desirable to be able to produce (semi-)monoenergetic neutrons...

  17. Nuclear Safety Charter; Charte Surete Nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    The AREVA 'Values Charter' reaffirmed the priority that must be given to the requirement for a very high level of safety, which applies in particular to the nuclear field. The purpose of this Nuclear Safety Charter is to set forth the group's commitments in the field of nuclear safety and radiation protection so as to ensure that this requirement is met throughout the life cycle of the facilities. It should enable each of us, in carrying out our duties, to commit to this requirement personally, for the company, and for all stakeholders. These commitments are anchored in organizational and action principles and in complete transparency. They build on a safety culture shared by all personnel and maintained by periodic refresher training. They are implemented through Safety, Health, and Environmental management systems. The purpose of these commitments, beyond strict compliance with the laws and regulations in force in countries in which we operate as a group, is to foster a continuous improvement initiative aimed at continually enhancing our overall performance as a group. Content: 1 - Organization: responsibility of the group's executive management and subsidiaries, prime responsibility of the operator, a system of clearly defined responsibilities that draws on skilled support and on independent control of operating personnel, the general inspectorate: a shared expertise and an independent control of the operating organization, an organization that can be adapted for emergency management. 2 - Action principles: nuclear safety applies to every stage in the plant life cycle, lessons learned are analyzed and capitalized through the continuous improvement initiative, analyzing risks in advance is the basis of Areva's safety culture, employees are empowered to improve nuclear Safety, the group is committed to a voluntary radiation protection initiative And a sustained effort in reducing waste and effluent from facility Operations, employees and

  18. Rough Sets and Nuclear Safety

    Institute of Scientific and Technical Information of China (English)

    2007-01-01

    It is well-known that rough set theory can be applied successfully to rough classification and knowledge discovery. Our work is concerned with finding methods for using rough sets to identify classes in datasets, finding dependencies in relations and discovering rules which are hidden in databases by means of decision tables and algorithm D. We use these methods to analyze and control aspects of nuclear energy generation.

  19. Regulatory control of nuclear safety in Finland. Annual report 1998

    Energy Technology Data Exchange (ETDEWEB)

    Tossavainen, K. [ed.

    1999-10-01

    The report describes regulatory control of the safe use of nuclear energy by the Radiation and Nuclear Safety Authority (STUK) in 1998. STUK is the Finnish nuclear safety authority. The submission of this report to the Ministry of Trade and Industry is stipulated in Section 121 of the Nuclear Energy Decree. It was verified by regulatory control that the operation of Finnish NPPs was in compliance with conditions set out in the operating licences of the plants and with regulations currently in force. In addition to supervising the normal operation of the plants, STUK oversaw projects carried out at the plant units, which related to the uprating of their power and the improvement of their safety. STUK issued to the Ministry of Trade and Industry a statement about applications for the renewal of the operating licences of Loviisa and Olkiluoto NPPs, which had been submitted by Imatran Voima Oy and Teollisuuden Voima Oy. Regulatory activities in the field of nuclear waste management were focused on the storage and final disposal of spent fuel as well as the treatment, storage and final disposal of reactor waste. STUK issued a statement to the Ministry of Trade and Industry about an environmental impact assessment programme pertaining to a spent fuel repository project, which had been submitted by Posiva Oy, as well as on Imatran Voima Oy's application concerning the operation of a repository for medium- and low-level reactor waste from Loviisa NPP. The use of nuclear materials was in compliance with the regulations currently in force and also the whereabouts of every batch of nuclear material were ensured by safeguards control. In international safeguards, important changes took place, which were reflected also in safeguards activities at national level. International co-operation continued based on financing both from STUK's budget and from additional sources. The focus of co-operation funded from outside sources was as follows: improvement of the safety of

  20. Nuclear Criticality Safety Organization training implementation. Revision 4

    Energy Technology Data Exchange (ETDEWEB)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1997-05-19

    The Nuclear Criticality Safety Organization (NCSO) is committed to developing and maintaining a staff of qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document provides a listing of the roles and responsibilities of NCSO personnel with respect to training and details of the Training Management System (TMS) programs, Mentoring Checklists and Checksheets, as well as other documentation utilized to implement the program. This Training Implementation document is applicable to all technical and managerial NCSO personnel, including temporary personnel, sub-contractors and/or LMES employees on loan to the NCSO, who are in a qualification program.

  1. Regulatory control of nuclear safety in Finland. Annual report 1999

    Energy Technology Data Exchange (ETDEWEB)

    Tossavainen, K. [ed.

    2000-06-01

    This report concerns the regulatory control of nuclear energy in Finland in 1999. Its submission to the Ministry of Trade and Industry by the Finnish Radiation and Nuclear Safety Authority (STUK) is stipulated in section 121 of the Nuclear Energy Decree. STUK's regulatory work was focused on the operation of the Finnish nuclear power plants as well as on nuclear waste management and safeguards of nuclear materials. The operation of the Finnish nuclear power plants was in compliance with the conditions set out in their operating licences and with current regulations, with the exception of some inadvertent deviations from the Technical Specifications. No plant events endangering the safe use of nuclear energy occurred. The individual doses of all nuclear power plant workers remained below the dose threshold. The collective dose of the workers was low, compared internationally, and did not exceed STUK's guidelines at either nuclear power plant. The radioactive releases were minor and the dose calculated on their basis for the most exposed individual in the vicinity of the plant was well below the limit established in a decision of the Council of State at both Loviisa and Olkiluoto nuclear power plants. STUK issued statements to the Ministry of Trade and Industry about the environmental impact assessment programme reports on the possible nuclear power plant projects at Olkiluoto and Loviisa and about the continued operation of the research reactor in Otaniemi, Espoo. A Y2k-related safety assessment of the Finnish nuclear power plants was completed in December. In nuclear waste management STUK's regulatory work was focused on spent fuel storage and final disposal plans as well as on the treatment, storage and final disposal of reactor waste. No events occurred in nuclear waste management that would have endangered safety. A statement was issued to the Ministry of Trade and Industry about an environmental impact assessment report on a proposed final

  2. Safety research in nuclear fuel cycle at PNC

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This report collects the results of safety research in nuclear fuel cycle at Power Reactor and Nuclear Fuel Development Corporation, in order to answer to the Questionnaire of OECD/NEA. The Questionnaire request to include information concerning to research topic, description, main results (if available), reference documents, research institutes involved, sponsoring organization and other pertinent information about followings: a) Recently completed research projects. b) Ongoing (current) research projects. Achievements on following items are omitted by the request of OECD/NEA, uranium mining and milling, uranium refining and conversion to UF{sub 6}, uranium enrichment, fuel manufacturers, spent fuel storage, radioactive waste management, transport of radioactive materials, decommissioning. We select topics from the fields of a) nuclear installation, b) seismic, and c) PSA, in projects from frame of annual safety research plan for nuclear installations established by Nuclear Safety Commission. We apply for the above a) and b) projects as follows: a) Achievements in Safety Research, fiscal 1991-1995, b) fiscal 1996 Safety Research Achievements: Progress. (author)

  3. Safety research in nuclear fuel cycle at PNC

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This report collects the results of safety research in nuclear fuel cycle at Power Reactor and Nuclear Fuel Development Corporation, in order to answer to the Questionnaire of OECD/NEA. The Questionnaire request to include information concerning to research topic, description, main results (if available), reference documents, research institutes involved, sponsoring organization and other pertinent information about followings: a) Recently completed research projects. b) Ongoing (current) research projects. Achievements on following items are omitted by the request of OECD/NEA, uranium mining and milling, uranium refining and conversion to UF{sub 6}, uranium enrichment, fuel manufacturers, spent fuel storage, radioactive waste management, transport of radioactive materials, decommissioning. We select topics from the fields of a) nuclear installation, b) seismic, and c) PSA, in projects from frame of annual safety research plan for nuclear installations established by Nuclear Safety Commission. We apply for the above a) and b) projects as follows: a) Achievements in Safety Research, fiscal 1991-1995, b) fiscal 1996 Safety Research Achievements: Progress. (author)

  4. Political economy and social psychology of nuclear safety

    Energy Technology Data Exchange (ETDEWEB)

    Choe, Gwang Sik

    2009-03-15

    The contents of this book are consideration on independence of nuclear safety regulations, analysis of trend in internal and external on effectualness of nuclear safety regulations, political psychology of a hard whistle, how to deal with trust and distrust on regulation institute, international trend and domestic trend of nuclear safe culture, policy for building of trust of people on nuclear safety and regulations, measurement and conception of nuclear safety and for who imposes legal controls?.

  5. Management of National Nuclear Power Programs for assured safety

    Energy Technology Data Exchange (ETDEWEB)

    Connolly, T.J. (ed.)

    1985-01-01

    Topics discussed in this report include: nuclear utility organization; before the Florida Public Service Commission in re: St. Lucie Unit No. 2 cost recovery; nuclear reliability improvement and safety operations; nuclear utility management; training of nuclear facility personnel; US experience in key areas of nuclear safety; the US Nuclear Regulatory Commission - function and process; regulatory considerations of the risk of nuclear power plants; overview of the processes of reliability and risk management; management significance of risk analysis; international and domestic institutional issues for peaceful nuclear uses; the role of the Institute of Nuclear Power Operations (INPO); and nuclear safety activities of the International Atomic Energy Agency (IAEA).

  6. Current Situation of International Nuclear Arms Control and Nuclear Disarmament

    Institute of Scientific and Technical Information of China (English)

    Gong; Xianfu

    2014-01-01

    <正>Currently,international nuclear arms control and nuclear disarmament process is showing both encouraging and frustrating signs,with a stress on the latter.The following is a general picture:First,the new U.S.-Russian nuclear disarmament process faces challenges and prospect of a new round of nuclear disarmament negotiation is grim.As a result of implementing the New START signed in February 2011,as of March 1,2014,the United States has 1585

  7. Convention on nuclear safety. Questions posted to Switzerland in 2008

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    Switzerland signed the Convention on Nuclear Safety (CNS) on 31 October 1995. It ratified the Convention on 12 September 1996, which came into force on 11 December 1996. In accordance with Article 5 of the Convention, Switzerland has prepared and submitted 4 country reports for Review Meetings of Contracting Parties organised in 1999, 2002, 2005 and 2006. These meetings at the IAEA headquarters in Vienna were attended by a Swiss delegation. Most of the requirements of the articles of the Convention were already standard practice in Switzerland. In the last years, all Swiss nuclear power plants (NPPs) as well as the Swiss Federal Nuclear Safety Inspectorate (HSK) built up documented quality management systems. The independence of HSK from licensing authorities is fulfilled on a technical level. In 2005, a new Nuclear Energy Act came into force requiring formal independence of the supervisory authorities from the licensing authorities. A separate act to legally settle the Inspectorate's fully independent status was adopted by Parliament. HSK participates in international co-operation and is represented in numerous nuclear safety working groups in order to ensure the exchange of scientific, technical and regulatory know-how. The regulatory processes applied to the licensing and safety surveillance of nuclear installations and their operation are up to date with the current state of science and technology. Deterministic and probabilistic safety evaluations guide and prioritise inspections and provide the basis for a graded approach to safety review and assessment. The surveillance of the NPPs' operating, control and safety systems, their component performance and integrity, their organisational and human aspects as well as the management, conditioning and interim storage of radioactive waste are permanent features of the supervisory authority's activities. Within the frame of a new integrated oversight process there is an annual systematic assessment of

  8. Safety Assessment - Swedish Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kjellstroem, B. [Luleaa Univ. of Technology (Sweden)

    1996-12-31

    After the reactor accident at Three Mile Island, the Swedish nuclear power plants were equipped with filtered venting of the containment. Several types of accidents can be identified where the filtered venting has no effect on the radioactive release. The probability for such accidents is hopefully very small. It is not possible however to estimate the probability accurately. Experiences gained in the last years, which have been documented in official reports from the Nuclear Power Inspectorate indicate that the probability for core melt accidents in Swedish reactors can be significantly larger than estimated earlier. A probability up to one in a thousand operating years can not be excluded. There are so far no indications that aging of the plants has contributed to an increased accident risk. Maintaining the safety level with aging nuclear power plants can however be expected to be increasingly difficult. It is concluded that the 12 Swedish plants remain a major threat for severe radioactive pollution of the Swedish environment despite measures taken since 1980 to improve their safety. Closing of the nuclear power plants is the only possibility to eliminate this threat. It is recommended that until this is done, quantitative safety goals, same for all Swedish plants, shall be defined and strictly enforced. It is also recommended that utilities distributing misleading information about nuclear power risks shall have their operating license withdrawn. 37 refs.

  9. Report on nuclear safety in EU applicant countries

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Nuclear safety in the candidate countries to the European Union is a major issue which needs to be addressed in the frame of the enlargement process. The Heads of the nuclear safety Regulatory Bodies of the European Union member states having nuclear power plants, i.e. Belgium, Finland, France, Germany, Italy, the Netherlands, Spain, Sweden and the United Kingdom thought it was their duty to offer their assistance to the European Union institutions at a moment when the expansion of the Union is being considered. As a consequence, they decided to issue a report giving their collective opinion on nuclear safety in those applicant countries having at least one nuclear power reactor (Bulgaria, Czech Republic, Hungary, Lithuania, Romania, Slovak Republic, Slovenia) and covering: the status of the regulatory regime and regulatory body and the nuclear power plant safety status. This report is based on the knowledge they gained through multilateral assistance programmes, in particular the Phare programmes, and also through bilateral contacts. It must be stressed that in some cases, they recognised that their current knowledge was not sufficient to express a clear and exhaustive opinion. Also, it should be pointed out that the judgements are based on widely applied Western European design standards for the defence-in-depth and associated barriers. Quantitative comparisons of Probabilistic Safety Assessments have not been used as the available results are of widely different depth and quality. They also recognised that such a report could only present the situation at a given moment and they intend to periodically update it so as to reflect the changes which may occur in these countries. At this stage, the report does not cover radioactive waste or radiation protection issues in any detail. After they had taken the decision to issue this report, they decided to create an association, the Western European Nuclear Regulators Association (WENRA) in order to increase the co

  10. Nuclear Safety Design Base for License Application

    Energy Technology Data Exchange (ETDEWEB)

    R.J. Garrett

    2005-09-29

    The purpose of this report is to identify and document the nuclear safety design requirements that are specific to structures, systems, and components (SSCs) of the repository that are important to safety (ITS) during the preclosure period and to support the preclosure safety analysis and the license application for the high-level radioactive waste (HLW) repository at Yucca Mountain, Nevada. The scope of this report includes the assignment of nuclear safety design requirements to SSCs that are ITS and does not include the assignment of design requirements to SSCs or natural or engineered barriers that are important to waste isolation (ITWI). These requirements are used as input for the design of the SSCs that are ITS such that the preclosure performance objectives of 10 CFR 63.111(b) [DIRS 173273] are met. The natural or engineered barriers that are important to meeting the postclosure performance objectives of 10 CFR 63.113(b) and (c) [DIRS 173273] are identified as ITWI. Although a structure, system, or component (SSC) that is ITS may also be ITWI, this report is only concerned with providing the nuclear safety requirements for SSCs that are ITS to prevent or mitigate event sequences during the repository preclosure period.

  11. Current safety issues of CANDU licensing

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Y. [University of Ottawa, Ottawa (Canada); Natalizio, A. [ENSAC Associates, Ontario (Canada)

    1994-01-15

    As requested by Korea Institute of Nuclear Safety(KINS), the status of five generic licensing issues has been examined and their potential impact on a new plant that would be constructed in Canada has been evaluated. The results and conclusions of this evaluation are summarized as follows: steam explosion in calandria, hydrogen explosion in containment, use of PSA in reactor licensing, human factors, safety critical software.

  12. Sociodrama approach for enhancing nuclear safety

    Energy Technology Data Exchange (ETDEWEB)

    Choi, K. S.; Kim, C. B.; Ha, Y. H. [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

    2004-07-01

    A role playing or sociodrama has been experimentally conducted among residents from 4 NPP sites in Korea and KINS employees as a psychological approach for enhancing nuclear safety and improving public communication and public confidence in regulator in Dec. 2004. In this paper, the results were analyzed and presented and future plan and area of further study were suggested. This socio-psychological approach can be used as a new communication method for improving mutual understanding between residents and NPP operators at sites. It can be also used to solve conflicts among stakeholders and interest groups in nuclear industry.

  13. Nuclear Safety Research Department annual report 2000

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Damkjaer, A.; Nielsen, S.P.; Nonboel, E

    2001-08-01

    The report presents a summary of the work of the Nuclear Safety Research Department in 2000. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. In addition the department was responsible for the tasks 'Applied Health Physics and Emergency Preparedness', 'Dosimetry', 'Environmental Monitoring', and Irradiation and Isotope Services'. Lists of publications, committee memberships and staff members are included. (au)

  14. The role of nuclear law in nuclear safety after Fukushima; El rol del derecho nuclear en seguridad nuclear luego de Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    Cardozo, Diva E. Puig, E-mail: d.puig@adinet.com.uy [International Nuclear Law Association (INLA), Montevideo (Uruguay)

    2013-07-01

    The paper contains the following topics: nuclear law, origin and evolution, role of the legal instruments on nuclear safety, nuclear safety the impact of major nuclear accidents: Chernobyl and Fukushima. The response of the nuclear law post Fukushima. Safety and security. International framework for nuclear safety: nuclear convention joint convention on safety on spent fuel management and on the safety of radioactive waste management. The Fukushima World Conference on Nuclear Safety. Convention on Prompt Notification and Assistance in case of a Nuclear Accident or Radiological Emergency. Plan of Action for Nuclear Safety. IAEA recommendations for the safety transport of radioactive material. International framework for nuclear security. Convention on the Physical Protection of Nuclear Materials. International Convention for the Suppression of Acts Against Nuclear Terrorism. Resolution No. 1540 of the Security Council of United Nations (2004). Measures to strengthen international safety. Code of conduct on the safety research reactor.

  15. Double-clad nuclear fuel safety rod

    Science.gov (United States)

    McCarthy, William H.; Atcheson, Donald B.; Vaidyanathan, Swaminathan

    1984-01-01

    A device for shutting down a nuclear reactor during an undercooling or overpower event, whether or not the reactor's scram system operates properly. This is accomplished by double-clad fuel safety rods positioned at various locations throughout the reactor core, wherein melting of a secondary internal cladding of the rod allows the fuel column therein to shift from the reactor core to place the reactor in a subcritical condition.

  16. Safety aspects of nuclear waste disposal in space

    Science.gov (United States)

    Rice, E. E.; Edgecombe, D. S.; Compton, P. R.

    1981-01-01

    Safety issues involved in the disposal of nuclear wastes in space as a complement to mined geologic repositories are examined as part of an assessment of the feasibility of nuclear waste disposal in space. General safety guidelines for space disposal developed in the areas of radiation exposure and shielding, containment, accident environments, criticality, post-accident recovery, monitoring systems and isolation are presented for a nuclear waste disposal in space mission employing conventional space technology such as the Space Shuttle. The current reference concept under consideration by NASA and DOE is then examined in detail, with attention given to the waste source and mix, the waste form, waste processing and payload fabrication, shipping casks and ground transport vehicles, launch site operations and facilities, Shuttle-derived launch vehicle, orbit transfer vehicle, orbital operations and space destination, and the system safety aspects of the concept are discussed for each component. It is pointed out that future work remains in the development of an improved basis for the safety guidelines and the determination of the possible benefits and costs of the space disposal option for nuclear wastes.

  17. A study in improvement of administrative system in the nuclear safety regulation

    Energy Technology Data Exchange (ETDEWEB)

    Yook, Dong Il; Kuk, Doe Hyeong; Lee, Seong Min; Kim, Jong Sam; Hwang, Sun Ho [Chungnam National Univ., Taejon (Korea, Republic of)

    2001-03-15

    One of the most important tasks to improve nuclear safety regulation system is to separate nuclear regulatory institutes from public agencies which promote the development nuclear power. Moreover, nuclear safety regulation should be not only specialized but optimized to be adapted for new environments such as high-tech information age. Especially, it is necessary to reform the current nuclear safety regulation systems both to be effective under the local self-administration which began to operate in recent years and to be supported by local residents.

  18. Nuclear Safety: Technical progress review, January--March 1989

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E. G. [ed.

    1989-01-01

    This review journal covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  19. Nuclear Safety: Technical progress review, January-March 1988

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1988-01-01

    This journal covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  20. Nuclear Safety. Technical progress journal: Volume 35, No.2

    Energy Technology Data Exchange (ETDEWEB)

    None

    1994-09-01

    This journal covers significant issues in the field of nuclear safety. Its primary scope is safety in the design, construction, operation, and de commissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities.

  1. Safety in nuclear power plants in India

    Directory of Open Access Journals (Sweden)

    Deolalikar R

    2008-01-01

    Full Text Available Safety in nuclear power plants (NPPs in India is a very important topic and it is necessary to dissipate correct information to all the readers and the public at large. In this article, I have briefly described how the safety in our NPPs is maintained. Safety is accorded overriding priority in all the activities. NPPs in India are not only safe but are also well regulated, have proper radiological protection of workers and the public, regular surveillance, dosimetry, approved standard operating and maintenance procedures, a well-defined waste management methodology, proper well documented and periodically rehearsed emergency preparedness and disaster management plans. The NPPs have occupational health policies covering periodic medical examinations, dosimetry and bioassay and are backed-up by fully equipped Personnel Decontamination Centers manned by doctors qualified in Occupational and Industrial Health. All the operating plants are ISO 14001 and IS 18001 certified plants. The Nuclear Power Corporation of India Limited today has 17 operating plants and five plants under construction, and our scientists and engineers are fully geared to take up many more in order to meet the national requirements.

  2. Safety in nuclear power plants in India.

    Science.gov (United States)

    Deolalikar, R

    2008-12-01

    Safety in nuclear power plants (NPPs) in India is a very important topic and it is necessary to dissipate correct information to all the readers and the public at large. In this article, I have briefly described how the safety in our NPPs is maintained. Safety is accorded overriding priority in all the activities. NPPs in India are not only safe but are also well regulated, have proper radiological protection of workers and the public, regular surveillance, dosimetry, approved standard operating and maintenance procedures, a well-defined waste management methodology, proper well documented and periodically rehearsed emergency preparedness and disaster management plans. The NPPs have occupational health policies covering periodic medical examinations, dosimetry and bioassay and are backed-up by fully equipped Personnel Decontamination Centers manned by doctors qualified in Occupational and Industrial Health. All the operating plants are ISO 14001 and IS 18001 certified plants. The Nuclear Power Corporation of India Limited today has 17 operating plants and five plants under construction, and our scientists and engineers are fully geared to take up many more in order to meet the national requirements.

  3. Current challenges for education of nuclear engineers. Beyond nuclear basics

    Energy Technology Data Exchange (ETDEWEB)

    Schoenfelder, Christian [AREVA GmbH, Offenbach (Germany). Training Center

    2014-07-15

    In past decades, curricula for the education of nuclear engineers (either as a major or minor subject) have been well established all over the world. However, from the point of view of a nuclear supplier, recent experiences in large and complex new build as well as modernization projects have shown that important competences required in these projects were not addressed during the education of young graduates. Consequently, in the past nuclear industry has been obliged to either accept long periods for job familiarization, or to develop and implement various dedicated internal training measures. Although the topics normally addressed in nuclear engineering education (like neutron and reactor physics, nuclear materials or thermohydraulics and the associated calculation methods) build up important competences, this paper shows that the current status of nuclear applications requires adaptations of educational curricula. As a conclusion, when academic nuclear engineering curricula start taking into account current competence needs in nuclear industry, it will be for the benefit of the current and future generation of nuclear engineers. They will be better prepared for their future job positions and career perspectives, especially on an international level. The recommendations presented should not only be of importance for the nuclear fission field, but also for the fusion community. Here, the Horizon 2020 Roadmap to Fusion as published in 2012 now is focusing on ITER and on a longer-term development of fusion technology for a future demonstration reactor DEMO. The very challenging work program is leading to a strong need for exactly those skills that are described in this article.

  4. Safety and effective developing nuclear power to realize green and low-carbon development

    Directory of Open Access Journals (Sweden)

    Qi-Zhen Ye

    2016-03-01

    Full Text Available This paper analyzes the role of nuclear power of China's energy structure and industry system. Comparing with other renewable energy the nuclear power chain has very low greenhouse gas emission, so it will play more important role in China's low-carbon economy. The paper also discussed the necessity of nuclear power development to achieve emission reduction, energy structure adjustment, nuclear power safety, environmental protection, enhancement of nuclear power technology, nuclear waste treatment, and disposal, as well as nuclear power plant decommissioning. Based on the safety record and situation of the existing power plants in China, the current status of the development of world nuclear power technology, and the features of the independently designed advanced power plants in China, this paper aims to demonstrate the safety of nuclear power. A nuclear power plant will not cause harm either to the environment and nor to the public according to the real data of radioactivity release, which are obtained from an operational nuclear plant. The development of nuclear power technology can enhance the safety of nuclear power. Further, this paper discusses issues related to the nuclear fuel cycle, the treatment, and disposal strategies of nuclear waste, and the decommissioning of a nuclear power plant, all of which are issues of public concern.

  5. Geological safety aspects of nuclear waste disposalin in Finland

    Energy Technology Data Exchange (ETDEWEB)

    Ahonen, L.; Hakkarainen, V.; Kaija, J.; Kuivamaki, A.; Lindberg, A.; Paananen, M.; Paulamaki, S.; Ruskeeniemi, T., e-mail: lasse.ahonen@gtk.fi

    2011-07-01

    The management of nuclear waste from Finnish power companies is based on the final geological disposal of encapsulated spent fuel at a depth of several hundreds of metres in the crystalline bedrock. Permission for the licence requires that the safety of disposal is demonstrated in a safety case showing that processes, events and future scenarios possibly affecting the performance of the deep repository are appropriately understood. Many of the safety-related issues are geological in nature. The Precambrian bedrock of Finland has a long history, even if compared with the time span considered for nuclear waste disposal, but the northern location calls for a detailed study of the processes related to Quaternary glaciations. This was manifested in an extensive international permafrost study in northern Canada, coordinated by GTK. Hydrogeology and the common existence of saline waters deep in the bedrock have also been targets of extensive studies, because water chemistry affects the chemical stability of the repository near-field, as well as radionuclide transport. The Palmottu natural analogue study was one of the international high-priority natural analogue studies in which transport phenomena were explored in a natural geological system. Currently, deep biosphere processes are being investigated in support of the safety of nuclear waste disposal. (orig.)

  6. Nuclear Safety: Volume 29, No. 3: Technical progress review

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1988-07-01

    Nuclear Safety is a review journal that covers significant development in the field of nuclear safety. Its scope included the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated. Individual papers have been cataloged separately.

  7. 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.

  8. 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.

  9. 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.

  10. Proceedings of the international meeting on thermal nuclear reactor safety. Vol. 1

    Energy Technology Data Exchange (ETDEWEB)

    None

    1983-02-01

    Separate abstracts are included for each of the papers presented concerning current issues in nuclear power plant safety; national programs in nuclear power plant safety; radiological source terms; probabilistic risk assessment methods and techniques; non LOCA and small-break-LOCA transients; safety goals; pressurized thermal shocks; applications of reliability and risk methods to probabilistic risk assessment; human factors and man-machine interface; and data bases and special applications.

  11. Review of Policy Documents for Nuclear Safety and Regulation

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Woong Sik; Choi, Kwang Sik; Choi, Young Sung; Kim, Hho Jung; Kim, Ho Ki [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

    2006-07-01

    The goal of regulation is to protect public health and safety as well as environment from radiological hazards that may occur as a result of the use of atomic energy. In September 1994, the Korean government issued the Nuclear Safety Policy Statement (NSPS) to establish policy goals of maintaining and achieving high-level of nuclear safety and also help the public understand the national policy and a strong will of the government toward nuclear safety. It declares the importance of establishing safety culture in nuclear community and also specifies five nuclear regulatory principles (Independence, Openness, Clarity, Efficiency and Reliability) and provides the eleven regulatory policy directions. In 2001, the Nuclear Safety Charter was declared to make the highest goal of safety in driving nuclear business clearer; to encourage atomic energy- related institutions and workers to keep in mind the mission and responsibility for assuring safety; to guarantee public confidence in related organizations. The Ministry of Science and Technology (MOST) also issues Yearly Regulatory Policy Directions at the beginning of every year. Recently, the third Atomic Energy Promotion Plan (2007-2011) has been established. It becomes necessary for the relevant organizations to prepare the detailed plans on such areas as nuclear development, safety management, regulation, etc. This paper introduces a multi-level structure of nuclear safety and regulation policy documents in Korea and presents some improvements necessary for better application of the policies.

  12. Natural Disasters and Safety Risks at Nuclear Power Stations

    Science.gov (United States)

    Tutnova, T.

    2012-04-01

    In the aftermath of Fukushima natural-technological disaster the global opinion on nuclear energy divided even deeper. While Germany, Italy and the USA are currently reevaluating their previous plans on nuclear growth, many states are committed to expand nuclear energy output. In China and France, where the industry is widely supported by policymakers, there is little talk about abandoning further development of nuclear energy. Moreover, China displays the most remarkable pace of nuclear development in the world: it is responsible for 40% of worldwide reactors under construction, and aims at least to quadruple its nuclear capacity by 2020. In these states the consequences of Fukushima natural-technological accident will probably result in safety checks and advancement of new reactor technologies. Thus, China is buying newer reactor design from the USA which relies on "passive safety systems". It means that emergency power generators, crucial for reactor cooling in case of an accident, won't depend on electricity, so that tsunami won't disable them like it happened in the case of Fukushima. Nuclear energy managed to draw lessons from previous nuclear accidents where technological and human factors played crucial role. But the Fukushima lesson shows that the natural hazards, nevertheless, were undervalued. Though the ongoing technological advancements make it possible to increase the safety of nuclear power plants with consideration of natural risks, it is not just a question of technology improvement. A necessary action that must be taken is the reevaluation of the character and sources of the potential hazards which natural disasters can bring to nuclear industry. One of the examples is a devastating impact of more than one natural disaster happening at the same time. This subject, in fact, was not taken into account before, while it must be a significant point in planning sites for new nuclear power plants. Another important lesson unveiled is that world nuclear

  13. Seismic safety in nuclear-waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Carpenter, D.W.; Towse, D.

    1979-04-26

    Seismic safety is one of the factors that must be considered in the disposal of nuclear waste in deep geologic media. This report reviews the data on damage to underground equipment and structures from earthquakes, the record of associated motions, and the conventional methods of seismic safety-analysis and engineering. Safety considerations may be divided into two classes: those during the operational life of a disposal facility, and those pertinent to the post-decommissioning life of the facility. Operational hazards may be mitigated by conventional construction practices and site selection criteria. Events that would materially affect the long-term integrity of a decommissioned facility appear to be highly unlikely and can be substantially avoided by conservative site selection and facility design. These events include substantial fault movement within the disposal facility and severe ground shaking in an earthquake epicentral region. Techniques need to be developed to address the question of long-term earthquake probability in relatively aseismic regions, and for discriminating between active and extinct faults in regions where earthquake activity does not result in surface ruptures.

  14. Development of the Advanced Nuclear Safety Information Management (ANSIM) System

    Energy Technology Data Exchange (ETDEWEB)

    Sohn, Jae Min; Ko, Young Cheol; Song, Tai Gil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    Korea has become a technically independent nuclear country and has grown into an exporter of nuclear technologies. Thus, nuclear facilities are increasing in significance at KAERI (Korea Atomic Energy Research Institute), and it is time to address the nuclear safety. The importance of nuclear safety cannot be overemphasized. Therefore, a management system is needed urgently to manage the safety of nuclear facilities and to enhance the efficiency of nuclear information. We have established ISP (Information Strategy Planning) for the Integrated Information System of nuclear facility and safety management. The purpose of this paper is to develop a management system for nuclear safety. Therefore, we developed the Advanced Nuclear Safety Information Management system (hereinafter referred to as the 'ANSIM system'). The ANSIM system has been designed and implemented to computerize nuclear safety information for standardization, integration, and sharing in real-time. Figure 1 shows the main home page of the ANSIM system. In this paper, we describe the design requirements, contents, configurations, and utilizations of the ANSIM system

  15. Safety related events at nuclear installations in 1995

    DEFF Research Database (Denmark)

    Korsbech, Uffe C C

    1996-01-01

    Nuclear safety related events of significance at least corresponding to level 2 of the International Nuclear Event Scale are described. In 1995 only two events occured at nuclear power plants, and four events occured at plants using ionizing radiation for processing or research.......Nuclear safety related events of significance at least corresponding to level 2 of the International Nuclear Event Scale are described. In 1995 only two events occured at nuclear power plants, and four events occured at plants using ionizing radiation for processing or research....

  16. Current Abstracts Nuclear Reactors and Technology

    Energy Technology Data Exchange (ETDEWEB)

    Bales, J.D.; Hicks, S.C. [eds.

    1993-01-01

    This publication Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency`s Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on the Energy Science and Technology Database and Nuclear Science Abstracts (NSA) database. Current information, added daily to the Energy Science and Technology Database, is available to DOE and its contractors through the DOE Integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user`s needs.

  17. Progress in high energy physics and nuclear safety : Proceedings of the NATO Advanced Research Workshop on Safe Nuclear Energy

    CERN Document Server

    Polański, Aleksander; Begun, Viktor

    2009-01-01

    The book contains recent results on the progress in high-energy physics, accelerator, detection and nuclear technologies, as well as nuclear safety in high-energy experimentation and in nuclear industry, covered by leading experts in the field. The forthcoming experiments at the Large Hadron Collider (LHC) at CERN and cosmic-ray experiments are highlighted. Most of the current high-energy experiments and their physical motivation are analyzed. Various nuclear energy safety aspects, including progress in the production of new radiation-resistant materials, new and safe nuclear reactor designs, such as the slowly-burning reactor, as well as the use of coal-nuclear symbiotic methods of energy production can be found in the book.

  18. National report of Brazil: nuclear safety convention - September 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This National Report was prepared by a group composed of representatives of the various Brazilian organizations with responsibilities in the field of nuclear safety, aiming the fulfilling the Convention of Nuclear Energy obligations. The Report contains a description of the Brazilian policy and programme on the safety of nuclear installations, and an article by article description of the measures Brazil is undertaking in order to implement the obligations described in the Convention. The last chapter describes plans and future activities to further enhance the safety of nuclear installations in Brazil.

  19. Nuclear Plant/Hydrogen Plant Safety: Issues and Approaches

    Energy Technology Data Exchange (ETDEWEB)

    Steven R. Sherman

    2007-06-01

    The U.S. Department of Energy, through its agents the Next Generation Nuclear Plant Project and the Nuclear Hydrogen Initiative, is working on developing the technologies to enable the large scale production of hydrogen using nuclear power. A very important consideration in the design of a co-located and connected nuclear plant/hydrogen plant facility is safety. This study provides an overview of the safety issues associated with a combined plant and discusses approaches for categorizing, quantifying, and addressing the safety risks.

  20. The Department of Energy Nuclear Criticality Safety Program

    Science.gov (United States)

    Felty, James R.

    2005-05-01

    This paper broadly covers key events and activities from which the Department of Energy Nuclear Criticality Safety Program (NCSP) evolved. The NCSP maintains fundamental infrastructure that supports operational criticality safety programs. This infrastructure includes continued development and maintenance of key calculational tools, differential and integral data measurements, benchmark compilation, development of training resources, hands-on training, and web-based systems to enhance information preservation and dissemination. The NCSP was initiated in response to Defense Nuclear Facilities Safety Board Recommendation 97-2, Criticality Safety, and evolved from a predecessor program, the Nuclear Criticality Predictability Program, that was initiated in response to Defense Nuclear Facilities Safety Board Recommendation 93-2, The Need for Critical Experiment Capability. This paper also discusses the role Dr. Sol Pearlstein played in helping the Department of Energy lay the foundation for a robust and enduring criticality safety infrastructure.

  1. Public opinion poll on safety and regulations of nuclear energy

    Energy Technology Data Exchange (ETDEWEB)

    Park, M. I.; Park, B. I.; Lee, S. M. [Gallup Korea, Seoul (Korea, Republic of)

    2004-02-15

    The purpose of this poll is not only to research understanding on safety and regulations of nuclear energy and to compare the result by time series followed 2003 to 2002 years, also to establish the public relations strategies and to offer information for developing long-term policies. The contents of the study are on the general perception, safety, management of nuclear power station, regulations and surroundings about nuclear energy.

  2. The current state of FPGA technology in the nuclear domain

    Energy Technology Data Exchange (ETDEWEB)

    Ranta, J.

    2012-07-01

    Field programmable gate arrays are a form of programmable electronic device used in various applications including automation systems. In recent years, there has been a growing interest in the use of FPGA-based systems also for safety automation of nuclear power plants. The interest is driven by the need for reliable new alternatives to replace, on one hand, the aging technology currently in use and, on the other hand, microprocessor and software-based systems, which are seen as overly complex from the safety evaluation point of view. This report presents an overview of FPGA technology, including hardware aspects, the application development process, risks and advantages of the technology, and introduces some of the current systems. FPGAs contain an interesting combination of features from software-based and fully hardware-based systems. Application development has a great deal in common with software development, but the final product is a hardware component without the operating system and other platform functions on which software would execute. Currently the number of FPGA-based applications used for safety functions of nuclear power plants is rather limited, but it is growing. So far there is little experience or common solid understanding between different parties on how FPGAs should be evaluated and handled in the licensing process. (orig.)

  3. Providing Nuclear Criticality Safety Analysis Education through Benchmark Experiment Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    John D. Bess; J. Blair Briggs; David W. Nigg

    2009-11-01

    One of the challenges that today's new workforce of nuclear criticality safety engineers face is the opportunity to provide assessment of nuclear systems and establish safety guidelines without having received significant experience or hands-on training prior to graduation. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and/or the International Reactor Physics Experiment Evaluation Project (IRPhEP) provides students and young professionals the opportunity to gain experience and enhance critical engineering skills.

  4. Safety related events at nuclear installations in 1995

    DEFF Research Database (Denmark)

    Korsbech, Uffe C C

    1996-01-01

    Nuclear safety related events of significance at least corresponding to level 2 of the International Nuclear Event Scale are described. In 1995 only two events occured at nuclear power plants, and four events occured at plants using ionizing radiation for processing or research....

  5. Nuclear power and nuclear safety 2009; Kernekraft og nuklear sikkerhed 2009

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, B.; OElgaard, P.L. (eds.); Nonboel, E. (Risoe DTU, Roskilde (Denmark)); Kampmann, D.; Nystrup, P.E.; Thorlaksen, B. (Beredskabsstyrelsen, Birkeroed (Denmark))

    2010-05-15

    The report is the seventh report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2009 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations, conflicts and the European safety directive. (LN)

  6. Review of Current Nuclear Vacuum System Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Carroll, M.; McCracken, J.; Shope, T.

    2003-02-25

    Nearly all industrial operations generate unwanted dust, particulate matter, and/or liquid wastes. Waste dust and particulates can be readily tracked to other work locations, and airborne particulates can be spread through ventilation systems to all locations within a building, and even vented outside the building - a serious concern for processes involving hazardous, radioactive, or nuclear materials. Several varieties of vacuum systems have been proposed and/or are commercially available for clean up of both solid and liquid hazardous and nuclear materials. A review of current technologies highlights both the advantages and disadvantages of the various systems, and demonstrates the need for a system designed to address issues specific to hazardous and nuclear material cleanup. A review of previous and current hazardous/nuclear material cleanup technologies is presented. From simple conventional vacuums modified for use in industrial operations, to systems specifically engineered for such purposes, the advantages and disadvantages are examined in light of the following criteria: minimal worker exposure; minimal secondary waste generation;reduced equipment maintenance and consumable parts; simplicity of design, yet fully compatible with all waste types; and ease of use. The work effort reviews past, existing and proposed technologies in light of such considerations. Accomplishments of selected systems are presented, including identified areas where technological improvements could be suggested.

  7. On safety management and nuclear safety - A frame of reference for studies of safety management with examples from non-nuclear contects of relevance for nuclear safety

    Energy Technology Data Exchange (ETDEWEB)

    Svenson, O.; Allwin, P. [Stockholm Univ. (Sweden); Salo, I. [Lund Univ. (Sweden)

    2004-03-01

    The report includes three case studies of safety management. The studies are presented as chapters, but are written in a format that makes them easy to read separately. Two of the studies cover regulators (the Swedish Civil Aviation Safety Authority, Luftfartsinspektionen) and the Norwegian Petroleum Directorate) and one a regulated activity/industry (a car manufacturer, Volvo Car). The introduction outlines a living system framework and relates this to concepts used in organizational management. The report concludes with some findings with potential relevance for safety management in the nuclear power domain. In the next phase of the work, the regulated counterparts of the regulators here will be investigated in addition to a fourth case study of a regulated activity/industry. (au)

  8. Nuclear power and nuclear safety 2007; Kernekraft og nuklear sikkerhed 2007

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, B.; OElgaard, P.L. (eds.); Kampmann, D.; Majborn, B.; Nonboel, E.; Nystrup, P.E.

    2008-05-15

    The report is the fifth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2007 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events of nuclear power, and international relations and conflicts. (LN)

  9. Nuclear power and nuclear safety 2008; Kernekraft og nuklear sikkerhed 2008

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, B.; OElgaard, P.L. (eds.); Nonboel, E. (Risoe DTU, Roskilde (Denmark)); Kampmann, D. (Beredskabsstyrelsen, Birkeroed (Denmark))

    2009-06-15

    The report is the fifth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2008 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events of nuclear power, and international relations and conflicts. (LN)

  10. Nuclear power and nuclear safety 2004; Kernekraft og nuklear sikkerhed 2004

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-03-01

    The report is the second report in a new series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2004 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power and international relations and conflicts. (ln)

  11. Nuclear power and nuclear safety 2006; Kernekraft og nuklear sikkerhed 2006

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, B.; Oelgaard, P.L. (eds.); Kampmann, D.; Majborn, B.; Nonboel, E.; Nystrup, P.E.

    2007-04-15

    The report is the fourth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2006 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power, and international relations and conflicts. (LN)

  12. Nuclear power and nuclear safety 2005; Kernekraft of nuklear sikkerhed 2005

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, B.; Oelgaard, P.L.; Kampman, D.; Majborn, B.; Nonboel, E.; Nystrup, P.E.

    2006-03-15

    The report is the third report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2005 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power and international relations and conflicts. (ln)

  13. Nuclear Technology Series. Course 8: Reactor Safety.

    Science.gov (United States)

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

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutians in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  14. Core safety of Indian nuclear power plants (NPPs) under extreme conditions

    Indian Academy of Sciences (India)

    J B Joshi; A K Nayak; M Singhal; D Mukhopadhaya

    2013-10-01

    Nuclear power is currently the fourth largest source of electricity production in India after thermal, hydro and renewable sources of electricity. Currently, India has 20 nuclear reactors in operation and seven other reactors are under construction. Most of these reactors are indigenously designed and built Heavy Water Reactors. In addition, a 300 MWe Advanced Heavy Water Reactor has already been designed and in the process of deployment in near future for demonstration of power production from Thorium apart from enhanced safety features by passive means. India has ambitious plans to enhance the share of electricity production from nuclear. The recent Fukushima accident has raised concerns of safety of Nuclear Power Plants worldwide. The Fukushima accident was caused by extreme events, i.e., large earthquake followed by gigantic Tsunami which are not expected to hit India’s coast considering the geography of India and historical records. Nevertheless, systematic investigations have been conducted by nuclear scientists in India to evaluate the safety of the current Nuclear Power Plants in case of occurrence of such extreme events in any nuclear site. This paper gives a brief outline of the safety features of Indian Heavy Water Reactors for prevention and mitigation of such extreme events. The probabilistic safety analysis revealed that the risk from Indian Heavy Water Reactors are negligibly small.

  15. Nuclear Criticality Safety Handbook, Version 2. English translation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-08-01

    The Nuclear Criticality Safety Handbook, Version 2 essentially includes the description of the Supplement Report to the Nuclear Criticality Safety Handbook, released in 1995, into the first version of the Nuclear Criticality Safety Handbook, published in 1988. The following two points are new: (1) exemplifying safety margins related to modeled dissolution and extraction processes, (2) describing evaluation methods and alarm system for criticality accidents. Revision has been made based on previous studies for the chapter that treats modeling the fuel system: e.g., the fuel grain size that the system can be regarded as homogeneous, non-uniformity effect of fuel solution, an burnup credit. This revision has solved the inconsistencies found in the first version between the evaluation of errors found in JACS code system and the criticality condition data that were calculated based on the evaluation. This report is an English translation of the Nuclear Criticality Safety Handbook, Version 2, originally published in Japanese as JAERI 1340 in 1999. (author)

  16. A Methodology for Evaluating Quantitative Nuclear Safety Culture Impact

    Energy Technology Data Exchange (ETDEWEB)

    Han, Kiyoon; Jae, Moosung [Hanyang University, Seoul (Korea, Republic of)

    2015-05-15

    Through several accidents of NPPs including the Fukushima Daiichi in 2011 and Chernobyl accidents in 1986, nuclear safety culture has been emphasized in reactor safety world-widely. In Korea, KHNP evaluates the safety culture of NPP itself. KHNP developed the principles of the safety culture in consideration of the international standards. A questionnaire and interview questions are also developed based on these principles and it is used for evaluating the safety culture. However, existing methodology to evaluate the safety culture has some disadvantages. First, it is difficult to maintain the consistency of the assessment. Second, the period of safety culture assessment is too long (every two years) so it has limitations in preventing accidents occurred by a lack of safety culture. Third, it is not possible to measure the change in the risk of NPPs by weak safety culture since it is not clearly explains the effect of safety culture on the safety of NPPs. In this study, Safety Culture Impact Assessment Model (SCIAM) is developed overcoming these disadvantages. In this study, SCIAM which overcoming disadvantages of exiting safety culture assessment method is developed. SCIAM uses SCII to monitor the statues of the safety culture periodically and also uses RCDF to quantify the safety culture impact on NPP's safety. It is significant that SCIAM represents the standard of the healthy nuclear safety culture, while the exiting safety culture assessment presented only vulnerability of the safety culture of organization. SCIAM might contribute to monitoring the level of safety culture periodically and, to improving the safety of NPP.

  17. Licensed reactor nuclear safety criteria applicable to DOE reactors

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-01

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

  18. Evaluation of safety criteria on LOCA and RIA for high burnup nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sun Ki; Bang, Je Geon; Kim, Dae Ho; Yang, Yong Sik; Song, Keun Woo

    2007-12-15

    Comprehensive researches in many countries and some international research programs to investigate the applicability to high burnup nuclear fuels have been performing as the existing safety criteria of DBA such as LOCA and RIA was established several decades ago. In this report, main research programs for the safety criteria of DBA such as LOCA and RIA are introduced, and also the current status on the modification of the safety criteria are also introduced.

  19. Manual of functions, assignments, and responsibilities for nuclear safety: Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    1994-10-15

    The FAR Manual is a convenient easy-to-use collection of the functions, assignments, and responsibilities (FARs) of DOE nuclear safety personnel. Current DOE directives, including Orders, Secretary of Energy Notices, and other assorted policy memoranda, are the source of this information and form the basis of the FAR Manual. Today, the majority of FARs for DOE personnel are contained in DOE`s nuclear safety Orders. As these Orders are converted to rules in the Code of Federal Regulations, the FAR Manual will become the sole source for information relating to the functions, assignments, responsibilities of DOE nuclear safety personnel. The FAR Manual identifies DOE directives that relate to nuclear safety and the specific DOE personnel who are responsible for implementing them. The manual includes only FARs that have been extracted from active directives that have been approved in accordance with the procedures contained in DOE Order 1321.1B.

  20. Human Factors Research and Nuclear Safety.

    Science.gov (United States)

    Moray, Neville P., Ed.; Huey, Beverly M., Ed.

    The Panel on Human Factors Research Needs in Nuclear Regulatory Research was formed by the National Research Council in response to a request from the Nuclear Regulatory Commission (NRC). The NRC asked the research council to conduct an 18-month study of human factors research needs for the safe operation of nuclear power plants. This report…

  1. Nuclear Science and Safety in Europe

    CERN Document Server

    Čechák, Tomas; Karpenko, Iurii

    2006-01-01

    Presents results on the nature of low-, intermediate- and high-energy nuclear forces as well as on the internal structure of nucleons and atomic nuclei are presented. This work also discusses prospects to find a new state of the nuclear matter at extreme conditions that existed in the early Universe and the utilisation of nuclear energy.

  2. Licensed reactor nuclear safety criteria applicable to DOE reactors

    Energy Technology Data Exchange (ETDEWEB)

    1991-04-01

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

  3. A Study on Methodologies for Assessing Safety Critical Network's Risk Impact on Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Lim, T. J.; Park, S. K.; Seo, S. J. [Soongsil Univ., Seoul (Korea, Republic of)

    2007-04-15

    The objectives of this project is to establish methodologies for assessing safety-critical network's risk impact on nuclear power plant by developing reliability analysis models for the safety-critical network. It is essential to develop reliability analysis models for safety-critical network, and it is very important to adapt the model to the current methodologies for assessing risk impact on nuclear power plants. Major outputs of the first year study are preliminary models for assessing reliability of safety-critical communication networks and those of the second year study are methodologies for assessing safety-critical network's risk impact on nuclear power plant.

  4. Development of technology-neutral safety requirements for the regulation of future nuclear power reactors: Back to basics

    Energy Technology Data Exchange (ETDEWEB)

    Tronea, Madalina, E-mail: madalina.tronea@gmail.co [Faculty of Physics, University of Bucharest (Romania)

    2011-03-15

    This paper explores the current trends as regards the development of technology-neutral safety requirements to be used in the regulation of future nuclear power reactors and the role of the quantitative safety goals in the design of reactor safety systems. The use of the recommendations of the International Commission on Radiological Protection (ICRP) on protection against potential exposure could form the basis of a technology-neutral framework for safety requirements on new reactor designs and could contribute to international harmonisation of nuclear safety assessment practices as part of the licensing processes for future nuclear power plants.

  5. Enhancement of safety at nuclear facilities in Pakistan

    Energy Technology Data Exchange (ETDEWEB)

    Ahmad, S.A.; Hayat, T.; Azhar, W. [Directorate of Safety, Pakistan Atomic Energy Commission, P.O. Box 3416, Islamabad (Pakistan)

    2006-07-01

    Pakistan is benefiting from nuclear technology mostly in health and energy sectors as well as agriculture and industry and has an impeccable safety record. At the national level uses of nuclear technology started in 1955 resulting in the operation of Karachi Radioisotope Center, Karachi, in December 1960. Pakistan Nuclear Safety Committee (PNSC) was formulated in 1964 with subsequent promulgation of Pakistan Atomic Energy Commission (PAEC) Ordinance in 1965 to cope with the anticipated introduction of a research reactor, namely PARR-I, and a nuclear power plant, namely KANUPP. Since then Pakistan's nuclear program has expanded to include numerous nuclear facilities of varied nature. This program has definite economic and social impacts by producing electricity, treating and diagnosing cancer patients, and introducing better crop varieties. Appropriate radiation protection includes a number of measures including database of sealed radiation sources at PAEC operated nuclear facilities, see Table l, updated during periodic physical verification of these sources, strict adherence to the BSS-115, IAEA recommended enforcement of zoning at research reactors and NPPs, etc. Pakistan is party to several international conventions and treaties, such as Convention of Nuclear Safety and Early Notification, to improve and enhance safety at its nuclear facilities. In addition Pakistan generally and PAEC particularly believes in a blend of prudent regulations and good/best practices. This is described in this paper. (Author)

  6. Nuclear power plants and safety; Elektrownie jadrowe i bezpieczenstwo

    Energy Technology Data Exchange (ETDEWEB)

    Celinski, Z. [Politechnika Warszawska, Warsaw (Poland)

    1995-12-31

    The brief scope on the state of nuclear energetics worldwide as well as development perspectives have been presented. The safety problems, economic competitiveness and public acceptance have been shown and discussed. 55 refs, 3 figs, 2 tabs.

  7. Nuclear safety, Volume 38, Number 1, January--March 1997

    Energy Technology Data Exchange (ETDEWEB)

    None

    1997-03-01

    This journal contains nine articles which fall under the following categories: (1) general safety considerations; (2) control and instrumentation; (3) design features (4) environmental effects; (5) US Nuclear Regulatory Commission information and analyses; and (6) recent developments.

  8. A Safer Nuclear Enterprise - Application to Nuclear Explosive Safety (NES)(U)

    Energy Technology Data Exchange (ETDEWEB)

    Morris, Tommy J. [Los Alamos National Laboratory

    2012-07-05

    Activities and infrastructure that support nuclear weapons are facing significant challenges. Despite an admirable record and firm commitment to make safety a primary criterion in weapons design, production, handling, and deployment - there is growing apprehension about terrorist acquiring weapons or nuclear material. At the NES Workshop in May 2012, Scott Sagan, who is a proponent of the normal accident cycle, presented. Whether a proponent of the normal accident cycle or High Reliability Organizations - we have to be diligent about our safety record. Constant vigilance is necessary to maintain our admirable safety record and commitment to Nuclear Explosive Safety.

  9. Progress of experimental research on nuclear safety in NPIC

    Energy Technology Data Exchange (ETDEWEB)

    Gong, Houjun; Zan, Yuanfeng; Peng, Chuanxin; Xi, Zhao; Zhang, Zhen; Wang, Ying; He, Yanqiu; Huang, Yanping [Nuclear Power Institute of China, Chengdu (China)

    2016-05-15

    Two kinds of Generation III commercial nuclear power plants have been developed in CNNC (China National Nuclear Corporation), one is a small modular reactor ACP100 having an equivalent electric power 100 MW, and the other is HPR1000 (once named ACP1000) having an equivalent electric power 1 000 MW. Both NPPs widely adopted the design philosophy of advanced passive safety systems and considered the lessons from Fukushima Daichi nuclear accident. As the backbone of the R and D of ACP100 and HPR1000, NPIC (Nuclear power Institute of China) has finished the engineering verification test of main safety systems, including passive residual heat removal experiments, reactor cavity injection experiments, hydrogen combustion experiments, and passive autocatalytic recombiner experiments. Above experimental work conducted in NPIC and further research plan of nuclear safety are introduced in this paper.

  10. Current Developments in Nuclear Density Functional Methods

    CERN Document Server

    Dobaczewski, J

    2010-01-01

    Density functional theory (DFT) became a universal approach to compute ground-state and excited configurations of many-electron systems held together by an external one-body potential in condensed-matter, atomic, and molecular physics. At present, the DFT strategy is also intensely studied and applied in the area of nuclear structure. The nuclear DFT, a natural extension of the self-consistent mean-field theory, is a tool of choice for computations of ground-state properties and low-lying excitations of medium-mass and heavy nuclei. Over the past thirty-odd years, a lot of experience was accumulated in implementing, adjusting, and using the density-functional methods in nuclei. This research direction is still extremely actively pursued. In particular, current developments concentrate on (i) attempts to improve the performance and precision delivered by the nuclear density-functional methods, (ii) derivations of density functionals from first principles rooted in the low-energy chromodynamics and effective th...

  11. Periodic safety review of French nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Poirrier, D.; Debes, M. [Electricite de France, Paris (France)

    1997-12-01

    The safety of nuclear power plants (NPPs) is checked through different types of safety evaluations, for example, a continuous process, with followup of operational feedback and over-all evaluation every year by each NPP; specific examination, with the study of generic problems when they occur; and a 10-yr outage inspection. In France, the license does not explicitly require periodic safety reviews (PSRs), but an article has been added to the Decree of December 11, 1963 concerning nuclear installations that states, {open_quotes}The Ministers may jointly request the operating utility at any time to proceed to a review of nuclear safety,{close_quotes} which supports requests for PSRs from the safety authority.

  12. Information security as part of the nuclear safety culture

    Energy Technology Data Exchange (ETDEWEB)

    Sitnica, A., E-mail: demetrkj@westinghouse.com [Westinghouse Electric Co., 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

    2016-09-15

    No industry, organization, individual or even the government is immune to the information security risks which are associated with nuclear power. It can no longer be ignored, delayed or treated as unimportant. Nuclear safety is paramount to our industry, and cyber security must be woven into the fabric of our safety culture in order to succeed. Achieving this in an environment which has remained relatively unchanged and conservative prior to digitalisation demands a shift in behavior and culture. (Author)

  13. Nuclear power and nuclear safety 2010; Kernekraft og nuklear sikkerhed 2010

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, B.; OElgaard, P.L. (eds.); Nonboel, E. (Risoe DTU, Roskilde (Denmark)); Kampmann, D.; Nystrup, P.E. (Beredskabsstyrelsen, Birkeroed (Denmark))

    2011-07-15

    The report is the eighth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2010 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations, and conflicts and the Fukushima accident. (LN)

  14. Nuclear power and nuclear safety 2011; Kernekraft og nuklear sikkerhed 2011

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, B.; OElgaard, P.L. (eds.); Hedemann Jensen, P.; Nonboel, E. (Technical Univ. of Denmark. DTU Risoe Campus, Roskilde (Denmark)); Aage, H.K.; Kampmann, D.; Nystrup, P.E.; Thomsen, J. (Beredskabsstyrelsen, Birkeroed (Denmark))

    2012-07-15

    The report is the ninth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2011 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations and conflicts, and the Fukushima accident. (LN)

  15. Nuclear power and nuclear safety 2012; Kernekraft og nuklear sikkerhed 2012

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, B.; Nonboel, E. (eds.); Oelgaard, P.L. [Technical Univ. of Denmark. DTU Risoe Campus, Roskilde (Denmark); Israelson, C.; Kampmann, D.; Nystrup, P.E.; Thomsen, J. [Beredskabsstyrelsen, Birkeroed (Denmark)

    2013-11-15

    The report is the tenth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is prepared in collaboration between DTU Nutech and the Danish Emergency Management Agency. The report for 2012 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations and conflicts, and the results of the EU stress test. (LN)

  16. Sixth national report of Brazil for the nuclear safety convention

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-07-01

    Brazil has presented periodically its National Report prepared by a group composed of representatives of the various Brazilian organizations with responsibilities related to nuclear safety. Due to the implications of the Fukushima nuclear accident in 2011, an Extraordinary National Report was presented in 2012. This Sixth National Report is an update of the Fifth National Report in relation to the Convention on Nuclear Safety articles and also an update of the Extraordinary Report with respect to the action taken related to lesson learned from the Fukushima accident. It includes relevant information for the period of 2010/2012. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations.

  17. Safety and security aspects in design of digital safety I and C in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Ding, Yongjian [University of Applied Sciences Magdeburg-Stendal, Magdeburg (Germany). Inst. of Electrical Engineering; Waedt, Karl [Areva GmbH, Erlangen (Germany). PEAS-G

    2016-05-15

    The paper describes a safety objective oriented systematic design approach of digital (computerized) safety I and C in modern nuclear power plants which considers the plant safety requirements as well as cybersecurity needs. The defence in depth philosophy is applied by using different defence lines in the I and C architecture and protection zones in the plant IT environment.

  18. Safety and Nuclear Power Sources for Space Systems

    Science.gov (United States)

    Segalas, Corinne C.; Schmidt, George R.

    2010-09-01

    Nuclear power sources have been used in space applications for decades. They have been used extensively for electrical power production, and their future potential for propulsion has been recognized since the dawn of the spaceflight era. Nuclear power sources offer many advantages in terms of long duration operation and high power densities independent of distance and orientation with respect to the Sun. However, it is also broadly known that use of radioactive materials do carry more risk that must be addressed to ensure safe operation during all phases of the mission, particularly before and during launch into orbit. Almost all of the nuclear-powered missions to date have been flown by the United States and former Soviet Union, but other space-faring nations have recognized its importance for their future missions. Consequently, many in the space community have advocated the development of a broad set of principles that could be applied on an international basis. This paper examines the current guidelines by the major space-faring nations, and suggests a framework primarily based on the U.S. methodology for ensuring reduction of risk, mitigating environmental impact and promoting launch safety.

  19. Nuclear power and nuclear safety 2003 (in Danish); Kernekraft og nuklear sikkerhed 2003

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, B.; Majborn, B.; Nonboel, E.; Oelgaard, P.L. (eds.)

    2004-03-01

    The report, 'Kernekraft og nuklear sikkerhed 2003' (Nuclear power and nuclear safe-ty 2003) is the first report in a new series of annual reports on the international devel-opment of nuclear power production, with special emphasis on safety issues and nu-clear emergency preparedness. The report series is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency and re-places the previous series, 'International kernekraftstatus' (International Nuclear Po-wer Status). The report for 2003 covers the following topics: status of nuclear power production and regional trends, development of reactors and emergency management systems, safety-related events with nuclear power production, and international rela-tions and conflicts. (au)

  20. Government: Nuclear Safety in Doubt a Year after Accident.

    Science.gov (United States)

    Ember, Lois R.

    1980-01-01

    A year after the accident at Three Mile Island (TMI), the signals transmitted to the public are still confused. Industry says that nuclear power is safe and that the aftermath of TMI ushers in a new era of safety. Antinuclear activists say TMI sounded nuclear power's death knell. (Author/RE)

  1. 48 CFR 923.7001 - Nuclear safety.

    Science.gov (United States)

    2010-10-01

    ... ENVIRONMENT, CONSERVATION, OCCUPATIONAL SAFETY, AND DRUG-FREE WORKPLACE Environmental, Energy and Water... Atomic Energy Act and other legislation. The DOE also regulates, under certain specific conditions,...

  2. Safety pharmacology — Current and emerging concepts

    Energy Technology Data Exchange (ETDEWEB)

    Hamdam, Junnat; Sethu, Swaminathan; Smith, Trevor; Alfirevic, Ana; Alhaidari, Mohammad [MRC Centre for Drug Safety Science, University of Liverpool (United Kingdom); Atkinson, Jeffrey [Lorraine University Pharmacolor Consultants Nancy PCN (France); Ayala, Mimieveshiofuo; Box, Helen; Cross, Michael [MRC Centre for Drug Safety Science, University of Liverpool (United Kingdom); Delaunois, Annie [UCB Pharma (Belgium); Dermody, Ailsa; Govindappa, Karthik [MRC Centre for Drug Safety Science, University of Liverpool (United Kingdom); Guillon, Jean-Michel [Sanofi-aventis (France); Jenkins, Rosalind [MRC Centre for Drug Safety Science, University of Liverpool (United Kingdom); Kenna, Gerry [Astra-Zeneca (United Kingdom); Lemmer, Björn [Ruprecht-Karls-Universität Heidelberg (Germany); Meecham, Ken [Huntingdon Life Sciences (United Kingdom); Olayanju, Adedamola [MRC Centre for Drug Safety Science, University of Liverpool (United Kingdom); Pestel, Sabine [Boehringer-Ingelheim (Germany); Rothfuss, Andreas [Roche (Switzerland); and others

    2013-12-01

    Safety pharmacology (SP) is an essential part of the drug development process that aims to identify and predict adverse effects prior to clinical trials. SP studies are described in the International Conference on Harmonisation (ICH) S7A and S7B guidelines. The core battery and supplemental SP studies evaluate effects of a new chemical entity (NCE) at both anticipated therapeutic and supra-therapeutic exposures on major organ systems, including cardiovascular, central nervous, respiratory, renal and gastrointestinal. This review outlines the current practices and emerging concepts in SP studies including frontloading, parallel assessment of core battery studies, use of non-standard species, biomarkers, and combining toxicology and SP assessments. Integration of the newer approaches to routine SP studies may significantly enhance the scope of SP by refining and providing mechanistic insight to potential adverse effects associated with test compounds. - Highlights: • SP — mandatory non-clinical risk assessments performed during drug development. • SP organ system studies ensure the safety of clinical participants in FiH trials. • Frontloading in SP facilitates lead candidate drug selection. • Emerging trends: integrating SP-Toxicological endpoints; combined core battery tests.

  3. Current status of nuclear physics research

    Energy Technology Data Exchange (ETDEWEB)

    Bertulani, Carlos A. [Department of Physics and Astronomy, Texas A and M University-Commerce (United States); Hussein, Mahir S., E-mail: hussein@if.usp.br [Instituto Tecnologico de Aeronautica (ITA), Sao Jose dos Campos, SP (Brazil). Dept. de Fisica

    2015-12-15

    In this review, we discuss the current status of research in nuclear physics which is being carried out in different centers in the world. For this purpose, we supply a short account of the development in the area which evolved over the last nine decades, since the discovery of the neutron. The evolution of the physics of the atomic nucleus went through many stages as more data became available. We briefly discuss models introduced to discern the physics behind the experimental discoveries, such as the shell model, the collective model, the statistical model, the interacting boson model, etc., some of these models may be seemingly in conflict with each other, but this was shown to be only apparent. The richness of the ideas and abundance of theoretical models attests to the important fact that the nucleus is a really singular system in the sense that it evolves from two-body bound states such as the deuteron, to few-body bound states, such as {sup 4}He, {sup 7}Li, {sup 9}Be, etc. and up the ladder to heavier bound nuclei containing up to more than 200 nucleons. Clearly, statistical mechanics, usually employed in systems with very large number of particles, would seemingly not work for such finite systems as the nuclei, neither do other theories which are applicable to condensed matter. The richness of nuclear physics stems from these restrictions. New theories and models are presently being developed. Theories of the structure and reactions of neutron-rich and proton-rich nuclei, called exotic nuclei, halo nuclei, or Borromean nuclei, deal with the wealth of experimental data that became available in the last 35 years. Furthermore, nuclear astrophysics and stellar and Big Bang nucleosynthesis have become a more mature subject. Due to limited space, this review only covers a few selected topics, mainly those with which the authors have worked on. Our aimed potential readers of this review are nuclear physicists and physicists in other areas, as well as graduate

  4. Current Status of Nuclear Physics Research

    Science.gov (United States)

    Bertulani, Carlos A.; Hussein, Mahir S.

    2015-12-01

    In this review, we discuss the current status of research in nuclear physics which is being carried out in different centers in the world. For this purpose, we supply a short account of the development in the area which evolved over the last nine decades, since the discovery of the neutron. The evolution of the physics of the atomic nucleus went through many stages as more data became available. We briefly discuss models introduced to discern the physics behind the experimental discoveries, such as the shell model, the collective model, the statistical model, the interacting boson model, etc., some of these models may be seemingly in conflict with each other, but this was shown to be only apparent. The richness of the ideas and abundance of theoretical models attests to the important fact that the nucleus is a really singular system in the sense that it evolves from two-body bound states such as the deuteron, to few-body bound states, such as 4He, 7Li, 9Be, etc. and up the ladder to heavier bound nuclei containing up to more than 200 nucleons. Clearly, statistical mechanics, usually employed in systems with very large number of particles, would seemingly not work for such finite systems as the nuclei, neither do other theories which are applicable to condensed matter. The richness of nuclear physics stems from these restrictions. New theories and models are presently being developed. Theories of the structure and reactions of neutron-rich and proton-rich nuclei, called exotic nuclei, halo nuclei, or Borromean nuclei, deal with the wealth of experimental data that became available in the last 35 years. Furthermore, nuclear astrophysics and stellar and Big Bang nucleosynthesis have become a more mature subject. Due to limited space, this review only covers a few selected topics, mainly those with which the authors have worked on. Our aimed potential readers of this review are nuclear physicists and physicists in other areas, as well as graduate students interested in

  5. Safety pharmacology--current and emerging concepts.

    Science.gov (United States)

    Hamdam, Junnat; Sethu, Swaminathan; Smith, Trevor; Alfirevic, Ana; Alhaidari, Mohammad; Atkinson, Jeffrey; Ayala, Mimieveshiofuo; Box, Helen; Cross, Michael; Delaunois, Annie; Dermody, Ailsa; Govindappa, Karthik; Guillon, Jean-Michel; Jenkins, Rosalind; Kenna, Gerry; Lemmer, Björn; Meecham, Ken; Olayanju, Adedamola; Pestel, Sabine; Rothfuss, Andreas; Sidaway, James; Sison-Young, Rowena; Smith, Emma; Stebbings, Richard; Tingle, Yulia; Valentin, Jean-Pierre; Williams, Awel; Williams, Dominic; Park, Kevin; Goldring, Christopher

    2013-12-01

    Safety pharmacology (SP) is an essential part of the drug development process that aims to identify and predict adverse effects prior to clinical trials. SP studies are described in the International Conference on Harmonisation (ICH) S7A and S7B guidelines. The core battery and supplemental SP studies evaluate effects of a new chemical entity (NCE) at both anticipated therapeutic and supra-therapeutic exposures on major organ systems, including cardiovascular, central nervous, respiratory, renal and gastrointestinal. This review outlines the current practices and emerging concepts in SP studies including frontloading, parallel assessment of core battery studies, use of non-standard species, biomarkers, and combining toxicology and SP assessments. Integration of the newer approaches to routine SP studies may significantly enhance the scope of SP by refining and providing mechanistic insight to potential adverse effects associated with test compounds. Copyright © 2013 Elsevier Inc. All rights reserved.

  6. NASA safety program activities in support of the Space Exploration Initiatives Nuclear Propulsion program

    Science.gov (United States)

    Sawyer, J. C., Jr.

    1993-01-01

    The activities of the joint NASA/DOE/DOD Nuclear Propulsion Program Technical Panels have been used as the basis for the current development of safety policies and requirements for the Space Exploration Initiatives (SEI) Nuclear Propulsion Technology development program. The Safety Division of the NASA Office of Safety and Mission Quality has initiated efforts to develop policies for the safe use of nuclear propulsion in space through involvement in the joint agency Nuclear Safety Policy Working Group (NSPWG), encouraged expansion of the initial policy development into proposed programmatic requirements, and suggested further expansion into the overall risk assessment and risk management process for the NASA Exploration Program. Similar efforts are underway within the Department of Energy to ensure the safe development and testing of nuclear propulsion systems on Earth. This paper describes the NASA safety policy related to requirements for the design of systems that may operate where Earth re-entry is a possibility. The expected plan of action is to support and oversee activities related to the technology development of nuclear propulsion in space, and support the overall safety and risk management program being developed for the NASA Exploration Program.

  7. Safety and Nonsafety Communications and Interactions in International Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kisner, Roger A [ORNL; Mullens, James Allen [ORNL; Wilson, Thomas L [ORNL; Wood, Richard Thomas [ORNL; Korsah, Kofi [ORNL; Qualls, A L [ORNL; Muhlheim, Michael David [ORNL; Holcomb, David Eugene [ORNL; Loebl, Andy [ORNL

    2007-08-01

    Current industry and NRC guidance documents such as IEEE 7-4.3.2, Reg. Guide 1.152, and IEEE 603 do not sufficiently define a level of detail for evaluating interdivisional communications independence. The NRC seeks to establish criteria for safety systems communications that can be uniformly applied in evaluation of a variety of safety system designs. This report focuses strictly on communication issues related to data sent between safety systems and between safety and nonsafety systems. Further, the report does not provide design guidance for communication systems nor present detailed failure modes and effects analysis (FMEA) results for existing designs. This letter report describes communications between safety and nonsafety systems in nuclear power plants outside the United States. A limited study of international nuclear power plants was conducted to ascertain important communication implementations that might have bearing on systems proposed for licensing in the United States. This report provides that following information: 1.communications types and structures used in a representative set of international nuclear power reactors, and 2.communications issues derived from standards and other source documents relevant to safety and nonsafety communications. Topics that are discussed include the following: communication among redundant safety divisions, communications between safety divisions and nonsafety systems, control of safety equipment from a nonsafety workstation, and connection of nonsafety programming, maintenance, and test equipment to redundant safety divisions during operation. Information for this report was obtained through publicly available sources such as published papers and presentations. No proprietary information is represented.

  8. Nuclear electric power safety, operation, and control aspects

    CERN Document Server

    Knowles, J Brian

    2013-01-01

    Assesses the engineering of renewable sources for commercial power generation and discusses the safety, operation, and control aspects of nuclear electric power From an expert who advised the European Commission and UK government in the aftermath of Three Mile Island and Chernobyl comes a book that contains experienced engineering assessments of the options for replacing the existing, aged, fossil-fired power stations with renewable, gas-fired, or nuclear plants. From geothermal, solar, and wind to tidal and hydro generation, Nuclear Electric Power: Safety, Operation, and Control Aspects ass

  9. Nuclear Power for Sustainable Development : Current Status and Future Prospects

    OpenAIRE

    Adamantiades, A.; Kessides, I.

    2009-01-01

    Interest in nuclear power has been revived as a result of volatile fossil fuel prices, concerns about the security of energy supplies, and global climate change. This paper describes the current status and future plans for expansion of nuclear power, the advances in nuclear reactor technology, and their impacts on the associated risks and performance of nuclear power. Advanced nuclear reactors have been designed to be simpler and safer, and to have lower costs than currently operating reactor...

  10. The awareness of employees in safety culture through the improved nuclear safety culture evaluation method

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Ga; Sung, Chan Ho; Jung, Yeon Sub [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2012-10-15

    After the Chernobyl nuclear accident in 1986, nuclear safety culture terminology was at first introduced emphasizing the importance of employees' attitude and organizational safety. The concept of safety culture was spread by INSAG 4 published in 1991. From that time, IAEA had provided the service of ASCOT for the safety culture assessment. However, many people still are thinking that safety culture is abstract and is not clear. It is why the systematic and reliable assessment methodology was not developed. Assessing safety culture is to identify what is the basic assumption for any organization to accept unconsciously. Therefore, it is very difficult to reach a meaningful conclusion by a superficial investigation alone. KHNP had been doing the safety culture assessment which was based on ASCOT methodology every 2 years. And this result had contributed to improving safety culture. But this result could not represent the level of organization's safety culture due to the limitation of method. So, KHNP has improved the safety culture method by benchmarking the over sea assessment techniques in 2011. The effectiveness of this improved methodology was validated through a pilot assessment. In this paper, the level of employees' safety culture awareness was analyzed by the improved method and reviewed what is necessary for the completeness and objectivity of the nuclear safety culture assessment methodology.

  11. Psychometric model for safety culture assessment in nuclear research facilities

    Energy Technology Data Exchange (ETDEWEB)

    Nascimento, C.S. do, E-mail: claudio.souza@ctmsp.mar.mil.br [Centro Tecnológico da Marinha em São Paulo (CTMSP), Av. Professor Lineu Prestes 2468, 05508-000 São Paulo, SP (Brazil); Andrade, D.A., E-mail: delvonei@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN – SP), Av. Professor Lineu Prestes 2242, 05508-000 São Paulo, SP (Brazil); Mesquita, R.N. de, E-mail: rnavarro@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN – SP), Av. Professor Lineu Prestes 2242, 05508-000 São Paulo, SP (Brazil)

    2017-04-01

    Highlights: • A psychometric model to evaluate ‘safety climate’ at nuclear research facilities. • The model presented evidences of good psychometric qualities. • The model was applied to nuclear research facilities in Brazil. • Some ‘safety culture’ weaknesses were detected in the assessed organization. • A potential tool to develop safety management programs in nuclear facilities. - Abstract: A safe and reliable operation of nuclear power plants depends not only on technical performance, but also on the people and on the organization. Organizational factors have been recognized as the main causal mechanisms of accidents by research organizations through USA, Europe and Japan. Deficiencies related with these factors reveal weaknesses in the organization’s safety culture. A significant number of instruments to assess the safety culture based on psychometric models that evaluate safety climate through questionnaires, and which are based on reliability and validity evidences, have been published in health and ‘safety at work’ areas. However, there are few safety culture assessment instruments with these characteristics (reliability and validity) available on nuclear literature. Therefore, this work proposes an instrument to evaluate, with valid and reliable measures, the safety climate of nuclear research facilities. The instrument was developed based on methodological principles applied to research modeling and its psychometric properties were evaluated by a reliability analysis and validation of content, face and construct. The instrument was applied to an important nuclear research organization in Brazil. This organization comprises 4 research reactors and many nuclear laboratories. The survey results made possible a demographic characterization and the identification of some possible safety culture weaknesses and pointing out potential areas to be improved in the assessed organization. Good evidence of reliability with Cronbach's alpha

  12. International environmental law and the problem of nuclear safety

    Energy Technology Data Exchange (ETDEWEB)

    De La Fayette, L.

    1993-01-01

    Upon a decision of the Board of Governors, the IAEA is now engaged in substantive preparations for an international convention on nuclear safety. Part I of this paper examines member states' attitudes and outlines the process and the proposals culminating in the commencement of the negotiations. Part II then considers the possible elements of an ideal convention on nuclear safety. Section A surveys legal instruments in the fields of industrial safety and environmental protection that might serve as possible models for a solution, while Section B contains a commentary on the proposed structure and substance, with reference to the existing practice of states in relation to safety standards and external safety assessments. (author).

  13. Nuclear Safety research in CIEMAT; Quince anos de investigacion en Seguridad Nuclear en el Ciemat

    Energy Technology Data Exchange (ETDEWEB)

    Lopez Jimenez, J.

    2003-07-01

    A review was done on the main activities performed and achievements managed by the Project of Nuclear Safety Research (Department of Nuclear Fission) of Ciemat in the last fifteen years on the areas of: severe accident, advanced reactors and containment analysis. It was emphasised Ciemat's participation in national and international projects, mainly promoted by The Spanish Nuclear Sector, the CSN the OECD, EPRI and the European Union. The experimental and analytical capabilities on reactor nuclear safety set up in Ciemat along this period of time were also described. (Author) 23 refs.

  14. Regulatory and safety aspects of ageing in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kaufer, B. [OECD/Nuclear Energy Agency, Issy-les-Moulineaux (France). Nuclear Safety Div.

    2002-08-01

    The OECD Nuclear Energy Agency (NEA) is a semi-autonomous body within the OECD established in 1958 with the mandate to promote co-operation among the governments of its participating countries in furthering the development of nuclear power as a safe, environmentally acceptable and economicy energy source. While all of groups have detailed programmes involving important aspects, this paper will focus specifically on the work of Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI). (orig.)

  15. Nuclear safety in light water reactors severe accident phenomenology

    CERN Document Server

    Sehgal, Bal Raj

    2011-01-01

    This vital reference is the only one-stop resource on how to assess, prevent, and manage severe nuclear accidents in the light water reactors (LWRs) that pose the most risk to the public. LWRs are the predominant nuclear reactor in use around the world today, and they will continue to be the most frequently utilized in the near future. Therefore, accurate determination of the safety issues associated with such reactors is central to a consideration of the risks and benefits of nuclear power. This book emphasizes the prevention and management of severe accidents to teach nuclear professionals

  16. Lessons in Nuclear Safety, Panel on Integration of People and Programs

    Energy Technology Data Exchange (ETDEWEB)

    Pinkston, David [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-02-24

    Four slides present a historical perspective on the evolution of nuclear safety, a description of systemic misalignment (available resources do not match expectations, demographic cliff developing, promulgation of increased expectations and new requirements proceeds unabated), and needs facing nuclear safety (financial stability, operational stability, and succession planning). The following conclusions are stated under the heading "Nuclear Safety - 'The System'": the current universe of requirements is too large for the resource pool available; the current universe of requirements has too many different sources of interpretation; there are so many indicators that it’s hard to know what is leading (or important); and the net result can come to defy integrated comprehension at the worker level.

  17. Nuclear Data Activities in Support of the DOE Nuclear Criticality Safety Program

    Science.gov (United States)

    Westfall, R. M.; McKnight, R. D.

    2005-05-01

    The DOE Nuclear Criticality Safety Program (NCSP) provides the technical infrastructure maintenance for those technologies applied in the evaluation and performance of safe fissionable-material operations in the DOE complex. These technologies include an Analytical Methods element for neutron transport as well as the development of sensitivity/uncertainty methods, the performance of Critical Experiments, evaluation and qualification of experiments as Benchmarks, and a comprehensive Nuclear Data program coordinated by the NCSP Nuclear Data Advisory Group (NDAG). The NDAG gathers and evaluates differential and integral nuclear data, identifies deficiencies, and recommends priorities on meeting DOE criticality safety needs to the NCSP Criticality Safety Support Group (CSSG). Then the NDAG identifies the required resources and unique capabilities for meeting these needs, not only for performing measurements but also for data evaluation with nuclear model codes as well as for data processing for criticality safety applications. The NDAG coordinates effort with the leadership of the National Nuclear Data Center, the Cross Section Evaluation Working Group (CSEWG), and the Working Party on International Evaluation Cooperation (WPEC) of the OECD/NEA Nuclear Science Committee. The overall objective is to expedite the issuance of new data and methods to the DOE criticality safety user. This paper describes these activities in detail, with examples based upon special studies being performed in support of criticality safety for a variety of DOE operations.

  18. Proceedings of the Nuclear Criticality Technology Safety Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Rene G. Sanchez

    1998-04-01

    This document contains summaries of most of the papers presented at the 1995 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 16 and 17 at San Diego, Ca. The meeting was broken up into seven sessions, which covered the following topics: (1) Criticality Safety of Project Sapphire; (2) Relevant Experiments For Criticality Safety; (3) Interactions with the Former Soviet Union; (4) Misapplications and Limitations of Monte Carlo Methods Directed Toward Criticality Safety Analyses; (5) Monte Carlo Vulnerabilities of Execution and Interpretation; (6) Monte Carlo Vulnerabilities of Representation; and (7) Benchmark Comparisons.

  19. Research on the improvement of nuclear safety -Thermal hydraulic tests for reactor safety system-

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Moon Kee; Park, Choon Kyung; Yang, Sun Kyoo; Chun, Se Yung; Song, Chul Hwa; Jun, Hyung Kil; Jung, Heung Joon; Won, Soon Yun; Cho, Yung Roh; Min, Kyung Hoh; Jung, Jang Hwan; Jang, Suk Kyoo; Kim, Bok Deuk; Kim, Wooi Kyung; Huh, Jin; Kim, Sook Kwan; Moon, Sang Kee; Lee, Sang Il [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-06-01

    The present research aims at the development of the thermal hydraulic verification test technology for the safety system of the conventional and advanced nuclear power plant and the development of the advanced thermal hydraulic measuring techniques. In this research, test facilities simulating the primary coolant system and safety system are being constructed for the design verification tests of the existing and advanced nuclear power plant. 97 figs, 14 tabs, 65 refs. (Author).

  20. IR-360 nuclear power plant safety functions and component classification

    Energy Technology Data Exchange (ETDEWEB)

    Yousefpour, F., E-mail: fyousefpour@snira.co [Management of Nuclear Power Plant Construction Company (MASNA) (Iran, Islamic Republic of); Shokri, F.; Soltani, H. [Management of Nuclear Power Plant Construction Company (MASNA) (Iran, Islamic Republic of)

    2010-10-15

    The IR-360 nuclear power plant as a 2-loop PWR of 360 MWe power generation capacity is under design in MASNA Company. For design of the IR-360 structures, systems and components (SSCs), the codes and standards and their design requirements must be determined. It is a prerequisite to classify the IR-360 safety functions and safety grade of structures, systems and components correctly for selecting and adopting the suitable design codes and standards. This paper refers to the IAEA nuclear safety codes and standards as well as USNRC standard system to determine the IR-360 safety functions and to formulate the principles of the IR-360 component classification in accordance with the safety philosophy and feature of the IR-360. By implementation of defined classification procedures for the IR-360 SSCs, the appropriate design codes and standards are specified. The requirements of specific codes and standards are used in design process of IR-360 SSCs by design engineers of MASNA Company. In this paper, individual determination of the IR-360 safety functions and definition of the classification procedures and roles are presented. Implementation of this work which is described with example ensures the safety and reliability of the IR-360 nuclear power plant.

  1. Regulatory oversight report 2012 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2012 zur nuklearen Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-04-15

    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

  2. Nuclear safety. Volume 36, Number 2, July--December 1995

    Energy Technology Data Exchange (ETDEWEB)

    None

    1995-12-01

    The primary scope of the journal is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities. The following subjects are covered here: (1) the Chernobyl accident; (2) general safety considerations; (3) accident analysis; (4) design features; (5) environmental effects; (6) operating experiences; (7) US NRC information and analyses; and (8) recent developments. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  3. Legal principles of regulatory administration and nuclear safety regulation

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kyeong Hui; Cheong, Sang Kee [Hannam Univ., Taejon (Korea, Republic of)

    2000-12-15

    This research presents a critical analysis and evaluation of principles of administrative laws in order to provide framework of structural reform on the nuclear safety regulation system. The focus of this analysis and evaluation is centered around the area of origin of regulatory administrative laws; authorities of regulation; procedures of regulatory actions; regulatory enforcement; and administrative relief system. In chapter 2 the concept of regulatory administration is analysed. Chapter 3 identifies the origin of regulatory administration and the principles of administration laws. It also examines legal nature of the nuclear safety standard. In relation to regulatory authorities. Chapter 4 identifies role and responsibility of administration authorities and institutions. It also examines fundamental principles of delegation of power. Then the chapter discusses the nuclear safety regulation authorities and their roles and responsibilities. Chapter 5 classifies and examines regulatory administration actions. Chapter 6 evaluates enforcement measure for effectiveness of regulation. Finally, chapter 7 discusses the administrative relief system for reviewing unreasonable regulatory acts.

  4. Framework for Integrating Safety, Operations, Security, and Safeguards in the Design and Operation of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Darby, John L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Horak, Karl Emanuel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); LaChance, Jeffrey L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Tolk, Keith Michael [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Whitehead, Donnie Wayne [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2007-10-01

    The US is currently on the brink of a nuclear renaissance that will result in near-term construction of new nuclear power plants. In addition, the Department of Energy’s (DOE) ambitious new Global Nuclear Energy Partnership (GNEP) program includes facilities for reprocessing spent nuclear fuel and reactors for transmuting safeguards material. The use of nuclear power and material has inherent safety, security, and safeguards (SSS) concerns that can impact the operation of the facilities. Recent concern over terrorist attacks and nuclear proliferation led to an increased emphasis on security and safeguard issues as well as the more traditional safety emphasis. To meet both domestic and international requirements, nuclear facilities include specific SSS measures that are identified and evaluated through the use of detailed analysis techniques. In the past, these individual assessments have not been integrated, which led to inefficient and costly design and operational requirements. This report provides a framework for a new paradigm where safety, operations, security, and safeguards (SOSS) are integrated into the design and operation of a new facility to decrease cost and increase effectiveness. Although the focus of this framework is on new nuclear facilities, most of the concepts could be applied to any new, high-risk facility.

  5. Nuclear space power safety and facility guidelines study

    Energy Technology Data Exchange (ETDEWEB)

    Mehlman, W.F.

    1995-09-11

    This report addresses safety guidelines for space nuclear reactor power missions and was prepared by The Johns Hopkins University Applied Physics Laboratory (JHU/APL) under a Department of Energy grant, DE-FG01-94NE32180 dated 27 September 1994. This grant was based on a proposal submitted by the JHU/APL in response to an {open_quotes}Invitation for Proposals Designed to Support Federal Agencies and Commercial Interests in Meeting Special Power and Propulsion Needs for Future Space Missions{close_quotes}. The United States has not launched a nuclear reactor since SNAP 10A in April 1965 although many Radioisotope Thermoelectric Generators (RTGs) have been launched. An RTG powered system is planned for launch as part of the Cassini mission to Saturn in 1997. Recently the Ballistic Missile Defense Office (BMDO) sponsored the Nuclear Electric Propulsion Space Test Program (NEPSTP) which was to demonstrate and evaluate the Russian-built TOPAZ II nuclear reactor as a power source in space. As of late 1993 the flight portion of this program was canceled but work to investigate the attributes of the reactor were continued but at a reduced level. While the future of space nuclear power systems is uncertain there are potential space missions which would require space nuclear power systems. The differences between space nuclear power systems and RTG devices are sufficient that safety and facility requirements warrant a review in the context of the unique features of a space nuclear reactor power system.

  6. Review of Overall Safety Manual for space nuclear systems. An evaluation of a nuclear safety analysis methodology for plutonium-fueled space nuclear systems

    Energy Technology Data Exchange (ETDEWEB)

    Coleman, J.; Inhaber, H.

    1984-02-01

    As part of its duties in connection with space missions involving nuclear power sources, the Office of Nuclear Safety (ONS) of the Office of Assistant Secretary for Environmental Protection, Safety, and Emergency Preparedness has been assigned the task of reviewing the Overall Safety Manual (OSM) (memo from B.J. Rock to J.R. Maher, December 1, 1982). The OSM, dated July 1981 and in four volumes, was prepared by NUS Corporation, Rockville, Maryland, for the US Department of Energy. The OSM provides many of the technical models and much of the data which are used by (1) space launch contractors in safety analysis reports and (2) the broader Interagency Nuclear Safety Review Panel (INSRP) safety evaluation reports. If fhs interaction between the OSM, contractors, and INSRP is to work effectively, the OSM must be accurate, comprehensive, understandable, and usable.

  7. Nuclear Safety Research and Facilities Department annual report 1999

    DEFF Research Database (Denmark)

    Majborn, B.; Damkjær, A.; Jensen, Per Hedemann

    2000-01-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department´s research and development activities were organized in two research programmes: "Radiation Protection and Reactor Safety" and"Radioecology and Tracer Studies". The nuclear...... facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are includedtogether with a summary of the staff´s participation in national and international committees....

  8. Nuclear Safety Research and Facilities Department annual report 1997

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Aarkrog, A.; Brodersen, K. [and others

    1998-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1997. The department`s research and development activities were organized in four research programmes: Reactor Safety, Radiation protection, Radioecology, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the educational reactor DR1. Lists of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au) 11 tabs., 39 ills.; 74 refs.

  9. Nuclear Safety Research and Facilities Department annual report 1998

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E

    1999-04-01

    The report present a summary of the work of the Nuclear Safety Research and Facilities Department in 1998. The department`s research and development activities were organized in two research programmes: `Radiation Protection and Reactor Safety` and `Radioecology and Tracer Studies`. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment plant, and the educational reactor DR1. Lsits of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au)

  10. Nuclear Safety Research and Facilities Department. Annual report 1999

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E. [eds.

    2000-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  11. Indicators of Nuclear safety and exploitation in ANAV; Indicadores de Seguridad Nuclear y explotacion en ANAV

    Energy Technology Data Exchange (ETDEWEB)

    Quintana Prieto, M.; Jorda Alcove, M.

    2013-07-01

    The use of indicators by ANAV plants, aims to be a tool to facilitate the assessment of the behaviour of the plants nuclear over a specific time period. The following are and are they explain those related to Nuclear safety and exploitation.

  12. Nuclear criticality safety training: guidelines for DOE contractors

    Energy Technology Data Exchange (ETDEWEB)

    Crowell, M.R.

    1983-09-01

    The DOE Order 5480.1A, Chapter V, Safety of Nuclear Facilities, establishes safety procedures and requirements for DOE nuclear facilities. This guide has been developed as an aid to implementing the Chapter V requirements pertaining to nuclear criticality safety training. The guide outlines relevant conceptual knowledge and demonstrated good practices in job performance. It addresses training program operations requirements in the areas of employee evaluations, employee training records, training program evaluations, and training program records. It also suggests appropriate feedback mechanisms for criticality safety training program improvement. The emphasis is on academic rather than hands-on training. This allows a decoupling of these guidelines from specific facilities. It would be unrealistic to dictate a universal program of training because of the wide variation of operations, levels of experience, and work environments among DOE contractors and facilities. Hence, these guidelines do not address the actual implementation of a nuclear criticality safety training program, but rather they outline the general characteristics that should be included.

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

    Energy Technology Data Exchange (ETDEWEB)

    2008-07-01

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

  14. Spent Nuclear Fuel Project path forward: nuclear safety equivalency to comparable NRC-licensed facilities

    Energy Technology Data Exchange (ETDEWEB)

    Garvin, L.J.

    1995-11-01

    This document includes the Technical requirements which meet the nuclear safety objectives of the NRC regulations for fuel treatment and storage facilities. These include requirements regarding radiation exposure limits, safety analysis, design and construction. This document also includes administrative requirements which meet the objectives of the major elements of the NRC licensing process. These include formally documented design and safety analysis, independent technical review, and oppportunity for public involvement.

  15. The European Union and nuclear safety; Die EU und die nukleare Sicherheit

    Energy Technology Data Exchange (ETDEWEB)

    Raetzke, Christian [CONLAR Consulting on Nuclear Law and Regulation, Leipzig (Germany)

    2014-02-15

    In recent years the EU Commission has developed a range of activities in the area of nuclear safety. Currently, the Commission has submitted a draft Directive revising the Nuclear Safety Directive 2009/71 to the Council. It seems that this draft text will undergo substantial changes in the course of Council deliberations and it is not clear yet whether any revision of the Directive will be adopted at all. The article shortly explains the background and the history of EU legislative activities in nuclear safety - a history which has been somewhat less than straightforward and has not yet reached its final chapter. The Commission's endeavours to introduce meaningful legislation have always met resistance from Member States determined to protect their sovereignty in this area. A decisive handicap for the Commission in this struggle certainly is the fact that it does not have a sufficient degree of in-house expertise in nuclear safety. Unless this is changed by upgrading and empowering the Commission to become a 'super-regulatory authority' - which seems to be very unlikely -, the Commission will have to resign itself to contribute to the further development of nuclear safety by closely cooperating with the Member States and their regulators. In any case, this can be a very effective and meaningful role. (orig.)

  16. Department of Nuclear Safety Research and Nuclear Facilities annual report 1995

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Jacobsen, U.; Oelgaard, P.L. [eds.

    1996-03-01

    The report presents a summary of the work of the Department of Nuclear Safety Research and Nuclear Facilities in 1995. The department`s research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au) 5 tabs., 21 ills.

  17. Training of nuclear criticality safety engineers

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, R.G. [Oak Ridge Y-12 Plant, TN (United States)

    1997-06-01

    The site specific analysis of nuclear criticality training needs is very briefly described. Analysis indicated that the four major components required were analysis, surveillance, business practices or administration, and emergency preparedness. The analysis component was further divided into process analysis, accident analysis, and transportation analysis. Ten subject matter areas for the process analysis component were identified as candidates for class development. Training classes developed from the job content analysis have demonstrated that the specialized information can be successfully delivered to new entrants. 1 fig.

  18. Risk and safety analysis of nuclear systems

    CERN Document Server

    Lee, John C

    2011-01-01

    The book has been developed in conjunction with NERS 462, a course offered every year to seniors and graduate students in the University of Michigan NERS program. The first half of the book covers the principles of risk analysis, the techniques used to develop and update a reliability data base, the reliability of multi-component systems, Markov methods used to analyze the unavailability of systems with repairs, fault trees and event trees used in probabilistic risk assessments (PRAs), and failure modes of systems. All of this material is general enough that it could be used in non-nuclear a

  19. 76 FR 61350 - DOE Response to Defense Nuclear Facilities Safety Board's Request for Clarification on...

    Science.gov (United States)

    2011-10-04

    ... Vorderbrueggen, Nuclear Engineer, Departmental Representative to the Defense Nuclear Facilities Safety Board, Office of Health, Safety and Security, U.S. Department of Energy, 1000 Independence Avenue, SW... Representative to the Defense Nuclear Facilities Safety Board, Office of Health, Safety and Security....

  20. Applications of nuclear safety probabilistic risk assessment to nuclear security for optimized risk mitigation

    Energy Technology Data Exchange (ETDEWEB)

    Donnelly, S.K.; Harvey, S.B. [Amec Foster Wheeler, Toronto, Ontario (Canada)

    2016-06-15

    Critical infrastructure assets such as nuclear power generating stations are potential targets for malevolent acts. Probabilistic methodologies can be applied to evaluate the real-time security risk based upon intelligence and threat levels. By employing this approach, the application of security forces and other protective measures can be optimized. Existing probabilistic safety analysis (PSA) methodologies and tools employed. in the nuclear industry can be adapted to security applications for this purpose. Existing PSA models can also be adapted and enhanced to consider total plant risk, due to nuclear safety risks as well as security risks. By creating a Probabilistic Security Model (PSM), safety and security practitioners can maximize the safety and security of the plant while minimizing the significant costs associated with security upgrades and security forces. (author)

  1. Proceedings of the Nuclear Criticality Technology and Safety Project Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, R.G. [comp.

    1994-01-01

    This report is the proceedings of the annual Nuclear Criticality Technology and Safety Project (NCTSP) Workshop held in Monterey, California, on April 16--28, 1993. The NCTSP was sponsored by the Department of Energy and organized by the Los Alamos Critical Experiments Facility. The report is divided into six sections reflecting the sessions outlined on the workshop agenda.

  2. Nuclear Safety Research Department annual progress report 1994

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Hoejerup, C.F. [eds.

    1995-03-01

    The report describes the work of the Nuclear Safety Research Department during 1994. The activities cover health physics, reactor physics, operation of the small reactor DR1, and radioactive waste management. Lists of staff and publications are included together with a summary of the staff`s participation in international committees. (au) (1 tab., 12 ills.).

  3. Water monitoring as a safety feature for nuclear desalination

    Energy Technology Data Exchange (ETDEWEB)

    Masriera, N.A. [Nuclear Engineering Department, INVAP, Bariloche, Rio Negro (Argentina)]. E-mail: masriera@invap.com.ar; Doval, A.S.; Di Tada, M.L. [Nuclear Engineering Department, INVAP, Bariloche, Rio Negro (Argentina)

    2006-07-01

    It is widely accepted that the general safety approach for nuclear facilities is valid for a Nuclear Desalination Plant (NDP), thus IAEA standards and guides are applicable. The coupling of a NDP should be designed with the safety objective of ensuring that it results in no adverse effect on the Nuclear Power Plant (NPP) safety. The first objective (provisions of barriers) is complied with by the known NDP design, so the relevant issue becomes the design features preventing the transfer of radioactive material to the product water, even in the event of system failures. This presentation drafts a coupling-system safety assessment, from fundamentals and general requirements down to specific design requirements. The state of the art of monitoring systems imposes constraints on the coupling design, in terms of hold-up capability and piping interconnection. This conceptual design shows the system's complexity implied in having monitoring of product water as a safety feature, and conclusions are extremely relevant when drafting general user requirements for a NDP project. (author)

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

    Science.gov (United States)

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

    2014-11-01

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

  5. Proceedings of the nuclear criticality technology safety project

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, R.G. [comp.

    1997-06-01

    This document contains summaries of the most of the papers presented at the 1994 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 10 and 11 at Williamsburg, Va. The meeting was broken up into seven sessions, which covered the following topics: (1) Validation and Application of Calculations; (2) Relevant Experiments for Criticality Safety; (3) Experimental Facilities and Capabilities; (4) Rad-Waste and Weapons Disassembly; (5) Criticality Safety Software and Development; (6) Criticality Safety Studies at Universities; and (7) Training. The minutes and list of participants of the Critical Experiment Needs Identification Workgroup meeting, which was held on May 9 at the same venue, has been included as an appendix. A second appendix contains the names and addresses of all NCTSP meeting participants. Separate abstracts have been indexed to the database for contributions to this proceedings.

  6. HFE safety reviews of advanced nuclear power plant control rooms

    Science.gov (United States)

    Ohara, John

    1994-01-01

    Advanced control rooms (ACR's) will utilize human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator's overall role and means of interacting with the system. The Nuclear Regulatory Commission (NRC) reviews the human factors engineering (HFE) aspects of HSI's to ensure that they are designed to good HFE principles and support performance and reliability in order to protect public health and safety. However, the only available NRC guidance was developed more than ten years ago, and does not adequately address the human performance issues and technology changes associated with ACR's. Accordingly, a new approach to ACR safety reviews was developed based upon the concept of 'convergent validity'. This approach to ACR safety reviews is described.

  7. Software reliability and safety in nuclear reactor protection systems

    Energy Technology Data Exchange (ETDEWEB)

    Lawrence, J.D. [Lawrence Livermore National Lab., CA (United States)

    1993-11-01

    Planning the development, use and regulation of computer systems in nuclear reactor protection systems in such a way as to enhance reliability and safety is a complex issue. This report is one of a series of reports from the Computer Safety and Reliability Group, Lawrence Livermore that investigates different aspects of computer software in reactor National Laboratory, that investigates different aspects of computer software in reactor protection systems. There are two central themes in the report, First, software considerations cannot be fully understood in isolation from computer hardware and application considerations. Second, the process of engineering reliability and safety into a computer system requires activities to be carried out throughout the software life cycle. The report discusses the many activities that can be carried out during the software life cycle to improve the safety and reliability of the resulting product. The viewpoint is primarily that of the assessor, or auditor.

  8. 76 FR 42686 - DOE Response to Recommendation 2011-1 of the Defense Nuclear Facilities Safety Board, Safety...

    Science.gov (United States)

    2011-07-19

    ... if we remain committed to continuous improvement and teamwork. DOE takes all safety concerns--whether... emphasize the importance of a robust nuclear safety culture. Even while some initiatives are already... importance of maintaining a strong nuclear safety culture at each of our sites and to solicit their...

  9. Nuclear power plant safety related pump issues

    Energy Technology Data Exchange (ETDEWEB)

    Colaccino, J.

    1996-12-01

    This paper summarizes of a number of pump issues raised since the Third NRC/ASME Symposium on Valve and Pump Testing in 1994. General issues discussed include revision of NRC Inspection Procedure 73756, issuance of NRC Information Notice 95-08 on ultrasonic flow meter uncertainties, relief requests for tests that are determined by the licensee to be impractical, and items in the ASME OM-1995 Code, Subsection ISTB, for pumps. The paper also discusses current pump vibration issues encountered in relief requests and plant inspections - which include smooth running pumps, absolute vibration limits, and vertical centrifugal pump vibration measurement requirements. Two pump scope issues involving boiling water reactor waterlog and reactor core isolation cooling pumps are also discussed. Where appropriate, NRC guidance is discussed.

  10. Analysis of safety information for nuclear power plants and development of source term estimation program

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Tae Woon; Choi, Seong Soo; Park, Jin Hee [Atomic Creative Technology, Taejon (Korea, Republic of)

    1999-12-15

    Current CARE(Computerized Advisory System for Radiological Emergency) in KINS(Korea Institute of Nuclear Safety) has no STES(Source Term Estimation System) which links between SIDS(Safety Information Display System) and FADAS(Following Accident Dose Assessment System). So in this study, STES is under development. STES system is the system that estimates the source term based on the safety information provided by SIDS. Estimated source term is given to FADAS as an input for estimation of environmental effect of radiation. Through this first year project STES for the Kori 3,4 and Younggwang 1,2 has been developed. Since there is no CARE for Wolsong(PHWR) plants yet, CARE for Wolsong is under construction. The safety parameters are selected and the safety information display screens and the alarm logic for plant status change are developed for Wolsong Unit 2 based on the design documents for CANDU plants.

  11. Design data and safety features of commerical nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Heddleson, F.A.

    1976-06-01

    Design data, safety features, and site characteristics are summarized for 34 nuclear power units in 17 power stations in the United States. Six pages of data are presented for each plant, consisting of thermal-hydraulic and nuclear factors, containment features, emergency-core-cooling systems, site features, circulating water system data, and miscellaneous factors. An aerial perspective is also presented for each plant. This volume covers Light Water Reactors (LWRs) with dockets 50-508 through 50-549, four HTGRs--50-171, 50-267, 50-450/451, 50-463/464, the Atlantic Floating Station 50-477/478, and the Clinch River Breeder 50-537.

  12. A proactive method for safety management in nuclear facilities; Um metodo proativo para gerenciamento da seguranca em instalacoes nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Grecco, Claudio Henrique dos Santos; Carvalho, Paulo Victor Rodrigues de; Santos, Isaac Antonio Luquetti dos, E-mail: grecco@ien.gov.br, E-mail: paulov@ien.gov.br, E-mail: luquetti@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN/RJ), Rio de Janeiro, RJ (Brazil). Div. de Instrumentacao e Confiabilidade Humana

    2014-07-01

    Due to the modern approach to address the safety of nuclear facilities which highlights that these organizations must be able to assess and proactively manage their activities becomes increasingly important the need for instruments to evaluate working conditions. In this context, this work presents a proactive method of managing organizational safety, which has three innovative features: 1) the use of predictive indicators that provide current information on the performance of activities, allowing preventive actions and not just reactive in safety management, different from safety indicators traditionally used (reactive indicators) that are obtained after the occurrence of undesired events; 2) the adoption of resilience engineering approach in the development of indicators - indicators are based on six principles of resilience engineering: top management commitment, learning, flexibility, awareness, culture of justice and preparation for the problems; 3) the adoption of the concepts and properties of fuzzy set theory to deal with subjectivity and consistency of human trials in the evaluation of the indicators. The fuzzy theory is used primarily to map qualitative models of decision-making, and inaccurate representation methods. The results of this study aim an improvement in performance and safety in organizations. The method was applied in a radiopharmaceutical shipping sector of a nuclear facility. The results showed that the method is a good monitoring tool objectively and proactively of the working conditions of an organizational domain.

  13. Current Comparison of Advanced Nuclear Fuel Cycles

    Energy Technology Data Exchange (ETDEWEB)

    Steven Piet; Trond Bjornard; Brent Dixon; Robert Hill; Gretchen Matthern; David Shropshire

    2007-04-01

    This paper compares potential nuclear fuel cycle strategies – once-through, recycling in thermal reactors, sustained recycle with a mix of thermal and fast reactors, and sustained recycle with fast reactors. Initiation of recycle starts the draw-down of weapons-usable material and starts accruing improvements for geologic repositories and energy sustainability. It reduces the motivation to search for potential second geologic repository sites. Recycle in thermal-spectru

  14. 78 FR 25488 - Qualification Tests for Safety-Related Actuators in Nuclear Power Plants

    Science.gov (United States)

    2013-05-01

    ... COMMISSION Qualification Tests for Safety-Related Actuators in Nuclear Power Plants AGENCY: Nuclear..., ``Qualification Tests for Safety-Related Actuators in Nuclear Power Plants.'' DG-1235 is proposed Revision 1 of RG... Stations in order to demonstrate their ability to perform their intended safety functions under...

  15. Probabilistic safety assessment in the chemical and nuclear industries

    CERN Document Server

    Fullwood, Ralph R

    2000-01-01

    Probabilistic Safety Analysis (PSA) determines the probability and consequences of accidents, hence, the risk. This subject concerns policy makers, regulators, designers, educators and engineers working to achieve maximum safety with operational efficiency. Risk is analyzed using methods for achieving reliability in the space program. The first major application was to the nuclear power industry, followed by applications to the chemical industry. It has also been applied to space, aviation, defense, ground, and water transportation. This book is unique in its treatment of chemical and nuclear risk. Problems are included at the end of many chapters, and answers are in the back of the book. Computer files are provided (via the internet), containing reliability data, a calculator that determines failure rate and uncertainty based on field experience, pipe break calculator, event tree calculator, FTAP and associated programs for fault tree analysis, and a units conversion code. It contains 540 references and many...

  16. Nuclear emergency preparedness. Final report of the Nordic Nuclear Safety Research Project BOK-1

    DEFF Research Database (Denmark)

    Lauritzen, B.

    2002-01-01

    Final report of the Nordic Nuclear Safety Research project BOK-1. The BOK-1 project, “Nuclear Emergency Preparedness”, was carried out in 1998-2001 with participants from the Nordic and Baltic Sea regions. The project consists of six sub-projects:Laboratory measurements and quality assurance (BOK-1.......1); Mobile measurements and measurement strategies (BOK-1.2); Field measurements and data assimilation (BOK-1.3); Countermeasures in agriculture and forestry (BOK-1.4); Emergency monitoring in theNordic and Baltic Sea countries (BOK-1.5); and Nuclear exercises (BOK-1.6). For each sub-project, the project...

  17. 75 FR 50009 - Babcock & Wilcox Nuclear Operations Group, Inc.; Establishment of Atomic Safety and Licensing Board

    Science.gov (United States)

    2010-08-16

    ... COMMISSION Babcock & Wilcox Nuclear Operations Group, Inc.; Establishment of Atomic Safety and Licensing... & Wilcox Nuclear Operations Group, Inc. (Lynchburg, VA Facility). This proceeding concerns an Order Imposing Civil Monetary Penalty served upon the Licensee, Babcock & Wilcox Nuclear Operations Group,...

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

    Science.gov (United States)

    What You Should Know About Pediatric Nuclear Medicine and Radiation Safety www.imagegently.org What is nuclear medicine? Nuclear medicine uses radioactive isotopes to create pictures of the human body. ...

  19. The Designing Bus for Nuclear Safety Class Controller

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dongil; Lee, Myeongkyun; Yun, Donghwa [PONUTech Co,. Ltd., Research Institute, Ulsan (Korea, Republic of); Ryoo, Kwangki [Hanbat National Univ., Daejeon (Korea, Republic of)

    2013-10-15

    EtherCAT (Ethernet for Control Automation Technology) is based on the IEEE 802.3 standard as one of the communication which is the I/O (Input/Output), sensors and communication function of PLC (Programmable Logic Controller) in industry and factory environment use is increasing. The Nuclear Safety Class Controller implemented by the EtherCAT applied bus can be shown the improving performance of data transmission in the controller.

  20. Double-clad nuclear-fuel safety rod

    Science.gov (United States)

    McCarthy, W.H.; Atcheson, D.B.

    1981-12-30

    A device for shutting down a nuclear reactor during an undercooling or overpower event, whether or not the reactor's scram system operates properly. This is accomplished by double-clad fuel safety rods positioned at various locations throughout the reactor core, wherein melting of a secondary internal cladding of the rod allows the fuel column therein to shift from the reactor core to place the reactor in a subcritical condition.

  1. A comparison of commercial/industry and nuclear weapons safety concepts

    Energy Technology Data Exchange (ETDEWEB)

    Bennett, R.R.; Summers, D.A.

    1996-07-01

    In this paper the authors identify factors which influence the safety philosophy used in the US commercial/industrial sector and compare them against those factors which influence nuclear weapons safety. Commercial/industrial safety is guided by private and public safety standards. Generally, private safety standards tend to emphasize product reliability issues while public (i.e., government) safety standards tend to emphasize human factors issues. Safety in the nuclear weapons arena is driven by federal requirements and memoranda of understanding (MOUs) between the Departments of Defense and Energy. Safety is achieved through passive design features integrated into the nuclear weapon. Though the common strand between commercial/industrial and nuclear weapons safety is the minimization of risk posed to the general population (i.e., public safety), the authors found that each sector tends to employ a different safety approach to view and resolve high-consequence safety issues.

  2. A proposal of safety indicators aggregation to assess the safety management effectiveness of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Jose Antonio B.; Saldanha, Pedro L.C. [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Coordenacao-Geral de Reatores e Ciclo Combustivel], e-mail: jantonio@cnen.gov.br, e-mail: saldanha@cnen.gov.br; Melo, Paulo F.F. Frutuoso e [Coordenacao dos Programas de Pos-graduacao de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear], e-mail: frutuoso@con.ufrj.br

    2009-07-01

    Safety management has changed with the evolution of management methods, named Quality Systems, moving from Quality Control, where the focus was the product, passing through Quality Assurance, which takes care of the whole manufacturing process and reaching the Total Quality Management, where policies and goals are established. Nowadays, there is a trend towards Management Systems, which integrate all different aspects related to the management of an organization (safety, environment, security, quality, costs and, etc), but it is necessary to have features to establish and assure that safety overrides the remaining aspects. The most usual way to reach this goal is to establish a policy where safety is a priority, but its implementation and the assessment of its effectiveness are no so simple. Nuclear power plants usually have over a hundred safety indicators in many processes dedicated to prevent and detect problems, although a lot of them do not evaluate these indicators in an integrated manner or point out degradation trends of organizational aspects, which can affect the plant safety. This work develops an aggregation of proactive and reactive safety indicators in order to evaluate the effectiveness of nuclear power plant safety management and to detect, at early stages, signs of process degradation or activities used to establish, maintain and assure safety conditions. The aggregation integrates indicators of the usual processes and is based on the manner the management activities have been developed in the last decades, that is: Planning, Doing, Checking and Acting - known as PDCA cycle - plus a fifth element related to the capability of those who perform safety activities. The proposed aggregation is in accordance to Brazilian standards and international recommendations and constitutes a friendly link between the top management level and the daily aspects of the organization. (author)

  3. Nuclear Safety and the Role of Quality Assurance

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Hyuk-il; Park, Chan-Gook; Nam, Ji-Hee; Kim, Kwan-Hyun; Lee, Young-Gun; Lim, Nam-Jin [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2006-07-01

    At the early stage of industrialization, quality of a product is determined and achieved by the skill and know-how of a craftsman who made his product. With the development of industry, however, products were diversified and became increasingly complicated. And, the necessity of quality verification by an independent expert, i.e. inspector, became imperative as a means of quality control and quality assurance. Quality should not be a hostage of a consequent tremendous disaster by an accident or malfunction of a product, but should be achieved by pre-planned and systematic control and management actions to assure safe operations. Quality assurance in the nuclear industry is most important because the failure of a safe operation of nuclear power plants or nuclear facilities would cause tremendous disaster to public safety.

  4. The Nuclear and Safety Council and the Nuclear Energy Agency; El Consejo de Seguridad Nuclear y la Agencia de Energia Nuclear. Una estrecha colaboracion

    Energy Technology Data Exchange (ETDEWEB)

    Martinez Ten, C.

    2008-07-01

    On the occasion of the fiftieth anniversary of creation of the Nuclear Energy Agency (NEA), specialised agency within the Organisation for Economic Cooperation and Development (OECD), the President of the Spanish Nuclear Safety Council (CSN), summarizes the activities of the NEA throughout its life up to now. Since it started up, the CSN has worked closely with this international organization, as a reflection of the strong commitment, shared by both institutions, each one in its field, to reach the highest levels in the regulation which contributes decisively to the nuclear safety of the Spanish nuclear power plants. (Author)

  5. Work practices, fatigue, and nuclear power plant safety performance.

    Science.gov (United States)

    Baker, K; Olson, J; Morisseau, D

    1994-06-01

    This paper focuses on work practices that may contribute to fatigue-induced performance decrements in the commercial nuclear power industry. Specifically, the amount of overtime worked by operations, technical, and maintenance personnel and the 12-h operator shift schedule are studied. Although overtime for all three job categories was fairly high at a number of plants, the analyses detected a clear statistical relationship only between operations overtime and plant safety performance. The results for the 12-h operator shift schedule were ambiguous. Although the 12-h operator shift schedule was correlated with operator error, it was not significantly related to the other five safety indicators. This research suggests that at least one of the existing work practices--the amount of operator overtime worked at some plants--represents a safety concern in this industry; however, further research is required before any definitive conclusions can be drawn.

  6. Just in Time DSA the Hanford Nuclear Safety Basis Strategy

    Energy Technology Data Exchange (ETDEWEB)

    JACKSON, M.W.

    2002-06-01

    The U.S. Department of Energy, Richland Operations Office (RL) is responsible for 30 hazard category 2 and 3 nuclear facilities that are operated by its prime contractors, Fluor Hanford, Incorporated (FHI), Bechtel Hanford, Incorporated (BHI) and Pacific Northwest National Laboratory (PNNL). The publication of Title 10, Code of Federal Regulations, Part 830, Subpart B, Safely Basis Requirements (the Rule) in January 2001 requires that the Documented Safety Analyses (DSA) for these facilities be reviewed against the requirements of the Rule. Those DSAs that do not meet the requirements must either be upgraded to satisfy the Rule, or an exemption must be obtained. RL and its prime contractors have developed a Nuclear Safety Strategy that provides a comprehensive approach for supporting RL's efforts to meet its long-term objectives for hazard category 2 and 3 facilities while also meeting the requirements of the Rule. This approach will result in a reduction of the total number of safety basis documents that must be developed and maintained to support the remaining mission and closure of the Hanford Site and ensure that the documentation that must be developed will support: Compliance with the Rule; A ''Just-In-Time'' approach to development of Rule-compliant safety bases supported by temporary exemptions; and Consolidation of safety basis documents that support multiple facilities with a common mission (e.g. decontamination, decommissioning and demolition [DD&D], waste management, surveillance and maintenance). This strategy provides a clear path to transition the safety bases for the various Hanford facilities from support of operation and stabilization missions through DD&D to accelerate closure. This ''Just-In-Time'' Strategy can also be tailored for other DOE Sites, creating the potential for large cost savings and schedule reductions throughout the DOE complex.

  7. Current status of respiratory nuclear medicine

    Energy Technology Data Exchange (ETDEWEB)

    Suga, Kazuyoshi [Yamaguchi Univ., Ube (Japan). School of Medicine

    2002-01-01

    Multimodality image fusion is now becoming popular in respiratory nuclear medical field, since scintigraphic diagnosis, based on functional image interpretation, becomes more accurate and meaningful when supported by corresponding anatomical data. Although SPECT/PET scanner-mounted X-ray tomographic systems are now being introduced for an accurate image fusion in the chest, the use of a fully automatic multi-modality image fusion algorithm may be an alternative method. Our initial attempt of this algorithm for fusion imaging of Tc-99m MAA perfusion or thallium-201 SPECT and helical CT scan has contributed to accurate interpretation of the results without user interaction, and has facilitated the understanding of the functional basis of lung parenchymal CT attenuation changes. Three-dimensional displays with functional mapping are also now being increasingly introduced to various respiratory nuclear studies. A fractal analysis has shown successful results in the analysis of technegas and {sup 99m}Tc-MAA perfusion images, which will be increasingly applied for more objective assessment of the results. The feasibility of {sup 18}F-FDG PET scan in accurate staging of lung cancer and the good cost performance of this method in lung cancer strategy are repeatedly stressed by the recent studies. The feasibility of {sup 99m}Tc-MAA perfusion scan in the evaluation of right-to-left shunt in patients with hepatopulmonary syndrome, and the potential of {sup 123}I-MIBG scan in the evaluation of the function status of pulmonary neuroadrenergic system are new aspects for these well established tracers. There is the first attempt of intraoperative {sup 99m}Tc-colloid sentinel lymph node mapping in patients with resectable non-small cell lung cancer. This may improve the precision of pathologic staging and limit the need for mediastinal node dissection in selected patients. Radiolabeled aerosol lung scintigraphy is being increasingly applied to evaluate lung deposition of various

  8. Objective 1: Extend Life, Improve Performance, and Maintain Safety of the Current Fleet Implementation Plan

    Energy Technology Data Exchange (ETDEWEB)

    Robert Youngblood

    2011-02-01

    Nuclear power has reliably and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. By the year 2030, domestic demand for electrical energy is expected to grow to levels of 16 to 36% higher than 2007 levels. At the same time, most currently operating nuclear power plants will begin reaching the end of their 60 year operating licenses. Figure E 1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy’s Research and Development (R&D) Roadmap has organized its activities in accordance with four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration’s energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document describes how Objective 1 and the LWRS Program will be implemented. The existing U.S. nuclear fleet has a remarkable safety and performance record and today accounts for 70% of the low greenhouse

  9. Objective 1: Extend Life, Improve Performance, and Maintain Safety of the Current Fleet Implementation Plan

    Energy Technology Data Exchange (ETDEWEB)

    Robert Youngblood

    2011-01-01

    Nuclear power has reliably and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. By the year 2030, domestic demand for electrical energy is expected to grow to levels of 16 to 36% higher than 2007 levels. At the same time, most currently operating nuclear power plants will begin reaching the end of their 60 year operating licenses. Figure E 1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy’s Research and Development (R&D) Roadmap has organized its activities in accordance with four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration’s energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document describes how Objective 1 and the LWRS Program will be implemented. The existing U.S. nuclear fleet has a remarkable safety and performance record and today accounts for 70% of the low greenhouse

  10. Current Development of Nuclear Thermal Propulsion technologies at the Center for Space Nuclear Research

    Energy Technology Data Exchange (ETDEWEB)

    Robert C. O' Brien; Steven K. Cook; Nathan D. Jerred; Steven D. Howe; Ronald Samborsky; Daniel Brasuell

    2012-09-01

    Nuclear power and propulsion has been considered for space applications since the 1950s. Between 1955 and 1972 the US built and tested over twenty nuclear reactors / rocket engines in the Rover/NERVA programs1. The Aerojet Corporation was the prime contractor for the NERVA program. Modern changes in environmental laws present challenges for the redevelopment of the nuclear rocket. Recent advances in fuel fabrication and testing options indicate that a nuclear rocket with a fuel composition that is significantly different from those of the NERVA project can be engineered; this may be needed to ensure public support and compliance with safety requirements. The Center for Space Nuclear Research (CSNR) is pursuing a number of technologies, modeling and testing processes to further the development of safe, practical and affordable nuclear thermal propulsion systems.

  11. On Safety Management. A Frame of Reference for Studies of Safety Management with Examples From Non-Nuclear Contexts of Relevance for Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    Svensson, Ola; Salo, Ilkka; Allwin, Pernilla (Risk Analysis, Social and Decision Research Unit, Dept. of Psychology, Stockholm Univ., Stockholm (Sweden))

    2004-11-15

    A good knowledge about safety management from risk technologies outside the area of nuclear power may contribute to both broaden the perspectives on safety management in general, and point at new opportunities for improving safety measures within the nuclear industry. First, a theoretical framework for the study of safety management in general is presented, followed by three case studies on safety management from different non-nuclear areas with potential relevance for nuclear safety. The chapters are written as separate reports and can be read independently of each other. The nuclear industry has a long experience about the management of risky activities, involving all the stages from planing to implementation, both on a more generalized level and in the specific branches of activities (management, administration, operation, maintenance, etc.). Here, safety management is a key concept related to these areas of activities. Outside the field of nuclear power there exist a number of different non-nuclear risk technologies, each one with their own specific needs and experiences about safety management. The differences between the areas consist partly of the different experiences caused by the different technologies. Besides using own experiences in safety practices within the own areas of activities, it may be profitable to take advantage in knowledge and experiences from one area and put it in practice in another area. In order to facilitate knowledge transfer from one technological area to another it may be possible to adapt a common theoretical model, for descriptions and explanations, to the different technologies. Such a model should admit that common denominators for safety management across the areas might be identified and described with common concepts. Systems theory gives the opportunity to not only create models that are descriptive for events within the limits of a given technology, but also to generate knowledge that can be transferred to other

  12. On Safety Management. A Frame of Reference for Studies of Safety Management with Examples From Non-Nuclear Contexts of Relevance for Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    Svensson, Ola; Salo, Ilkka; Allwin, Pernilla (Risk Analysis, Social and Decision Research Unit, Dept. of Psychology, Stockholm Univ., Stockholm (Sweden))

    2004-11-15

    A good knowledge about safety management from risk technologies outside the area of nuclear power may contribute to both broaden the perspectives on safety management in general, and point at new opportunities for improving safety measures within the nuclear industry. First, a theoretical framework for the study of safety management in general is presented, followed by three case studies on safety management from different non-nuclear areas with potential relevance for nuclear safety. The chapters are written as separate reports and can be read independently of each other. The nuclear industry has a long experience about the management of risky activities, involving all the stages from planing to implementation, both on a more generalized level and in the specific branches of activities (management, administration, operation, maintenance, etc.). Here, safety management is a key concept related to these areas of activities. Outside the field of nuclear power there exist a number of different non-nuclear risk technologies, each one with their own specific needs and experiences about safety management. The differences between the areas consist partly of the different experiences caused by the different technologies. Besides using own experiences in safety practices within the own areas of activities, it may be profitable to take advantage in knowledge and experiences from one area and put it in practice in another area. In order to facilitate knowledge transfer from one technological area to another it may be possible to adapt a common theoretical model, for descriptions and explanations, to the different technologies. Such a model should admit that common denominators for safety management across the areas might be identified and described with common concepts. Systems theory gives the opportunity to not only create models that are descriptive for events within the limits of a given technology, but also to generate knowledge that can be transferred to other

  13. An integrated design methodology for the safety and security of nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Joung, S. Y.; Chang, S. H. [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2012-03-15

    After Fukushima nuclear power plant accident, safety of nuclear power plant was issued. In Fukushima accident, one of main reason is location of emergency diesel power generators stop which locate under the sea water level when tsunami occurred. In view of security, emergency diesel generator location under reactor building design is good because for example to escape air strike but is not good for safety for example Fukushima accident. Sometimes safety and security design looks conflicting but nuclear safety and nuclear security share the goal of protecting but nuclear safety and nuclear power plants operate at acceptable risk levels. The purpose of this paper is to introduce safety and security integrated design for nuclear power plant in special emergency diesel generator and control room with simple probabilistic safety assessment analysis.

  14. Nuclear safety considerations in the conceptual design of a fast reactor for space electric power and propulsion

    Science.gov (United States)

    Hsieh, T.-M.; Koenig, D. R.

    1977-01-01

    Some nuclear safety aspects of a 3.2 mWt heat pipe cooled fast reactor with out-of-core thermionic converters are discussed. Safety related characteristics of the design including a thin layer of B4C surrounding the core, the use of heat pipes and BeO reflector assembly, the elimination of fuel element bowing, etc., are highlighted. Potential supercriticality hazards and countermeasures are considered. Impacts of some safety guidelines of space transportation system are also briefly discussed, since the currently developing space shuttle would be used as the primary launch vehicle for the nuclear electric propulsion spacecraft.

  15. A survey on reliability and safety analysis techniques of robot systems in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Eom, H.S.; Kim, J.H.; Lee, J.C.; Choi, Y.R.; Moon, S.S

    2000-12-01

    The reliability and safety analysis techniques was surveyed for the purpose of overall quality improvement of reactor inspection system which is under development in our current project. The contents of this report are : 1. Reliability and safety analysis techniques suvey - Reviewed reliability and safety analysis techniques are generally accepted techniques in many industries including nuclear industry. And we selected a few techniques which are suitable for our robot system. They are falut tree analysis, failure mode and effect analysis, reliability block diagram, markov model, combinational method, and simulation method. 2. Survey on the characteristics of robot systems which are distinguished from other systems and which are important to the analysis. 3. Survey on the nuclear environmental factors which affect the reliability and safety analysis of robot system 4. Collection of the case studies of robot reliability and safety analysis which are performed in foreign countries. The analysis results of this survey will be applied to the improvement of reliability and safety of our robot system and also will be used for the formal qualification and certification of our reactor inspection system.

  16. Nuclear Safety. Technical progress journal, April--June 1996: Volume 37, No. 2

    Energy Technology Data Exchange (ETDEWEB)

    Muhlheim, M D [ed.

    1996-01-01

    This journal covers significant issues in the field of nuclear safety. Its primary scope is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities.

  17. Nuclear Safety. Technical Progress Journal, January--March 1993: Volume 34, No. 1

    Energy Technology Data Exchange (ETDEWEB)

    None

    1993-01-01

    This review journal covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  18. Nuclear Safety. Technical Progress Journal, October--December 1992: Volume 33, No. 4

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-01-01

    This review journal covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  19. Nuclear Safety. Technical progress journal, April--June 1992: Volume 33, No.2

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1992-01-01

    This review journal covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  20. Nuclear Safety. Technical Progress Journal, January--March 1992: Volume 33, No. 1

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-01-01

    This review journal covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  1. Nuclear Safety. Technical progress journal, January--March 1994: Volume 35, No. 1

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1994-01-01

    This is a journal that covers significant issues in the field of nuclear safety. Its primary scope is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities.

  2. An interagency space nuclear propulsion safety policy for SEI - Issues and discussion

    Science.gov (United States)

    Marshall, A. C.; Sawyer, J. C., Jr.

    1991-01-01

    An interagency Nuclear Safety Policy Working Group (NSPWG) was chartered to recommend nuclear safety policy, requirements, and guidelines for the Space Exploration Initiative nuclear propulsion program to facilitate the implementation of mission planning and conceptual design studies. The NSPWG developed a top level policy to provide the guiding principles for the development and implementation of the nuclear propulsion safety program and the development of Safety Functional Requirements. In addition, the NSPWG reviewed safety issues for nuclear propulsion and recommended top level safety requirements and guidelines to address these issues. Safety topics include reactor start-up, inadvertent criticality, radiological release and exposure, disposal, entry, safeguards, risk/reliability, operational safety, ground testing, and other considerations. In this paper the emphasis is placed on the safety policy and the issues and considerations that are addressed by the NSPWG recommendations.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-05-15

    In 2005, no severe events occurred which challenged the safety at the Swedish nuclear power plants. However, some events have been given a special focus. The 'Gudrun' storm, which occurred in January 2005, affected the operation of the reactors at Ringhals and Barsebaeck 2. At Ringhals, the switchyards were affected by salt deposits and, at Barsebaeck, the 400kV grid was subjected to interruptions. The long-term trend is that the total number of fuel defects in Swedish reactors is decreasing. The damage that occurs nowadays has mainly been caused by small objects entering the fuel via the coolant and fretting holes in the cladding. To reduce the number of defects of this type, fuel with filters is successively being introduced to prevent debris from entering the fuel assemblies and cyclone filters in the facility which cleans the coolant. Since the mid-nineties, the pressurised water reactors, Ringhals 2, 3 and 4, have had problems with fuel rod bowing in excess of the safety analysis calculations. Ringhals AB (RAB) has adopted measures to rectify the bowing. Follow-up work shows that the fuel rod bowing is decreasing. The followup in 2005 of damaged tubes in the Ringhals 4 steam generators indicates a continued slow damage propagation. Tubes with defects of such a limited extent that there are adequate margins to rupture and loosening have been kept in operation. Damaged tubes with insufficient margins have plugged. During the year, previously observed minor leakage from the reactor containment in Ringhals 2 was investigated in greater detail and repaired. The investigations showed extensive corrosion attack caused by deficiencies in connection with containment construction. The ageing of electrical cables and other equipment in the I-C systems has been examined by SKI. Regulatory supervision has so far shown that these issues are largely handled in a satisfactory manner by the licensees but that certain supplementary investigations and other measures

  4. Foundational development of an advanced nuclear reactor integrated safety code.

    Energy Technology Data Exchange (ETDEWEB)

    Clarno, Kevin (Oak Ridge National Laboratory, Oak Ridge, TN); Lorber, Alfred Abraham; Pryor, Richard J.; Spotz, William F.; Schmidt, Rodney Cannon; Belcourt, Kenneth (Ktech Corporation, Albuquerque, NM); Hooper, Russell Warren; Humphries, Larry LaRon

    2010-02-01

    This report describes the activities and results of a Sandia LDRD project whose objective was to develop and demonstrate foundational aspects of a next-generation nuclear reactor safety code that leverages advanced computational technology. The project scope was directed towards the systems-level modeling and simulation of an advanced, sodium cooled fast reactor, but the approach developed has a more general applicability. The major accomplishments of the LDRD are centered around the following two activities. (1) The development and testing of LIME, a Lightweight Integrating Multi-physics Environment for coupling codes that is designed to enable both 'legacy' and 'new' physics codes to be combined and strongly coupled using advanced nonlinear solution methods. (2) The development and initial demonstration of BRISC, a prototype next-generation nuclear reactor integrated safety code. BRISC leverages LIME to tightly couple the physics models in several different codes (written in a variety of languages) into one integrated package for simulating accident scenarios in a liquid sodium cooled 'burner' nuclear reactor. Other activities and accomplishments of the LDRD include (a) further development, application and demonstration of the 'non-linear elimination' strategy to enable physics codes that do not provide residuals to be incorporated into LIME, (b) significant extensions of the RIO CFD code capabilities, (c) complex 3D solid modeling and meshing of major fast reactor components and regions, and (d) an approach for multi-physics coupling across non-conformal mesh interfaces.

  5. The current perspectives of nuclear energy and non-proliferation

    Energy Technology Data Exchange (ETDEWEB)

    Gilinsky, Victor

    2012-07-01

    The main reason given nowadays for supporting nuclear plant construction around the world is that the plants do not produce CO{sub 2}. The negative aspects are costs so high as to require subsidies, the possible connection with proliferation, and since the Fukushima accident, a renewed concern about nuclear safety. To make a dent on global climate, we would need many power reactors, perhaps a thousand worldwide, perhaps more. Such a scale-up is not likely in view of nuclear power's high cost. Fukushima demonstrated that LWRs are capable of large accidental releases of radioactivity, roughly comparable to that at Chernobyl. While effective evacuation can protect people, the evacuates may never be able to return. The half- life of cesium 137, the main contaminant, is about 30 years, and it may take several half-lives to make an area acceptable for rehabilitation. In Fukushima about 100,000 persons were evacuated from an area of about 1000 square kilometer. When it comes to proliferation, there are strong arguments over whether we can have nuclear power without nuclear weapons. The 1946 US Acheson-Lilienthal Report argued that gaining nuclear energy's benefits without proliferation required strict international control. Inspection alone couldn't afford any reasonable security against the diversion of such materials to the purposes of war. The authors view is that the connection between technologies for nuclear power and nuclear weapons is still so close that you can't get the benefits of power without increasing the risks of weapons spread. Up to now we have allowed our interest in nuclear power to trump our bomb worries. It is time to rethink the proliferation risk of a large increase in nuclear power capacity.

  6. Regulatory oversight report 2012 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2012 zur nuklearen Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-04-15

    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

  7. Safety-Related Contractor Activities at Nuclear Power Plants. New Challenges for Regulatory Oversight

    Energy Technology Data Exchange (ETDEWEB)

    Chockie, Alan [Chockie Group International, Inc., Seattle, WA (United States)

    2005-09-15

    The use of contractors has been an integral and important part of the design, construction, operation, and maintenance of nuclear power plants. To ensure the safe and efficient completion of contracted tasks, each nuclear plant licensee has developed and refined formal contract management processes to meet their specific needs and plant requirements. Although these contract management processes have proven to be effective tools for the procurement of support and components tailored to the needs of nuclear power plants, contractor-related incidents and accidents have revealed some serious weaknesses with the implementation of these processes. Identifying and addressing implementation problems are becoming more complicated due to organizational and personnel changes affecting the nuclear power industry. The ability of regulators and licensees to effectively monitor and manage the safety-related performance of contractors will likely be affected by forthcoming organization and personnel changes due to: the aging of the workforce; the decline of the nuclear industry; and the deregulation of nuclear power. The objective of this report is to provide a review of current and potential future challenges facing safety-related contractor activities at nuclear power plants. The purpose is to assist SKI in establishing a strategy for the proactive oversight of contractor safety-related activities at Swedish nuclear power plants and facilities. The nature and role of contractors at nuclear plants is briefly reviewed in the first section of the report. The second section describes the essential elements of the contract management process. Although organizations have had decades of experience with the a contract management process, there remain a number of common implantation weaknesses that have lead to serious contractor-related incidents and accidents. These implementation weaknesses are summarized in the third section. The fourth section of the report highlights the

  8. Improved technical specifications and related improvements to safety in commercial Nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C. [EXCEL Services Corporation, 11921 Rockville Pike, Suite 100, Rockville, MD 20852 (United States)]. e-mail: donaldh@excelservices.com

    2004-07-01

    Many of the commercial nuclear power plants in the United States (US) have been converting a portion of the plant operating license known as the Technical Specifications (TS) in accordance with a document published by the US Nuclear Regulatory Commission (NRC). The TS prescribe commercial nuclear power plant operating requirements. There are several types of nuclear power plants in the US, based on the technology of different vendors, and there is an NRC document that supports each of the five different vendor designs. The NRC documents are known as the Improved Standard Technical Specifications (ISTS) and are contained in a separate document (NUREG series) for each one of the designs. EXCEL Services Corporation (hereinafter EXCEL) has played a major role in the development of the ISTS and in the development, licensing, and implementation of the plant specific Improved Technical Specifications (ITS) (which is based on the ISTS) for the commercial nuclear power plants in the US that have elected to make this conversion. There are currently 103 operating commercial nuclear power plants in the US and 68 of them have successfully completed the conversion to the ITS and are now operating in accordance with their plant specific ITS. The ISTS is focused mainly on safety by ensuring the commercial nuclear reactors can safely shut down and mitigate the consequences of any postulated transient and accident. It accomplishes this function by including requirements directly associated with safety in a document structured systematically and taking into account some key human factors and technical initiatives. This paper discusses the ISTS including its format, content, and detail, the history of the ISTS, the ITS development, licensing, and implementation process, the safety improvements resulting from a plant conversion to ITS, and the importance of the ITS Project to the industry. (Author)

  9. Considerations on Safety Evaluation of Safety grade Smart Transmitter in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyung Tae; Jeong, Choong heui [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-05-15

    Non-safety grade smart transmitters have been used for I and C systems of NPPs(Nuclear Power Plants). Smart transmitter is a microprocessor-based device including software and provides capability for digital signals to be communicated on top of the 4-20 mA analog signals. Recently, smart transmitters have been used for safety grade I and C systems as well as non-safety grade I and C system for SKN 3 and 4. Due to potential benefits of smart transmitter, it is anticipated smart transmitters will be widely used safety-related applications at NPPs. For those reasons, smart transmitter's technology and characteristics need to be investigated. Smart transmitters have been used for safety grade as well as non-safety grade I and C system since SKN 3 and 4. Due to potential benefits of smart transmitter, it is anticipated smart transmitters will be widely used safety-related applications at NPPs. For those reasons, smart transmitter's technology and characteristics need to be investigated. To get useful information about that, we surveyed EPRI qualification report, NRC event report, and SKN 3 and 4's review.

  10. Surveys of organizational culture and safety culture in nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Walter S. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2000-07-30

    The results of a survey of organizational culture at a nuclear power plant are summarized and compared with those of a similar survey which has been described in the literature on ''high-reliability organizations''. A general-purpose cultural inventory showed a profile of organizational style similar to that reported in the literature; the factor structure for the styles was also similar to that of the plant previously described. A specialized scale designed to measure ''safety culture'' did not distinguished among groups within the organization that would be expected to differ.

  11. SAFETY ANALYSIS METHODOLOGY FOR AGED CANDU® 6 NUCLEAR REACTORS

    Directory of Open Access Journals (Sweden)

    WOLFGANG HARTMANN

    2013-10-01

    Full Text Available This paper deals with the Safety Analysis for CANDU® 6 nuclear reactors as affected by main Heat Transport System (HTS aging. Operational and aging related changes of the HTS throughout its lifetime may lead to restrictions in certain safety system settings and hence some restriction in performance under certain conditions. A step in confirming safe reactor operation is the tracking of relevant data and their corresponding interpretation by the use of appropriate thermalhydraulic analytic models. Safety analyses ranging from the assessment of safety limits associated with the prevention of intermittent fuel sheath dryout for a slow Loss of Regulation (LOR analysis and fission gas release after a fuel failure are summarized. Specifically for fission gas release, the thermalhydraulic analysis for a fresh core and an 11 Effective Full Power Years (EFPY aged core was summarized, leading to the most severe stagnation break sizes for the inlet feeder break and the channel failure time. Associated coolant conditions provide the input data for fuel analyses. Based on the thermalhydraulic data, the fission product inventory under normal operating conditions may be calculated for both fresh and aged cores, and the fission gas release may be evaluated during the transient. This analysis plays a major role in determining possible radiation doses to the public after postulated accidents have occurred.

  12. Renovated Korean nuclear safety and security system: A review and suggestions to successful settlement

    Energy Technology Data Exchange (ETDEWEB)

    Chung, W. S.; Yun, S. W.; Lee, D. S. [Korea Atomic Energy Research Inst., Dukjin-dong 150, Yusung-gu, Daejon, R.O., 305-353 (Korea, Republic of); Go, D. Y. [Kyung Hee Univ., Kyung Hee daero 26, Dongdaemoon-gu, Seoul, R.O., 130-701 (Korea, Republic of)

    2012-07-01

    Questions of whether past nuclear regulatory body of Korea is not a proper system to monitor and check the country's nuclear energy policy and utilization have been raised. Moreover, a feeling of insecurity regarding nuclear safety after the nuclear accident in Japan has spread across the public. This has stimulated a renovation of the nuclear safety regime in Korea. The Nuclear Safety and Security Commission (NSSC) was launched on October 26, 2011 as a regulatory body directly under the President in charge of strengthening independence and nuclear safety. This was a meaningful event as the NSSC it is a much more independent regulatory system for Korea. However, the NSSC itself does not guarantee an enhanced public acceptance of the nuclear policy and stable use nuclear energy. This study introduces the new NSSC system and its details in terms of organization structure, appropriateness of specialty, budget stability, and management system. (authors)

  13. Software and hardware package for justification of safety of nuclear legacy facilities

    Directory of Open Access Journals (Sweden)

    P.A. Blokhin

    2017-03-01

    Full Text Available Determination of future fate for nuclear legacy facilities is becoming an extremely important near-term issue. This includes decommissioning options to be identified based on detailed justifications of respective designs. No general practice has been developed in Russia to address such issues, while the initial steps to this end have been made as part of the federal target program “Ensuring Nuclear and Radiation Safety for 2008 and Up to the Year 2015”. Problems arising in justification of decommissioning options for such facilities, in terms of radiation protection and safety assessments both for the public and personnel, differ greatly from tasks involved in design of new nuclear installations. The explanation is a critical shortage of information on both nuclear legacy facilities as such and on the RW they contain. Extra complexities stem from regulatory requirements to facilities of this type having changed greatly since the time these facilities were built. This puts priority on development of approaches to justification of nuclear, radiation and environmental safety. A software and hardware package, OBOYAN, has been developed to solve a great variety of tasks to be addressed as part of this problem based on a combination of software and hardware tools enabling analysis and justification of the NLS safety in their current state and in a long term. The package's key components are computational modules used to model radiation fields, radionuclide migration and distribution of contamination in water and air, as well as to estimate human doses and risks. The purpose of the study is to describe the structure and the functional capabilities of the package and to provide examples of the package application.

  14. ORNL Nuclear Safety Research and Development Program Bimonthly Report for July-August 1968

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W.B.

    2001-08-17

    The accomplishments during the months of July and August in the research and development program under way at ORNL as part of the U.S. Atomic Energy Commission's Nuclear Safety Program are summarized, Included in this report are work on various chemical reactions, as well as the release, characterization, and transport of fission products in containment systems under various accident conditions and on problems associated with the removal of these fission products from gas streams. Although most of this work is in general support of water-cooled power reactor technology, including LOFT and CSE programs, the work reflects the current safety problems, such as measurements of the prompt fuel element failure phenomena and the efficacy of containment spray and pool-suppression systems for fission-product removal. Several projects are also conducted in support of the high-temperature gas-cooled reactor (HTGR). Other major projects include fuel-transport safety investigations, a series of discussion papers on various aspects of water-reactor technology, antiseismic design of nuclear facilities, and studies of primary piping and steel, pressure-vessel technology. Experimental work relative to pressure-vessel technology includes investigations of the attachment of nozzles to shells and the implementation of joint AEX-PVFX programs on heavy-section steel technology and nuclear piping, pumps, and valves. Several of the projects are directly related to another major undertaking; namely, the AEC's standards program, which entails development of engineering safeguards and the establishment of codes and standards for government-owned or -sponsored reactor facilities. Another task, CHORD-S, is concerned with the establishment of computer programs for the evaluation of reactor design data, The recent activities of the NSIC and the Nuclear Safety journal in behalf of the nuclear community are also discussed.

  15. Engineering thinking in emergency situations: A new nuclear safety concept.

    Science.gov (United States)

    Guarnieri, Franck; Travadel, Sébastien

    2014-11-01

    The lessons learned from the Fukushima Daiichi accident have focused on preventive measures designed to protect nuclear reactors, and crisis management plans. Although there is still no end in sight to the accident that occurred on March 11, 2011, how engineers have handled the aftermath offers new insight into the capacity of organizations to adapt in situations that far exceed the scope of safety standards based on probabilistic risk assessment and on the comprehensive identification of disaster scenarios. Ongoing crises in which conventional resources are lacking, but societal expectations are high, call for "engineering thinking in emergency situations." This is a new concept that emphasizes adaptability and resilience within organizations-such as the ability to create temporary new organizational structures; to quickly switch from a normal state to an innovative mode; and to integrate a social dimension into engineering activities. In the future, nuclear safety oversight authorities should assess the ability of plant operators to create and implement effective engineering strategies on the fly, and should require that operators demonstrate the capability for resilience in the aftermath of an accident.

  16. Nuclear emergency preparedness. Final report of the Nordic nuclear safety research project BOK-1

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, Bent [Risoe National Lab., Roskilde (Denmark)

    2002-02-01

    Final report of the Nordic Nuclear Safety Research project BOK-1. The BOK-1 project, 'Nuclear Emergency Preparedness', was carried out in 1998-2001 with participants from the Nordic and Baltic Sea regions. The project consists of six sub-projects: Laboratory measurements and quality assurance (BOK-1.1); Mobile measurements and measurement strategies (BOK-1.2); Field measurement and data assimilation (BOK-1.3); Countermeasures in agriculture and forestry (BOK-1.4); Emergency monitoring in the Nordic and Baltic Sea countries (BOK-1.5); and Nuclear exercises (BOK-1.6). For each sub-project, the project outline, objectives and organization are described and main results presented. (au)

  17. Impact of nuclear data uncertainty on safety calculations for spent nuclear fuel geological disposal

    Directory of Open Access Journals (Sweden)

    Herrero J.J.

    2017-01-01

    Full Text Available In the design of a spent nuclear fuel disposal system, one necessary condition is to show that the configuration remains subcritical at time of emplacement but also during long periods covering up to 1,000,000 years. In the context of criticality safety applying burn-up credit, k-eff eigenvalue calculations are affected by nuclear data uncertainty mainly in the burnup calculations simulating reactor operation and in the criticality calculation for the disposal canister loaded with the spent fuel assemblies. The impact of nuclear data uncertainty should be included in the k-eff value estimation to enforce safety. Estimations of the uncertainty in the discharge compositions from the CASMO5 burn-up calculation phase are employed in the final MCNP6 criticality computations for the intact canister configuration; in between, SERPENT2 is employed to get the spent fuel composition along the decay periods. In this paper, nuclear data uncertainty was propagated by Monte Carlo sampling in the burn-up, decay and criticality calculation phases and representative values for fuel operated in a Swiss PWR plant will be presented as an estimation of its impact.

  18. Implementation of the obligations of the convention on nuclear safety. Fourth Swiss report in accordance with Article 5

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-15

    Switzerland has signed the Convention on Nuclear Safety. Most of the requirements of the articles of the Convention were already standard practice in Switzerland. In the last years, all Swiss nuclear power plants (NPPs) as well as the Swiss Federal Nuclear Safety Inspectorate (HSK) built up documented quality management systems. The independence of HSK from licensing authorities is fulfilled on a technical level. In 2005, a new Nuclear Energy Act came into force requiring formal independence of the supervisory authorities from the licensing authorities. A separate act to legally settle the Inspectorate's fully independent status was adopted by Parliament. HSK participates in international projects and is represented in numerous nuclear safety working groups in order to ensure the exchange of scientific, technical and regulatory know-how. The regulatory processes applied to the licensing and safety surveillance of nuclear installations and their operation are up to date with the current state of science and technology. Deterministic and probabilistic safety evaluations guide and prioritise inspections and provide the basis for a graded approach to safety review and assessment. The surveillance of the NPPs' operating, control and safety systems, their component performance and integrity, their organisational and human aspects as well as the management, conditioning and interim storage of radioactive waste are permanent features of the supervisory authority's activities. Within the frame of a new integrated oversight process there is an annual systematic assessment of nuclear safety for each NPP based on the analysis of events, inspection results and operator licensing reviews. The assurance of low radiation doses to both NPP workers and the general public is an additional goal that is directly associated with the safe operation of NPPs. In case of an accident in a nuclear installation, contingency plans are in place and are continually updated

  19. Evaluating safety-critical organizations - emphasis on the nuclear industry

    Energy Technology Data Exchange (ETDEWEB)

    Reiman, Teemu; Oedewald, Pia (VTT, Technical Research Centre of Finland (Finland))

    2009-04-15

    - it is understood that safety is a complex phenomenon. Safety is understood as a property of an entire system and not just absence of incidents - people feel personally responsible for the safety of the entire system, they feel they can have an effect on safety - the organizations aims for understanding the hazards and anticipating the risks in their activities - the organization is alert to the possibility of an unanticipated event - good prerequisites for carrying out the daily work exist. An organizational evaluation should aim at reasoning the: - sources of effectiveness in the organizational dimensions - sources of ineffectiveness in the organization dimensions - social processes in the organization - psychological outcomes of the current organization on a personnel level, e.g. motivation, understanding of hazards and sense of control. When drawing inferences from the organizational evaluations and defining development initiatives, it is important to consider actions that will promote and maintain the strengths of the organization as well as actions that will address and develop the weak areas. Issues associated with data collection and choice of methods has been a topic of much discussion in the field of evaluation of safety-critical organizations. We argue that the problem of collecting data is not the most important problem in terms of facilitating valid evaluations. A more important problem concerns the criteria that are used, as well as the operationalization of criteria into something measurable. Too much effort has been spent on methods and too little on contemplating the question of valid evaluation criteria and a valid means of deducing from the data whether the criteria are fulfilled. In order to accomplish this, a valid evaluation framework is needed, which incorporates the idea of organization as a complex sociotechnical system. This report has been an attempt to illustrate the premises and key issues to consider in organizational evaluations. No

  20. Assessment of the current status of basic nuclear data compilations

    Energy Technology Data Exchange (ETDEWEB)

    Riemer, R.L.

    1992-12-31

    The Panel on Basic Nuclear Data Compilations believes that it is important to provide the user with an evaluated nuclear database of the highest quality, dependability, and currency. It is also important that the evaluated nuclear data are easily accessible to the user. In the past the panel concentrated its concern on the cycle time for the publication of A-chain evaluations. However, the panel now recognizes that publication cycle time is no longer the appropriate goal. Sometime in the future, publication of the evaluated A-chains will evolve from the present hard-copy Nuclear Data Sheets on library shelves to purely electronic publication, with the advent of universal access to terminals and the nuclear databases. Therefore, the literature cut-off date in the Evaluated Nuclear Structure Data File (ENSDF) is rapidly becoming the only important measure of the currency of an evaluated A-chain. Also, it has become exceedingly important to ensure that access to the databases is as user-friendly as possible and to enable electronic publication of the evaluated data files. Considerable progress has been made in these areas: use of the on-line systems has almost doubled in the past year, and there has been initial development of tools for electronic evaluation, publication, and dissemination. Currently, the nuclear data effort is in transition between the traditional and future methods of dissemination of the evaluated data. Also, many of the factors that adversely affect the publication cycle time simultaneously affect the currency of the evaluated nuclear database. Therefore, the panel continues to examine factors that can influence cycle time: the number of evaluators, the frequency with which an evaluation can be updated, the review of the evaluation, and the production of the evaluation, which currently exists as a hard-copy issue of Nuclear Data Sheets.

  1. Nuclear energy: current situation and prospects to 2020.

    Science.gov (United States)

    Ion, Sue

    2007-04-15

    For close to half a century nuclear fission has been providing reliable supplies of electricity to the UK, with virtually no emissions of carbon dioxide. Over that period, the UK nuclear industry has avoided the emission of over one and a half billion tonnes of CO2. Yet no nuclear plant has been built in the UK for over two decades even though many of the stations in our current fleet are now within a decade or so of the end of their lifetime. Without new plants being ordered soon, the UK's nuclear capacity will decline dramatically, from 23% today to 3% post-2020--just as considerations of supply security and climate change are becoming increasingly important. Elsewhere in the world, many countries such as China, India, Japan, South Korea, Finland and France are building new stations. Other countries such as the USA, South Africa, and some nations that currently do not have nuclear stations (such as Indonesia and Poland) are making preparations for future nuclear stations. Globally capacity factors for nuclear plants are higher than they have ever been, averaging around 85% and with the best stations achieving well over 90%. Lifetime can be 60 years. That the economics of such stations compete well with other technologies is well founded and easily verifiable--especially in the face of rising fossil fuel prices and the pricing in of costs for CO2 emissions--both of which stand to improve the economics of nuclear energy still further. Waste volumes arising from modern plants are just a fraction of those of some earlier stations, and the technologies are in place to deal with them safely and effectively. Following recent reviews and international developments, there is growing confidence that internationally available competitive designs of nuclear plant will provide part of the solution to the UK's long-term energy needs.

  2. The Evolution of Process Safety: Current Status and Future Direction.

    Science.gov (United States)

    Mannan, M Sam; Reyes-Valdes, Olga; Jain, Prerna; Tamim, Nafiz; Ahammad, Monir

    2016-06-01

    The advent of the industrial revolution in the nineteenth century increased the volume and variety of manufactured goods and enriched the quality of life for society as a whole. However, industrialization was also accompanied by new manufacturing and complex processes that brought about the use of hazardous chemicals and difficult-to-control operating conditions. Moreover, human-process-equipment interaction plus on-the-job learning resulted in further undesirable outcomes and associated consequences. These problems gave rise to many catastrophic process safety incidents that resulted in thousands of fatalities and injuries, losses of property, and environmental damages. These events led eventually to the necessity for a gradual development of a new multidisciplinary field, referred to as process safety. From its inception in the early 1970s to the current state of the art, process safety has come to represent a wide array of issues, including safety culture, process safety management systems, process safety engineering, loss prevention, risk assessment, risk management, and inherently safer technology. Governments and academic/research organizations have kept pace with regulatory programs and research initiatives, respectively. Understanding how major incidents impact regulations and contribute to industrial and academic technology development provides a firm foundation to address new challenges, and to continue applying science and engineering to develop and implement programs to keep hazardous materials within containment. Here the most significant incidents in terms of their impact on regulations and the overall development of the field of process safety are described.

  3. Sensitivity-Uncertainty Based Nuclear Criticality Safety Validation

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Forrest B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Univ. of New Mexico, Albuquerque, NM (United States). Nuclear Engineering Dept.

    2016-09-20

    These are slides from a seminar given to the University of Mexico Nuclear Engineering Department. Whisper is a statistical analysis package developed to support nuclear criticality safety validation. It uses the sensitivity profile data for an application as computed by MCNP6 along with covariance files for the nuclear data to determine a baseline upper-subcritical-limit for the application. Whisper and its associated benchmark files are developed and maintained as part of MCNP6, and will be distributed with all future releases of MCNP6. Although sensitivity-uncertainty methods for NCS validation have been under development for 20 years, continuous-energy Monte Carlo codes such as MCNP could not determine the required adjoint-weighted tallies for sensitivity profiles. The recent introduction of the iterated fission probability method into MCNP led to the rapid development of sensitivity analysis capabilities for MCNP6 and the development of Whisper. Sensitivity-uncertainty based methods represent the future for NCS validation – making full use of today’s computer power to codify past approaches based largely on expert judgment. Validation results are defensible, auditable, and repeatable as needed with different assumptions and process models. The new methods can supplement, support, and extend traditional validation approaches.

  4. Application of CFD Codes in Nuclear Reactor Safety Analysis

    Directory of Open Access Journals (Sweden)

    T. Höhne

    2010-01-01

    Full Text Available Computational Fluid Dynamics (CFD is increasingly being used in nuclear reactor safety (NRS analyses as a tool that enables safety relevant phenomena occurring in the reactor coolant system to be described in more detail. Numerical investigations on single phase coolant mixing in Pressurised Water Reactors (PWR have been performed at the FZD for almost a decade. The work is aimed at describing the mixing phenomena relevant for both safety analysis, particularly in steam line break and boron dilution scenarios, and mixing phenomena of interest for economical operation and the structural integrity. For the experimental investigation of horizontal two phase flows, different non pressurized channels and the TOPFLOW Hot Leg model in a pressure chamber was build and simulated with ANSYS CFX. In a common project between the University of Applied Sciences Zittau/Görlitz and FZD the behaviour of insulation material released by a LOCA released into the containment and might compromise the long term emergency cooling systems is investigated. Moreover, the actual capability of CFD is shown to contribute to fuel rod bundle design with a good CHF performance.

  5. Legislation for the countermeasures on special issues of nuclear safety regulations

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Heon Jin; Oh, Ho Chul [Chongju Univ., Cheongju (Korea, Republic of)

    2004-02-15

    Since the present nuclear safety regulation has some legal problems that refer to special issues and contents of regulatory provisions, this report has preformed research on the legal basic theory of nuclear safety regulation to solve the problems. In addition, this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation.

  6. Current Status of the Cyber Threat Assessment for Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyun Doo [KINAC, Daejeon (Korea, Republic of)

    2016-05-15

    In December 2014, unknown hackers hacked internal documents sourced from Korea Hydro and Nuclear Power (KHNP) and those electronic documents were posted five times on a Social Network Service (SNS). The data included personal profiles, flow charts, manuals and blueprints for installing pipes in the nuclear power plant. Although the data were not critical to operation or sabotage of the plant, it threatened people and caused social unrest in Korea and neighboring countries. In December 2015, cyber attack on power grid caused a blackout for hundreds of thousands of people in Ukraine. The power outage was caused by a sophisticated attack using destructive malware called 'BlackEnergy'. Cyber attacks are reality in today's world and critical infrastructures are increasingly targeted. Critical infrastructures, such as the nuclear power plant, need to be proactive and protect the nuclear materials, assets and facilities from potential cyber attacks. The threat assessment document and its detailed procedure are confidential for the State. Nevertheless, it is easy to find cooperation on assessing and evaluating the threats of nuclear materials and facilities with other government departments or agencies including the national police. The NSSC and KINAC also cooperated with the National Intelligence Service (NIS) and National Security Research Institute (NSR). However, robust cyber threat assessment system and regular consultative group should be established with domestic and overseas organization including NIS, NSR, the National Police Agency and the military force to protect and ensure to safety of people, public and environment from rapidly changing and upgrading cyber threats.

  7. Nuclear versus fossil - weighing up the safety issues (lists accidents for each energy option)

    Energy Technology Data Exchange (ETDEWEB)

    Gittus, J. (British Nuclear Forum, London (United Kingdom))

    1992-01-01

    In the public mind a large question mark still hangs over the safety of nuclear power. But compared with the fossil alternatives, nuclear power can be shown to provide the cleaner, safer option. (author).

  8. Application of Framework for Integrating Safety, Security and Safeguards (3Ss) into the Design Of Used Nuclear Fuel Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Badwan, Faris M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Demuth, Scott F [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-01-06

    Department of Energy’s Office of Nuclear Energy, Fuel Cycle Research and Development develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development focused on used nuclear fuel recycling and waste management to meet U.S. needs. Used nuclear fuel is currently stored onsite in either wet pools or in dry storage systems, with disposal envisioned in interim storage facility and, ultimately, in a deep-mined geologic repository. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Integrating safety, security, and safeguards (3Ss) fully in the early stages of the design process for a new nuclear facility has the potential to effectively minimize safety, proliferation, and security risks. The 3Ss integration framework could become the new national and international norm and the standard process for designing future nuclear facilities. The purpose of this report is to develop a framework for integrating the safety, security and safeguards concept into the design of Used Nuclear Fuel Storage Facility (UNFSF). The primary focus is on integration of safeguards and security into the UNFSF based on the existing Nuclear Regulatory Commission (NRC) approach to addressing the safety/security interface (10 CFR 73.58 and Regulatory Guide 5.73) for nuclear power plants. The methodology used for adaptation of the NRC safety/security interface will be used as the basis for development of the safeguards /security interface and later will be used as the basis for development of safety and safeguards interface. Then this will complete the integration cycle of safety, security, and safeguards. The overall methodology for integration of 3Ss will be proposed, but only the integration of safeguards and security will be applied to the design of the

  9. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, January 1--June 30, 1988

    Energy Technology Data Exchange (ETDEWEB)

    Baum, J W; Boccio, J L; Diamond, D; Fitzpatrick, R; Ginsberg, T; Greene, G A; Guppy, J G; Hall, R E; Higgins, J C; Weiss, A J [comp.

    1988-12-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through December 31, 1987.

  10. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, October 1--December 31, 1988

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, A J; Azarm, A; Baum, J W; Boccio, J L; Carew, J; Diamond, D J; Fitzpatrick, R; Ginsberg, T; Greene, G A; Guppy, J G; Haber, S B

    1989-07-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through September 30, 1988.

  11. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, July 1--September 30, 1988

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, A J [comp.

    1989-02-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through June 30, 1988. 71 figs., 24 tabs.

  12. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, January 1--March 31, 1989

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, A.J. (comp.)

    1989-08-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through December 31, 1988.

  13. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, October 1--December 31, 1988

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, A J; Azarm, A; Baum, J W; Boccio, J L; Carew, J; Diamond, D J; Fitzpatrick, R; Ginsberg, T; Greene, G A; Guppy, J G; Haber, S B

    1989-07-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through September 30, 1988.

  14. Institute of Energy and Climate Research IEK-6. Nuclear waste management and reactor safety report 2009/2010. Material science for nuclear waste management

    Energy Technology Data Exchange (ETDEWEB)

    Klinkenberg, M.; Neumeier, S.; Bosbach, D. (eds.)

    2011-07-01

    Due to the use of nuclear energy about 17.000 t (27.000 m{sup 3}) of high level waste and about 300.000 m{sup 3} of low and intermediated level waste will have accumulated in Germany until 2022. Research in the Institute of Energy and Climate Research (IEK-6), Nuclear Waste Management and Reactor Safety Division focuses on fundamental and applied aspects of the safe management of nuclear waste - in particular the nuclear aspects. In principle, our research in Forschungszentrum Juelich is looking at the material science/solid state aspects of nuclear waste management. It is organized in several research areas: The long-term safety of nuclear waste disposal is a key issue when it comes to the final disposal of high level nuclear waste in a deep geological formation. We are contributing to the scientific basis for the safety case of a nuclear waste repository in Germany. In Juelich we are focusing on a fundamental understanding of near field processes within a waste repository system. The main research topics are spent fuel corrosion and the retention of radionuclides by secondary phases. In addition, innovative waste management strategies are investigated to facilitate a qualified decision on the best strategy for Germany. New ceramic waste forms for disposal in a deep geological formation are studied as well as the partitioning of long-lived actinides. These research areas are supported by our structure research group, which is using experimental and computational approaches to examine actinide containing compounds. Complementary to these basic science oriented activities, IEK-6 also works on rather applied aspects. The development of non-destructive methods for the characterisation of nuclear waste packages has a long tradition in Juelich. Current activities focus on improving the segmented gamma scanning technique and the prompt gamma neutron activation analysis. Furthermore, the waste treatment group is developing concepts for the safe management of nuclear

  15. Legislation for the countermeasures on special issues of nuclear safety regulations

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Hak Man; Oh, Ho Chul [Chongju Univ., Cheongju (Korea, Republic of)

    2003-02-15

    Since the present legal system on nuclear safety regulation has some problems that refer to contents of regulatory provisions, this mid-report has preformed research on the legal basic theory of nuclear safety regulation. And then secondly this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation. In order to interpret easily this report finally took the cases of judicial precedents on nuclear safety regulation in USA, Germany, Japan and Korea.

  16. Proceedings of the 1984 DOE nuclear reactor and facility safety conference. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    1984-01-01

    This report is a collection of papers on reactor safety. The report takes the form of proceedings from the 1984 DOE Nuclear Reactor and Facility Safety Conference, Volume II of two. These proceedings cover Safety, Accidents, Training, Task/Job Analysis, Robotics and the Engineering Aspects of Man/Safety interfaces.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-11-01

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

  18. Artificial neural network model for prediction of safety performance indicators goals in nuclear plants

    Energy Technology Data Exchange (ETDEWEB)

    Souto, Kelling C.; Nunes, Wallace W. [Instituto Federal de Educacao, Ciencia e Tecnologia do Rio de Janeiro, Nilopolis, RJ (Brazil). Lab. de Aplicacoes Computacionais; Machado, Marcelo D., E-mail: dornemd@eletronuclear.gov.b [ELETROBRAS Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil). Gerencia de Combustivel Nuclear - GCN.T

    2011-07-01

    Safety performance indicators have been developed to provide a quantitative indication of the performance and safety in various industry sectors. These indexes can provide assess to aspects ranging from production, design, and human performance up to management issues in accordance with policy, objectives and goals of the company. The use of safety performance indicators in nuclear power plants around the world is a reality. However, it is necessary to periodically set goal values. Such goals are targets relating to each of the indicators to be achieved by the plant over a predetermined period of operation. The current process of defining these goals is carried out by experts in a subjective way, based on actual data from the plant, and comparison with global indices. Artificial neural networks are computational techniques that present a mathematical model inspired by the neural structure of intelligent organisms that acquire knowledge through experience. This paper proposes an artificial neural network model aimed at predicting values of goals to be used in the evaluation of safety performance indicators for nuclear power plants. (author)

  19. Artificial neural network model for prediction of safety performance indicators goals in nuclear plants

    Energy Technology Data Exchange (ETDEWEB)

    Souto, Kelling C.; Nunes, Wallace W. [Instituto Federal de Educacao, Ciencia e Tecnologia do Rio de Janeiro, Nilopolis, RJ (Brazil). Lab. de Aplicacoes Computacionais; Machado, Marcelo D., E-mail: dornemd@eletronuclear.gov.b [ELETROBRAS Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil). Gerencia de Combustivel Nuclear - GCN.T

    2011-07-01

    Safety performance indicators have been developed to provide a quantitative indication of the performance and safety in various industry sectors. These indexes can provide assess to aspects ranging from production, design, and human performance up to management issues in accordance with policy, objectives and goals of the company. The use of safety performance indicators in nuclear power plants around the world is a reality. However, it is necessary to periodically set goal values. Such goals are targets relating to each of the indicators to be achieved by the plant over a predetermined period of operation. The current process of defining these goals is carried out by experts in a subjective way, based on actual data from the plant, and comparison with global indices. Artificial neural networks are computational techniques that present a mathematical model inspired by the neural structure of intelligent organisms that acquire knowledge through experience. This paper proposes an artificial neural network model aimed at predicting values of goals to be used in the evaluation of safety performance indicators for nuclear power plants. (author)

  20. ABWR Nuclear Power Plant : Safety nuclear electricity and low cost; La Central Nuclear ABWR: Electricidad de origen nuclear segura y de costa previsible

    Energy Technology Data Exchange (ETDEWEB)

    Redding, J.; Segarr, J.

    2002-07-01

    The Advanced Boiling Water Reactor (ABWR) nuclear plant defines the new generation of advanced nuclear plant designs that have achieved higher levels of safety and can satisfy the increasing needs for low cost electricity. Two ABWRs in Japan are now in their fifth cycles of operation. By every measure, these units have proven themselves successful. The construction of two more ABWRs in Taiwan at the Lungmen site is once again proceeding smoothly. Attention is now being focused on europe where the ABWR has been adapted to meet European safety requirements through utility sponsored programs. (Author)

  1. NUCLEAR CARDIOLOGY, CURRENT APPLICATIONS IN CLINICAL-PRACTICE

    NARCIS (Netherlands)

    NIEMEYER, MG; VANDERWALL, EE; KUIJPER, AFM; CLEOPHAS, AT; PAUWELS, EKJ

    1995-01-01

    The clinical applications of nuclear cardiology have rapidly expanded since the introduction of suitable imaging cameras and readily applicable isotopes. The currently available methods can provide useful data on estimates of ventricular function and detection of myocardial ischemia for adequate pat

  2. Dismantlement of nuclear facilities decommissioned from the Russian navy: Enhancing regulatory supervision of nuclear and radiation safety

    Energy Technology Data Exchange (ETDEWEB)

    Sneve, M.K.

    2013-03-01

    The availability of up to date regulatory norms and standards for nuclear and radiation safety, relevant to the management of nuclear legacy situations, combined with effective and efficient regulatory procedures for licensing and monitoring compliance, are considered to be extremely important. Accordingly the NRPA has set up regulatory cooperation programs with corresponding authorities in the Russian Federation. Cooperation began with the civilian regulatory authorities and was more recently extended to include the military authority and this joint cooperation supposed to develop the regulatory documents to improve supervision over nuclear and radiation safety while managing the nuclear military legacy facilities in Northwest Russia and other regions of the country. (Author)

  3. A probabilistic safety analysis of incidents in nuclear research reactors.

    Science.gov (United States)

    Lopes, Valdir Maciel; Agostinho Angelo Sordi, Gian Maria; Moralles, Mauricio; Filho, Tufic Madi

    2012-06-01

    This work aims to evaluate the potential risks of incidents in nuclear research reactors. For its development, two databases of the International Atomic Energy Agency (IAEA) were used: the Research Reactor Data Base (RRDB) and the Incident Report System for Research Reactor (IRSRR). For this study, the probabilistic safety analysis (PSA) was used. To obtain the result of the probability calculations for PSA, the theory and equations in the paper IAEA TECDOC-636 were used. A specific program to analyse the probabilities was developed within the main program, Scilab 5.1.1. for two distributions, Fischer and chi-square, both with the confidence level of 90 %. Using Sordi equations, the maximum admissible doses to compare with the risk limits established by the International Commission on Radiological Protection (ICRP) were obtained. All results achieved with this probability analysis led to the conclusion that the incidents which occurred had radiation doses within the stochastic effects reference interval established by the ICRP-64.

  4. Safety assessment of a nuclear power plant building subjected to an aircraft crash

    Energy Technology Data Exchange (ETDEWEB)

    Thai, Duc-Kien; Kim, Seung-Eock, E-mail: sekim@sejong.ac.kr

    2015-11-15

    Highlights: • Numerical analysis of a nuclear auxiliary building under aircraft crash is conducted. • The analysis result of impact force is verified using the Riera function. • The safety assessment is performed with regard to different impact scenarios. • Discussions and conclusions on safety of the nuclear building are presented. - Abstract: This paper presents a safety assessment of a nuclear building subjected to an aircraft crash using numerical analysis. For impact simulation, the reinforced concrete (RC) Primary Auxiliary Building (PAB) of the Korea Standard Nuclear Power Plant (KSNP) is fully modeled and an aircraft model of a Boeing 767-400 is used. The Riera function is used to verify the analysis result of impact force–time history. The IRIS test is used to verify the structural behavior of the RC wall under impact loading. The safety assessment of the building is performed with regard to different impact scenarios. The safety of the nuclear building under aircraft crash, including (1) global structural safety, (2) local structural safety, and (3) vibration safety are evaluated and discussed. The results show that the global and local structural safety of the PAB is ensured in all impact scenarios. However, the vibration safety of the building is not ensured. In accordance, the regulatory guide of United States Nuclear Regulatory Commission (U.S. NRC), shutdown of the nuclear power plant is required.

  5. Human and organizational factors in nuclear safety; Factores humanos y organizativos en la seguridad nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, A.; Barrientos, M.; Gil, B.

    2015-07-01

    Nuclear installations are socio technical systems where human and organizational factors, in both utilities and regulators, have a significant impact on safety. Three Mile Island (TMI) accident, original of several initiatives in the human factors field, nevertheless became a lost opportunity to timely acquire lessons related to the upper tiers of the system. Nowadays, Spanish nuclear installations have integrated in their processes specialists and activities in human and organizational factors, promoted by the licensees After many years of hard work, Spanish installations have achieved a better position to face new challenges, such as those posed by Fukushima. With this experience, only technology-centered action plan would not be acceptable, turning this accident in yet another lost opportunity. (Author)

  6. Current Status and Applications of Integrated Safety Assessment and Simulation Code System for ISA

    Directory of Open Access Journals (Sweden)

    J.M. Izquierdo

    2017-03-01

    Full Text Available This paper reviews current status of the unified approach known as integrated safety assessment (ISA, as well as the associated SCAIS (simulation codes system for ISA computer platform. These constitute a proposal, which is the result of collaborative action among the Nuclear Safety Council (CSN, University of Madrid (UPM, and NFQ Solutions S.L, aiming to allow independent regulatory verification of industry quantitative risk assessments. The content elaborates on discussions of the classical treatment of time in conventional probabilistic safety assessment (PSA sequences and states important conclusions that can be used to avoid systematic and unacceptable underestimation of the failure exceedance frequencies. The unified ISA method meets this challenge by coupling deterministic and probabilistic mutual influences. The feasibility of the approach is illustrated with some examples of its application to a real size plant.

  7. Reviewing real-time performance of nuclear reactor safety systems

    Energy Technology Data Exchange (ETDEWEB)

    Preckshot, G.G. [Lawrence Livermore National Lab., CA (United States)

    1993-08-01

    The purpose of this paper is to recommend regulatory guidance for reviewers examining real-time performance of computer-based safety systems used in nuclear power plants. Three areas of guidance are covered in this report. The first area covers how to determine if, when, and what prototypes should be required of developers to make a convincing demonstration that specific problems have been solved or that performance goals have been met. The second area has recommendations for timing analyses that will prove that the real-time system will meet its safety-imposed deadlines. The third area has description of means for assessing expected or actual real-time performance before, during, and after development is completed. To ensure that the delivered real-time software product meets performance goals, the paper recommends certain types of code-execution and communications scheduling. Technical background is provided in the appendix on methods of timing analysis, scheduling real-time computations, prototyping, real-time software development approaches, modeling and measurement, and real-time operating systems.

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

    Directory of Open Access Journals (Sweden)

    Salih Sinan Gültekin

    2013-12-01

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

  9. Nuclear Safety Analysis for the Mars Exploration Rover 2003 Project

    Science.gov (United States)

    Firstenberg, Henry; Rutger, Lyle L.; Mukunda, Meera; Bartram, Bart W.

    2004-02-01

    The National Aeronautics and Space Administration's Mars Exploration Rover (MER) 2003 project is designed to place two mobile laboratories (Rovers) on Mars to remotely characterize a diversity of rocks and soils. Milestones accomplished so far include two successful launches of identical spacecraft (the MER-A and MER-B missions) from Cape Canaveral Air Force Station, Florida on June 10 and July 7, 2003. Each Rover uses eight Light Weight Radioisotope Heater Units (LWRHUs) fueled with plutonium-238 dioxide to provide local heating of Rover components. The LWRHUs are provided by the U.S. Department of Energy. In addition, small quantities of radioactive materials in sealed sources are used in scientific instrumentation on the Rover. Due to the radioactive nature of these materials and the potential for accidents, a formal Launch Approval Process requires the preparation of a Final Safety Analysis Report (FSAR) for submittal to and independent review by an Interagency Nuclear Safety Review Panel. This paper presents a summary of the FSAR in terms of potential accident scenarios, probabilities, source terms, radiological consequences, mission risks, and uncertainties in the reported results.

  10. Radiation Authority and Nuclear Safety in Finland (STUK); La autoridad de Radiacion y Seguridad Nuclear de Finlandia (STUK)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    Created in 1958 as an institute in charge of inspecting radioactive equipment used in hospitals, STUK is nowadays a specialised organisation whose functions cover all fields for applying radiation and nuclear safety. (Author)

  11. Atomic clock with nuclear transition: current status in TU Wien

    OpenAIRE

    Kazakov, G. A.; Schreitl, M.; Winkler, G.; Sterba, J. H.; Steinhauser, G; Schumm, T.

    2011-01-01

    The nucleus of 229Thorium presents a unique isomer state of very low energy and long lifetime, current estimates are around 7.8 eV and seconds to hours respectively. This nuclear transitions therefore is a promising candidate for a novel type of frequency standard and several groups worldwide have set out to investigate this system. Our aim is to construct a "solid state nuclear clock", i.e. a frequency standard where Thorium ions are implanted into Calciumfluoride crystals transparent in vac...

  12. Nuclear spin dependent atomic parity violation, nuclear anapole moments, and the hadronic axial neutral current

    Energy Technology Data Exchange (ETDEWEB)

    Bouchiat, C.; Piketty, C.A. (Ecole Normale Superieure, 75 - Paris (France). Lab. de Physique Theorique)

    1991-01-01

    Left-right symmetries in atomic transitions, depending upon the nuclear spin, could be a source of information on the neutral hadronic axial current. We show that the relevant electroweak parameter can be extracted from experiment by measuring hyperfine component ratios which do not involve the knowledge of the atomic wave function. In the standard electroweak model, the parity violating electron-nucleus interaction associated with the hadronic axial neutral current is accidently suppressed and, as a consequence, dominated by the electron interaction with the nuclear anapole moment, which describes the effect of the parity violating nuclear forces on the nucleus electromagnetic current. One of our objectives was to identify the various physical mechanisms which determine the size of the nuclear anapole moments. As an important step, we have established a simple relation between the anapole moment and the nuclear spin magnetization. From this relation it follows that the computation of the anapole moment can be reduced to that of one-body operators. The basic tool is a unitary transformation W which eliminates the one-body parity violating potential from the nuclear hamiltonian. A particular attention was paid to nuclear correlation effects. They are treated semi-empirically in the independent pair approximation. The nuclear anapole moments of {sup 85}Rb, {sup 133}Cs, and {sup 209}Bi have been evaluated for three sets of parity violating meson-nucleon coupling constants, taking into account configuration mixing effects in a semi-empirical way. We suggest a possible strategy to disentangle the axial neutral current from the anapole moment contribution. (orig.).

  13. Fuzzy-logic-based safety verification framework for nuclear power plants.

    Science.gov (United States)

    Rastogi, Achint; Gabbar, Hossam A

    2013-06-01

    This article presents a practical implementation of a safety verification framework for nuclear power plants (NPPs) based on fuzzy logic where hazard scenarios are identified in view of safety and control limits in different plant process values. Risk is estimated quantitatively and compared with safety limits in real time so that safety verification can be achieved. Fuzzy logic is used to define safety rules that map hazard condition with required safety protection in view of risk estimate. Case studies are analyzed from NPP to realize the proposed real-time safety verification framework. An automated system is developed to demonstrate the safety limit for different hazard scenarios.

  14. Current safety practices in nano-research laboratories in China.

    Science.gov (United States)

    Zhang, Can; Zhang, Jing; Wang, Guoyu

    2014-06-01

    China has become a key player in the global nanotechnology field, however, no surveys have specifically examined safety practices in the Chinese nano-laboratories in depth. This study reports results of a survey of 300 professionals who work in research laboratories that handle nanomaterials in China. We recruited participants at three major nano-research laboratories (which carry out research in diverse fields such as chemistry, material science, and biology) and the nano-chemistry session of the national meeting of the Chinese Chemical Society. Results show that almost all nano-research laboratories surveyed had general safety regulations, whereas less than one third of respondents reported having nanospecific safety rules. General safety measures were in place in most surveyed nano-research laboratories, while nanospecific protective measures existed or were implemented less frequently. Several factors reported from the scientific literature including nanotoxicology knowledge gaps, technical limitations on estimating nano-exposure, and the lack of nano-occupational safety legislation may contribute to the current state of affairs. With these factors in mind and embracing the precautionary principle, we suggest strengthening or providing nanosafety training (including raising risk awareness) and establishing nanosafety guidelines in China, to better protect personnel in the nano-workplace.

  15. Application of Safety Instrumented System (SIS) approach in older nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Nasimi, Elnara; Gabbar, Hossam A., E-mail: hossam.gabbar@uoit.ca

    2016-05-15

    Highlights: • Study Safety Instrumented System (SIS) design for older nuclear power plant. • Apply SIS on Reheater Drains (RD) system. • Apply IEC 61508/61511 to design safety system. • Evaluate risk reduction based on proposed SIS design. - Abstract: In order to remain economically effective and financially profitable, the modern industries have to take their safety culture to a higher level and consider production losses in addition to simple accident prevention techniques. Ideally, compliance with safety requirements start during early design stages, but in some older facilities provisions for Safety Instrumented Systems (SIS) may not have been originally included. In this paper, a case study of a Reheater Drains (RD) system is used to illustrate such an example. Frequent failures of tank level controller lead to transients where the operation of shutting down RD pumps requires operators to manually isolate the quenching water and to close the main steam admission valves. Water in this system is at saturation temperature for the reheater steam side pressure, and any manual operation of the system is highly undesirable due to hazards of working with wet steam at approximately 758 kPa(g) pressure, preheated to 237 °C. Additionally, losses of inventory are highly undesirable as well and challenge other systems in the plant. In this paper, it is suggested that RD system can benefit from installation of an independent SIS system in order to address current challenges. This idea is being explored using IEC 61508 framework for “Functional safety of electrical/electronic/programmable electronic safety-related systems” to provide assurance that the SIS will offer the necessary risk reduction required to achieve required safety for the equipment.

  16. Determining a cost/effectiveness/safety tradeoff methodology for strategic nuclear warheads

    Energy Technology Data Exchange (ETDEWEB)

    Erickson, S.A. Jr.; Hall, C.H.

    1992-04-27

    Department of Energy national laboratories are charged with anticipating with a long leadtime which technologies for nuclear warheads should be developed. The Safe Warhead System Study was constituted to provide Lawrence Livermore National Laboratory management with information and suggestions for making such decisions for enhanced safety warheads. The Minuteman III replacement warheads were analyzed as a test case and that information was used to identify and describe the dominant issues, to develop a methodology and to make initial recommendations. The test case work resulted in several insights into how ongoing design and engineering interacts with the technology ranking and on how to cope with the ubiquitous uncertainties relating to our current ICBM force.

  17. 33 CFR 165.115 - Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts. 165.115 Section 165.115 Navigation and Navigable... Coast Guard District § 165.115 Safety and Security Zones; Pilgrim Nuclear Power Plant,...

  18. The development of regulatory expectations for computer-based safety systems for the UK nuclear programme

    Energy Technology Data Exchange (ETDEWEB)

    Hughes, P. J. [HM Nuclear Installations Inspectorate Marine Engineering Submarines Defence Nuclear Safety Regulator Serco Assurance Redgrave Court, Merton Road, Bootle L20 7HS (United Kingdom); Westwood, R.N; Mark, R. T. [FLEET HQ, Leach Building, Whale Island, Portsmouth, PO2 8BY (United Kingdom); Tapping, K. [Serco Assurance,Thomson House, Risley, Warrington, WA3 6GA (United Kingdom)

    2006-07-01

    The Nuclear Installations Inspectorate (NII) of the UK's Health and Safety Executive (HSE) has completed a review of their Safety Assessment Principles (SAPs) for Nuclear Installations recently. During the period of the SAPs review in 2004-2005 the designers of future UK naval reactor plant were optioneering the control and protection systems that might be implemented. Because there was insufficient regulatory guidance available in the naval sector to support this activity the Defence Nuclear Safety Regulator (DNSR) invited the NII to collaborate with the production of a guidance document that provides clarity of regulatory expectations for the production of safety cases for computer based safety systems. A key part of producing regulatory expectations was identifying the relevant extant standards and sector guidance that reflect good practice. The three principal sources of such good practice were: IAEA Safety Guide NS-G-1.1 (Software for Computer Based Systems Important to Safety in Nuclear Power Plants), European Commission consensus document (Common Position of European Nuclear Regulators for the Licensing of Safety Critical Software for Nuclear Reactors) and IEC nuclear sector standards such as IEC60880. A common understanding has been achieved between the NII and DNSR and regulatory guidance developed which will be used by both NII and DNSR in the assessment of computer-based safety systems and in the further development of more detailed joint technical assessment guidance for both regulatory organisations. (authors)

  19. SRTC criticality safety technical review: Nuclear Criticality Safety Evaluation 93-04 enriched uranium receipt

    Energy Technology Data Exchange (ETDEWEB)

    Rathbun, R.

    1993-10-13

    Review of NMP-NCS-930087, {open_quotes}Nuclear Criticality Safety Evaluation 93-04 Enriched Uranium Receipt (U), July 30, 1993, {close_quotes} was requested of SRTC (Savannah River Technology Center) Applied Physics Group. The NCSE is a criticality assessment to determine the mass limit for Engineered Low Level Trench (ELLT) waste uranium burial. The intent is to bury uranium in pits that would be separated by a specified amount of undisturbed soil. The scope of the technical review, documented in this report, consisted of (1) an independent check of the methods and models employed, (2) independent HRXN/KENO-V.a calculations of alternate configurations, (3) application of ANSI/ANS 8.1, and (4) verification of WSRC Nuclear Criticality Safety Manual procedures. The NCSE under review concludes that a 500 gram limit per burial position is acceptable to ensure the burial site remains in a critically safe configuration for all normal and single credible abnormal conditions. This reviewer agrees with that conclusion.

  20. Style, content and format guide for writing safety analysis documents. Volume 1, Safety analysis reports for DOE nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The purpose of Volume 1 of this 4-volume style guide is to furnish guidelines on writing and publishing Safety Analysis Reports (SARs) for DOE nuclear facilities at Sandia National Laboratories. The scope of Volume 1 encompasses not only the general guidelines for writing and publishing, but also the prescribed topics/appendices contents along with examples from typical SARs for DOE nuclear facilities.

  1. Nuclear Safety Technical Progress Journal, January--June 1995. Volume 36, No. 1

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1995-01-01

    This journal covers significant issues in the field of nuclear safety. Its primary scope is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  2. Second national report of Brazil for the nuclear safety convention - September 2001

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-09-01

    This National Report was prepared by a group composed of representatives of the various Brazilian organizations with responsibilities in the field of nuclear safety, aiming the fulfilling the Convention of Nuclear Energy obligations. The Report contains a description of the Brazilian policy and programme on the safety of nuclear installations, and an article by article description of the measures Brazil is undertaking in order to implement the obligations described in the Convention. The chapter 6 describes plans and future activities to further enhance the safety of nuclear installations in Brazil.

  3. Nuclear Safety. Technical Progress Journal, October--December 1991: Volume 32, No. 4

    Energy Technology Data Exchange (ETDEWEB)

    1991-01-01

    This document is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  4. Nuclear Safety. Technical Progress Journal, July--September 1992: Volume 33, No. 3

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-01-01

    This review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  5. Nuclear Safety. Technical Progress Journal, April--June 1993: Volume 34, No. 2

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1993-01-01

    This review journal that covers significant developments in the field of Nuclear Safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations are also treated.

  6. Outline of results of safety research (in nuclear fuel cycle field in fiscal year 1996)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    The safety research in Power Reactor and Nuclear Fuel Development Corporation in fiscal year 1996 has been carried out based on the basic plan of safety research (from fiscal year 1996 to 2000) which was decided in March, 1996. In this report, on nuclear fuel cycle field, namely all the subjects in the fields of nuclear fuel facilities, environmental radioactivity and waste disposal, and the subjects related to nuclear fuel facilities among the fields of aseismatic and probabilistic safety assessments, the results of research in fiscal year 1996, the first year of the 5-year project, are summarized together with the outline of the basic plan of safety research. The basic policy, objective and system for promotion of the safety research are described. The objectives of the safety research are the advancement of safety technology, the safety of facilities, stable operation techniques, the safety design and the evaluation techniques of next generation facilities, and the support of transferring nuclear fuel cycle to private businesses. The objects of the research are uranium enrichment, fuel fabrication and reprocessing, and waste treatment and storage. 52 investigation papers of the results of the safety research in nuclear fuel cycle field in fiscal year 1996 are collected in this report. (K.I.)

  7. Japan`s international cooperation programs on seismic safety of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Sanada, Akira [Agency of Natural Resources and Energy, Tokyo (Japan)

    1997-03-01

    MITI is promoting many international cooperation programs on nuclear safety area. The seismic safety of nuclear power plants (NPPs) is a one of most important cooperation areas. Experts from MITI and related organization join the multilateral cooperation programs carried out by international organization such as IAEA, OECD/NEA etc. MITI is also promoting bilateral cooperation programs such as information exchange meetings, training programs and seminars on nuclear safety with several countries. Concerning to the cooperation programs on seismic safety of NPPs such as information exchange and training, MITI shall continue and expand these programs. (J.P.N.)

  8. Organizational Culture for Safety, Security, and Safeguards in New Nuclear Power Countries

    Energy Technology Data Exchange (ETDEWEB)

    Kovacic, Donald N [ORNL

    2015-01-01

    This chapter will contain the following sections: Existing international norms and standards for developing the infrastructure to support new nuclear power programs The role of organizational culture and how it supports the safe, secure, and peaceful application of nuclear power Identifying effective and efficient strategies for implementing safety, security and safeguards in nuclear operations Challenges identified in the implementation of safety, security and safeguards Potential areas for future collaboration between countries in order to support nonproliferation culture

  9. Nuclear Safety Functions of ITER Gas Injection System Instrumentation and Control and the Concept Design

    Science.gov (United States)

    Yang, Yu; Maruyama, S.; Fossen, A.; Villers, F.; Kiss, G.; Zhang, Bo; Li, Bo; Jiang, Tao; Huang, Xiangmei

    2016-08-01

    The ITER Gas Injection System (GIS) plays an important role on fueling, wall conditioning and distribution for plasma operation. Besides that, to support the safety function of ITER, GIS needs to implement three nuclear safety Instrumentation and Control (I&C) functions. In this paper, these three functions are introduced with the emphasis on their latest safety classifications. The nuclear I&C design concept is briefly discussed at the end.

  10. Licensee responsibility for nuclear power plant safety; Verantwortung der Genehmigungsinhaber fuer die Sicherheit der Kernkraftwerke

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, Horst

    2010-02-15

    Simple sentences easy to grasp are desirable in regulations and bans. However, in a legal system, their meaning must be unambiguous. Article 6, Paragraph 1 of the EURATOM Directive on a community framework for the nuclear safety of nuclear facilities of June 2009 states that 'responsibility for the nuclear safety of a nuclear facility is incumbent primarily on the licensee.' The draft 'Safety Criteria for Nuclear Power Plants, Revision D, April 2009' of the German Federal Ministry for the Environment, Nature Conservation, and Nuclear Safety (BMU) (A Module 1, 'Safety Criteria for Nuclear Power Plants: Basic Safety Criteria' / '0 Principles' Paragraph 2) reads: 'Responsibility for ensuring safety rests with the licensee. He shall give priority to compliance with the safety goal over the achievement of other operational objectives.' In addition, the existing rules and regulations, whose rank is equivalent to that of international regulations, assign priority to the safety goal to be pursued by the licensee over all other objectives of the company. The operator's responsibility for nuclear safety can be required and achieved only on the basis of permits granted, which must meet legal requirements. The operator's proximity to plant operation is the reason for his 'primary responsibility.' Consequently, verbatim incorporation of Article 6, Paragraph 1 of the EURATOM Directive would only be a superscript added to existing obligations of the operator - inclusive of a safety culture designed as an incentive to further 'the spirit of safety-related actions' - without any new legal contents and consequences. In the reasons of the regulation, this would have to be clarified in addition to the cryptic wording of 'responsibility.. primarily,' at the same time expressing that operators and authorities work together in a spirit of openness and trust. (orig.)

  11. Extreme meteorological events and nuclear facilities safety; Fenomenos meteorologicos extremos e a seguranca das instalacoes nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Patricia Moco Princisval

    2006-07-01

    An External Event is an event that originates outside the site and whose effects on the Nuclear Power Plants (NPP) should be considered. Such events could be of natural or human induced origin and should be identified and selected for design purposes during the site evaluation process. This work shows that the subtropics and mid latitudes of South America east of the Andes Mountain Range have been recognized as prone to severe convective weather. In Brazil, the events of tornadoes are becoming frequent; however there is no institutionalized procedure for a systematic documentation of severe weather. The information is done only for some scientists and by the newspapers. Like strong wind can affect the structural integrity of buildings or the pressure differential can affect the ventilation system, our concern is the safety of NPP and for this purpose the recommendations of International Atomic Energy Agency, Nuclear Regulatory Commission and Comissao Nacional de Energia Nuclear are showed and also a data base of tornadoes in Brazil is done. (author)

  12. Japan's regulatory and safety issues regarding nuclear materials transport

    Energy Technology Data Exchange (ETDEWEB)

    Saito, T. [Nuclear and Industrial Safety Agency, Ministry of Economy, Trade and Industry, Government of Japan, Tokyo (Japan); Yamanaka, T. [Japan Nuclear Energy Safety Organization, Government of Japan, Tokyo (Japan)

    2004-07-01

    This paper focuses on the regulatory and safety issues on nuclear materials transport which the Government of Japan (GOJ) faces and needs to well handle. Background information about the status of nuclear power plants (NPP) and nuclear fuel cycle (NFC) facilities in Japan will promote a better understanding of what this paper addresses.

  13. 76 FR 56242 - Duke Energy Carolinas, LLC; Southern Nuclear Operating Company; Establishment of Atomic Safety...

    Science.gov (United States)

    2011-09-12

    ... Energy Carolinas, LLC; Southern Nuclear Operating Company; Establishment of Atomic Safety and Licensing...: Duke Energy Carolinas, LLC, (William States Lee III Nuclear Station, Units 1 and 2), Docket Nos. 52-018... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY...

  14. A study of thermal, structural and shielding safety analysis for dry storage of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Shin, S. H. [Kyungpook Nationl Univ., Daegu (Korea, Republic of)

    1997-03-15

    As a replaced method for MRS, the dry storage has been intensively developed by the advanced countries of nuclear power technology. Currently, the domestic technology for the dry storage is also under development. In the present study, the developed technical standards for USNRC and its operation are summarized. Futhermore, the SAR for VECTRA's NUHOMES satisfied with DOE and NRC's requirements is inversely analyzed and combined with both USNRC's regulatory guide and LLNL's SARS. In the safety analysis of a dry storage, the principal design criteria which identifies the structural and mechanical safety criteria is investigated. Based on the design criteria, hypothetical accident analysis as well as off-normal operation analysis are investigated.

  15. Nuclear electromagnetic charge and current operators in Chiral EFT

    Energy Technology Data Exchange (ETDEWEB)

    Girlanda, Luca [Università del Salento; Marcucci, Laura Elisa [Univ. Pisa; Pastore, Saori [Department of Physics and Astronomy, University of South Carolina, Columbia, SC; Piarulli, Maria [Department of Physics, Old Dominion University, Norfolk, VA; Schiavilla, Rocco [Old Dominion U., JLAB; Viviani, Michele

    2013-08-01

    We describe our method for deriving the nuclear electromagnetic charge and current operators in chiral perturbation theory, based on time-ordered perturbation theory. We then discuss possible strategies for fixing the relevant low-energy constants, from the magnetic moments of the deuteron and of the trinucleons, and from the radiative np capture cross sections, and identify a scheme which, partly relying on {Delta} resonance saturation, leads to a reasonable pattern of convergence of the chiral expansion.

  16. Current Status of Helium-3 Alternative Technologies for Nuclear Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Henzlova, Daniela [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kouzes, R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); McElroy, R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Peerani, P. [European Commission, Ispra (Italy). Joint Research Centre; Aspinall, M. [Hybrid Instruments Ltd., Birmingham (United Kingdom); Baird, K. [Intl Atomic Energy Agency (IAEA), Vienna (Austria); Bakel, A. [National Nuclear Security Administration (NNSA), Washington, DC (United States); Borella, M. [SCK.CEN, Mol (Belgium); Bourne, M. [Univ. of Michigan, Ann Arbor, MI (United States); Bourva, L. [Canberra Ltd., Oxford (United Kingdom); Cave, F. [Hybrid Instruments Ltd., Birmingham (United Kingdom); Chandra, R. [Arktis Radiation Detectors Ltd., Zurich (Sweden); Chernikova, D. [Chalmers Univ. of Technology (Sweden); Croft, S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Dermody, G. [Symetrica Inc., Maynard, MA (United States); Dougan, A. [National Nuclear Security Administration (NNSA), Washington, DC (United States); Ely, J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Fanchini, E. [Istituto Nazionale di Fisica Nucleare (INFN), Milano (Italy); Finocchiaro, P. [Istituto Nazionale di Fisica Nucleare (INFN), Milano (Italy); Gavron, Victor [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kureta, M. [Japan Atomic Energy Agency (JAEA), Tokai (Japan); Ianakiev, Kiril Dimitrov [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Ishiyama, K. [Japan Atomic Energy Agency (JAEA), Tokai (Japan); Lee, T. [Intl Atomic Energy Agency (IAEA), Vienna (Austria); Martin, Ch. [Symetrica Inc., Maynard, MA (United States); McKinny, K. [GE Reuter-Stokes, Twinsburg, OH (United States); Menlove, Howard Olsen [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Orton, Ch. [National Nuclear Security Administration (NNSA), Washington, DC (United States); Pappalardo, A. [Istituto Nazionale di Fisica Nucleare (INFN), Milano (Italy); Pedersen, B. [European Commission, Ispra (Italy). Joint Research Centre; Peranteau, D. [National Nuclear Security Administration (NNSA), Washington, DC (United States); Plenteda, R. [Intl Atomic Energy Agency (IAEA), Vienna (Austria); Pozzi, S. [Univ. of Michigan, Ann Arbor, MI (United States); Schear, M. [Symetrica Inc., Maynard, MA (United States); Seya, M. [Japan Atomic Energy Agency (JAEA), Tokai (Japan); Siciliano, E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Stave, S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sun, L. [Proportional Technologies Inc., Houston, TX (United States); Swinhoe, Martyn Thomas [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Tagziria, H. [European Commission, Ispra (Italy). Joint Research Centre; Vaccaro, S. [DG Energy (Luxembourg); Takamine, J. [Japan Atomic Energy Agency (JAEA), Tokai (Japan); Weber, A. -L. [Inst. for Radiological Protection and Nuclear Safety (IRSN), Fontenay-aux-Roses (France); Yamaguchi, T. [Japan Atomic Energy Agency (JAEA), Tokai (Japan); Zhu, H. [National Nuclear Security Administration (NNSA), Washington, DC (United States)

    2015-12-01

    International safeguards inspectorates (e.g., International Atomic Energy Agency {IAEA}, or Euratom) rely heavily on neutron assay techniques, and in particular, on coincidence counters for the verification of declared nuclear materials under safeguards and for monitoring purposes. While 3He was readily available, the reliability, safety, ease of use, gamma-ray insensitivity, and high intrinsic thermal neutron detection efficiency of 3He-based detectors obviated the need for alternative detector technologies. However, the recent decline of the 3He gas supply has triggered international efforts to develop and field neutron detectors that make use of alternative materials. In response to this global effort, the U.S. Department of Energy’s (DOE) National Nuclear Security Administration (NNSA) and Euratom launched a joint effort aimed at bringing together international experts, technology users and developers in the field of nuclear safeguards to discuss and evaluate the proposed 3He alternative materials and technologies. The effort involved a series of two workshops focused on detailed overviews and viability assessments of various 3He alternative technologies for use in nuclear safeguards applications. The key objective was to provide a platform for collaborative discussions and technical presentations organized in a compact, workshop-like format to stimulate interactions among the participants. The meetings culminated in a benchmark exercise providing a unique opportunity for the first inter-comparison of several available alternative technologies. This report provides an overview of the alternative technology efforts presented during the two workshops along with a summary of the benchmarking activities and results. The workshop recommendations and key consensus observations are discussed in the report, and used to outline a proposed path forward and future needs foreseeable in the area of 3

  17. Toward a common nuclear safety culture. From knowledge creation to competence building in Euratom programs

    Energy Technology Data Exchange (ETDEWEB)

    Goethem, Georges van [EC DG Research J2 / Euratom (Fission), Brussels (Belgium). Innovation in Nuclear Systems, and Education and Training

    2010-11-15

    One of the main goals of the Euratom research and training programs is to contribute to the sustainability of nuclear energy by providing resources, in particular, for research and innovation in Generations II, IIII and IV (knowledge creation). Euratom training programs contribute most notably to competence building while facilitating the mutual recognition of experts and thereby continuously improving the nuclear safety culture. The Sustainable Nuclear Energy Technology Platform (SNE-TP), composed of all stakeholders of nuclear fission and radiation protection (over 75 organizations), is a driving force therein. The emphasis in this paper is on nuclear competence building under the current 7-th Euratom Framework Programme (2007 - 2013). The employers (in particular, the nuclear industry and the technical safety organisations) are naturally involved in this process. According to the IAEA definition, competence means the ability to apply knowledge, skills and attitudes so as to perform a job in an effective and efficient manner and to an established standard (S.S.S. No. RS-G-1.4 / 2001). Knowledge is usually created in higher education institutions (e.g., universities) and in (private and public) research organizations. Skills and attitudes are usually the result of specific training and on-the-job experience throughout professional life. Euratom training activities are traditionally addressed to scientists and experts with higher education. Special attention is devoted to the continuous improvement of their competencies through borderless mobility and lifelong learning in synergy with the main stakeholders. The Euratom training strategy is based on 3 objectives: 1. Analysis of the needs of society and industry with regard to a common nuclear safety culture. This issue raises important questions, for examples: What should be added to existing training schemes? How could Continuous Professional Development (CPD) be improved? Is mobility and mutual recognition of

  18. Current safety standards in infant nutrition--a European perspective.

    Science.gov (United States)

    Hernell, Olle

    2012-01-01

    Foods intended specifically for infants and young children are considered under European community law and are defined in specific commission directives. In principal, these directives conclude that such foods must be safe, have a special composition, be distinguishable from normal foods, be suitable for fulfilling particular nutritional requirements, and should, when marketed, indicate such suitability. Since infant formulas are intended as the sole source of nutrition during the first months of life, their nutritional adequacy and safety are particularly strictly regulated. The Scientific Committee on Food report from 2003, on which the current commission directive is based, makes clear recommendations on how benefits, suitability, and safety of modifications beyond established standards should be documented and evaluated. These principles resulted in part from a workshop on characterization of infant food modifications in the EU and two position papers by the European Society for Pediatric Gastroenterology, Hepatology and Nutrition (ESPGHAN). These papers are reviewed below.

  19. LMFBR safety. 1. Review of current issues and bibliography of literature, 1960--1969

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.; Keilholtz, G.W.

    1976-08-16

    This report discusses the current status of liquid-metal fast breeder (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1960 through 1969. The bibliography consists of 1560 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness.

  20. LMFBR safety. 4. Review of current issues and bibliography of literature (1974--1975)

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.; Keilholtz, G.W.

    1977-03-21

    This report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1974 through 1975. The bibliography consists of approximately 1554 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness.

  1. LMFBR safety. 2. Review of current issues and bibliography of literature, 1970--1972

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.; Keilholtz, G.W.

    1976-11-22

    This report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1970 through 1972. The bibliography consists of approximately 1620 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness.

  2. LMFBR safety. 3. Review of current issues and bibliography of literature (1972--1974)

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.; Keilholtz, G.W.

    1977-02-24

    The report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1972 through 1974. The bibliography consists of approximately 1380 abstracts covering research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included.

  3. Review of criteria for nuclear criticality safety control in transportation

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, J. T.; Smith, D. R.

    1978-01-01

    Basic elements in the review of criteria for nuclear criticality safety in transportation are the magnitudes of reactivity changes that may occur to a shipment of packages and those inherent in the regulatory procedure of assessment. The generic representation of criticality of reflected arrays of uncontained fissionable materials is used as a basis for comparison of packaged fissionable materials. The reactivities associated with array changes and perturbations representative of credible conditions that may occur in storage or transportation are summarized for air-spaced units of fissionable materials. Calculations of packaged fissionable material determined reactivities associated with similar changes to arrays of packages. Typical thermal insulating materials being studied are Celotex, wood, Foamglas, and a bonded vermiculite. The effect on the array neutron multiplication of these, with and without steel as an inner and outer container material, is examined. The present stage of the study has produced results illustrating the variable margin of subcriticality manifested by the criteria. Depending upon the packaging, mass loading and array reflector condition, the margin of subcriticality can be of the order of 1% in k/sub eff/.

  4. Updating Human Factors Engineering Guidelines for Conducting Safety Reviews of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    O, J.M.; Higgins, J.; Stephen Fleger - NRC

    2011-09-19

    The U.S. Nuclear Regulatory Commission (NRC) reviews the human factors engineering (HFE) programs of applicants for nuclear power plant construction permits, operating licenses, standard design certifications, and combined operating licenses. The purpose of these safety reviews is to help ensure that personnel performance and reliability are appropriately supported. Detailed design review procedures and guidance for the evaluations is provided in three key documents: the Standard Review Plan (NUREG-0800), the HFE Program Review Model (NUREG-0711), and the Human-System Interface Design Review Guidelines (NUREG-0700). These documents were last revised in 2007, 2004 and 2002, respectively. The NRC is committed to the periodic update and improvement of the guidance to ensure that it remains a state-of-the-art design evaluation tool. To this end, the NRC is updating its guidance to stay current with recent research on human performance, advances in HFE methods and tools, and new technology being employed in plant and control room design. This paper describes the role of HFE guidelines in the safety review process and the content of the key HFE guidelines used. Then we will present the methodology used to develop HFE guidance and update these documents, and describe the current status of the update program.

  5. Australian radiation protection and nuclear safety (consequential amendments) Bill 1998. Explanatory memorandum

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

    The purpose of this Bill is to make consequential changes to the Australian Nuclear Science and Technology Organisation Act 1987 (the ANSTO Act) and to provide for transitional arrangements to cover the operation of controlled facilities and the handling of radiation sources while applications for licences to cover these facilities and activities are being made under the proposed Australian Radiation Protection and Nuclear Safety Act 1998 (the ARPANS Act) For this purpose, the Bill: (a) repeals Parts VI and VII A of the ANSTO Act under which, respectively, the Safety Review Committee and the Nuclear Safety Bureau are established, as the functions of the Committee and Bureau will be transferred to the CEO of the Australian Radiation Protection and Nuclear Safety Agency, established under the ARPANS Act; (b) makes transitional arrangements for the transfer of the assets and liabilities of the Nuclear Safety Bureau to the Commonwealth, and confers on the CEO of ARPANSA the powers of the Director of the Nuclear Safety Bureau in relation to the Australian Nuclear Science and Technology Organisation during the transitional period before the offenses provisions commence to operate under the ARPANS Act; (c) repeals the Environment Protection (Nuclear Codes) Act 1978. That Act provides for the development and endorsement of Codes of Practice which will be undertaken under the auspices of ARPANSA; (d) provides that Commonwealth entities have a transition period of 6 months after the ARPANS Act commences to apply for a licence to authorize specified activities under that Act

  6. On the fundamentals of nuclear reactor safety assessment. Inherent threats and their implications

    Energy Technology Data Exchange (ETDEWEB)

    Hyvaerinen, J. [Finnish Centre for Radiation and Nuclear Safety, Helsinki (Finland). Nuclear Safety Dept.

    1996-12-01

    The thesis addresses some fundamental questions related to implementation and assessment of nuclear safety. The safety principles and assessment methods are described, followed by descriptions of selected novel technical challenges to nuclear safety. The novel challenges encompass a wide variety of technical issues, thus providing insights on the limitations of conventional safety assessment methods. Study of the limitations suggests means to improve nuclear reactor design criteria and safety assessment practices. The novel safety challenges discussed are (1) inherent boron dilution in PWRs, (2) metallic insulation performance with respect to total loss of emergency cooling systems in a loss-of-coolant accident, and (3) horizontal steam generator heat transfer performance at natural circulation conditions. (50 refs.).

  7. Development of a Novel Nuclear Safety Culture Evaluation Method for an Operating Team Using Probabilistic Safety Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Han, Sangmin; Lee, Seung Min; Seong, Poong Hyun [KAIST, Daejeon (Korea, Republic of)

    2015-05-15

    IAEA defined safety culture as follows: 'Safety Culture is that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance'. Also, celebrated behavioral scientist, Cooper, defined safety culture as,'safety culture is that observable degree of effort by which all organizational members direct their attention and actions toward improving safety on a daily basis' with his internal psychological, situational, and behavioral context model. With these various definitions and criteria of safety culture, several safety culture assessment methods have been developed to improve and manage safety culture. To develop a new quantitative safety culture evaluation method for an operating team, we unified and redefined safety culture assessment items. Then we modeled a new safety culture evaluation by adopting level 1 PSA concept. Finally, we suggested the criteria to obtain nominal success probabilities of assessment items by using 'operational definition'. To validate the suggested evaluation method, we analyzed the collected audio-visual recording data collected from a full scope main control room simulator of a NPP in Korea.

  8. Electric Power quality Analysis in research reactor: Impacts on nuclear safety assessment and electrical distribution reliability

    Energy Technology Data Exchange (ETDEWEB)

    Touati, Said; Chennai, Salim; Souli, Aissa [Nuclear Research Centre of Birine, Ain Oussera, Djelfa Province (Algeria)

    2015-07-01

    The increased requirements on supervision, control, and performance in modern power systems make power quality monitoring a common practise for utilities. Large databases are created and automatic processing of the data is required for fast and effective use of the available information. Aim of the work presented in this paper is the development of tools for analysis of monitoring power quality data and in particular measurements of voltage and currents in various level of electrical power distribution. The study is extended to evaluate the reliability of the electrical system in nuclear plant. Power Quality is a measure of how well a system supports reliable operation of its loads. A power disturbance or event can involve voltage, current, or frequency. Power disturbances can originate in consumer power systems, consumer loads, or the utility. The effect of power quality problems is the loss power supply leading to severe damage to equipments. So, we try to track and improve system reliability. The assessment can be focused on the study of impact of short circuits on the system, harmonics distortion, power factor improvement and effects of transient disturbances on the Electrical System during motor starting and power system fault conditions. We focus also on the review of the Electrical System design against the Nuclear Directorate Safety Assessment principles, including those extended during the last Fukushima nuclear accident. The simplified configuration of the required system can be extended from this simple scheme. To achieve these studies, we have used a demo ETAP power station software for several simulations. (authors)

  9. Handbook on criticality. Vol. 1. Criticality and nuclear safety; Handbuch zur Kritikalitaet. Bd. 1. Kritikalitaet und nukleare Sicherheit

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-04-15

    This handbook was prepared primarily with the aim to provide information to experts in industry, authorities or research facilities engaged in criticality-safety-related problems that will allow an adequate and rapid assessment of criticality safety issues already in the planning and preparation of nuclear facilities. However, it is not the intention of the authors of the handbook to offer ready solutions to complex problems of nuclear safety. Such questions have to remain subject to an in-depth analysis and assessment to be carried out by dedicated criticality safety experts. Compared with the previous edition dated December 1998, this handbook has been further revised and supplemented. The proven basic structure of the handbook remains unchanged. The handbook follows in some ways similar criticality handbooks or instructions published in the USA, UK, France, Japan and the former Soviet Union. The expedient use of the information given in this handbook requires a fundamental understanding of criticality and the terminology of nuclear safety. In Vol. 1, ''Criticality and Nuclear Safety'', therefore, first the most important terms and fundamentals are introduced and explained. Subsequently, experimental techniques and calculation methods for evaluating criticality problems are presented. The following chapters of Vol. 1 deal i. a. with the effect of neutron reflectors and absorbers, neutron interaction, measuring methods for criticality, and organisational safety measures and provide an overview of criticality-relevant operational experience and of criticality accidents and their potential hazardous impact. Vol. 2 parts 1 and 2 finally compile criticality parameters in graphical and tabular form. The individual graph sheets are provided with an initially explained set of identifiers, to allow the quick finding of the information of current interest. Part 1 includes criticality parameters for systems with {sup 235}U as fissile material, while part

  10. Views on safety culture at Swedish and Finnish nuclear power plants; Syn paa saekerhetskultur vid svenska och finska kaernkraftverk

    Energy Technology Data Exchange (ETDEWEB)

    Hammar, L. [ES-konsulent, (Sweden); Wahlstroem, B.; Kettunen, J. [VTT Automation (Finland)

    2000-02-01

    The report presents the results of interviews about safety culture at Swedish and Finnish nuclear power plants. The aim is to promote the safety work and increase the debate about safety in nuclear power plants, by showing that the safety culture is an important safety factor. The interviews point out different threats, which may become real. It is therefor necessary that the safety aspects get support from of the society and the power plant owners. (EHS)

  11. A Computer Program for Assessing Nuclear Safety Culture Impact

    Energy Technology Data Exchange (ETDEWEB)

    Han, Kiyoon; Jae, Moosung [Hanyang Univ., Seoul (Korea, Republic of)

    2014-10-15

    Through several accidents of NPP including the Fukushima Daiichi in 2011 and Chernobyl accidents in 1986, a lack of safety culture was pointed out as one of the root cause of these accidents. Due to its latent influences on safety performance, safety culture has become an important issue in safety researches. Most of the researches describe how to evaluate the state of the safety culture of the organization. However, they did not include a possibility that the accident occurs due to the lack of safety culture. Because of that, a methodology for evaluating the impact of the safety culture on NPP's safety is required. In this study, the methodology for assessing safety culture impact is suggested and a computer program is developed for its application. SCII model which is the new methodology for assessing safety culture impact quantitatively by using PSA model. The computer program is developed for its application. This program visualizes the SCIs and the SCIIs. It might contribute to comparing the level of the safety culture among NPPs as well as improving the management safety of NPP.

  12. Sensitivity analysis of parameters important to nuclear criticality safety of Castor X/28F spent nuclear fuel cask

    Energy Technology Data Exchange (ETDEWEB)

    Leotlela, Mosebetsi J. [Witwatersrand Univ., Johannesburg (South Africa). School of Physics; Koeberg Operating Unit, Johannesburg (South Africa). Regulations and Licensing; Malgas, Isaac [Koeberg Nuclear Power Station, Duinefontein (South Africa). Nuclear Engineering Analysis; Taviv, Eugene [ASARA consultants (PTY) LTD, Johannesburg (South Africa)

    2015-11-15

    In nuclear criticality safety analysis it is essential to ascertain how various components of the nuclear system will perform under certain conditions they may be subjected to, particularly if the components of the system are likely to be affected by environmental factors such as temperature, radiation or material composition. It is therefore prudent that a sensitivity analysis is performed to determine and quantify the response of the output to variation in any of the input parameters. In a fissile system, the output parameter of importance is the k{sub eff}. Therefore, in attempting to prevent reactivity-induced accidents, it is important for the criticality safety analyst to have a quantified degree of response for the neutron multiplication factor to perturbation in a given input parameter. This article will present the results of the perturbation of the parameters that are important to nuclear criticality safety analysis and their respective correlation equations for deriving the sensitivity coefficients.

  13. Nuclear energy with inherent safety: Change of outdated paradigm, criteria

    Science.gov (United States)

    Adamov, E. O.; Orlov, V. V.; Rachkov, V. I.; Slessarev, I. S.; Khomyakov, Yu. S.

    2015-12-01

    Modern nuclear power technology still has significant sources of risk, and, weak links, such as, a threat of severe accidents with catastrophic unpredictable consequences and damage to the population, proliferation of nuclear weapon-usable materials, risks of long-term storage of toxic radioactive waste, risks of loss of major investments in nuclear facilities and their construction, lack of fuel resources for the ambitious role of nuclear power in the competitive balance of energy. Each of these risks is important and almost independent, though the elimination of some of them does not significantly alter the overall assessment of nuclear power.

  14. Safety culture in the Finnish and Swedish nuclear industries - history and present

    Energy Technology Data Exchange (ETDEWEB)

    Reiman, T.; Pietikaeinen, E. (Technical Research Centre of Finland, VTT (Finland)); Kahlbom, U. (RiskPilot AB (Sweden)); Rollenhagen, C. (Royal Institute of Technology (KTH) (Sweden))

    2010-03-15

    The report presents results from an interview study that examined the characteristics of the Nordic nuclear branch safety culture. The study also tested the theoretical model of safety culture developed by the authors. The interview data was collected in Sweden (n = 14) and Finland (n = 16). Interviewees represented the major actors in the nuclear field (regulators, power companies, expert organizations, waste management organizations). The study gave insight into the nature of safety culture in the nuclear industry. It provided an overview on the variety of factors that people in the industry consider important for safety. The respondents rather coherently saw such psychological states as motivation, mindfulness, sense of control, understanding of hazards and safety and sense of responsibility as important for nuclear safety. Some of the respondents described a certain Nordic orientation towards safety. One characteristic was a sense of personal responsibility for safety. However, there was no clear agreement on the existence of a shared Nordic nuclear safety culture. Sweden and Finland were seen different for example in the way the co-operation between plants and nuclear safety authorities was arranged and re-search activities organized. There were also perceived differences in the way everyday activities like decision making were carried out in the organizations. There are multiple explanations for the differences. The industry in Sweden has been driven by the strong supplier. In Finland the regulator's role in shaping the culture has been more active. Other factors creating differences are e.g. national culture and company culture and the type of the power plant. Co-operation between Nordic nuclear power organizations was viewed valuable yet challenging from safety point of view. The report concludes that a good safety culture requires a deep and wide under-standing of nuclear safety including the various accident mechanisms of the power plants as well as

  15. Evaluation of natural phenomena hazards as part of safety assessments for nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kot, C.A.; Hsieh, B.J.; Srinivasan, M.G.; Shin, Y.W.

    1995-02-01

    The continued operation of existing US Department of Energy (DOE) nuclear facilities and laboratories requires a safety reassessment based on current criteria and guidelines. This also includes evaluations for the effects of Natural Phenomena Hazards (NPH), for which these facilities may not have been designed. The NPH evaluations follow the requirements of DOE Order 5480.28, Natural Phenomena Hazards Mitigation (1993) which establishes NPH Performance Categories (PCs) for DOE facilities and associated target probabilistic performance goals. These goals are expressed as the mean annual probability of exceedance of acceptable behavior for structures, systems and components (SSCs) subjected to NPH effects. The assignment of an NPH Performance Category is based on the overall hazard categorization (low, moderate, high) of a facility and on the function of an SSC under evaluation (DOE-STD-1021, 1992). Detailed guidance for the NPH analysis and evaluation criteria are also provided (DOE-STD-1020, 1994). These analyses can be very resource intensive, and may not be necessary for the evaluation of all SSCs in existing facilities, in particular for low hazard category facilities. An approach relying heavily on screening inspections, engineering judgment and use of NPH experience data (S. J. Eder et al., 1993), can minimize the analytical effort, give reasonable estimates of the NPH susceptibilities, and yield adequate information for an overall safety evaluation of the facility. In the following sections this approach is described in more detail and is illustrated by an application to a nuclear laboratory complex.

  16. Defense Nuclear Facilities Safety Board: Improvements Needed to Strengthen Internal Control and Promote Transparency

    Science.gov (United States)

    2015-01-01

    includes guidance. DNFSB refers to guidance as “work practices” and are not mandatory . Page 15 GAO-15-181 Nuclear Safety Board Technical...Federal Programs Congressional Relations Public Affairs Please Print on Recycled Paper.

  17. 78 FR 4477 - Review of Safety Analysis Reports for Nuclear Power Plants, Introduction

    Science.gov (United States)

    2013-01-22

    ... subsection to NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power... incorporate the final approved guidance into the next revision of NUREG 0800. Dated at Rockville,...

  18. Radiation and Nuclear Safety Authority (STUK) - History 1958-2008; Saeteilyturvakeskuksen historia 1958-2008

    Energy Technology Data Exchange (ETDEWEB)

    Hoffman, K.

    2008-07-01

    The publication is the 50th anniversary book of the Radiation and Nuclear Safety Authority (STUK). The organisation was founded in 1958 by the name Saeteilyfysiikan laitos (The Institute of Radiation Physics). The first duties were to inspect x-ray machines and machines used for radiation therapy in hospitals. The activities were started by six persons but were quickly widened and in the end of 1970's the institute employed more than 100 experts, who supervised nuclear power plants, radiation devices, radioactivity in the environment, and the radiation safety of miners. The present name Saeteilyturvakeskus - the Radiation and Nuclear Safety Authority (STUK) was given in 1984. Today STUK is the Finnish national regulatory authority in radiation and nuclear safety fields, research centre and organisation providing radiation related services. STUK employs about 350 experts

  19. Nuclear nonproliferation and safety: Challenges facing the International Atomic Energy Agency

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-01

    The Chairman of the Senate Committee on Govermental Affairs asked the United States General Accounting Office (GAO) to review the safeguards and nuclear power plant safety programs of the International Atomic Energy Agency (IAEA). This report examines (1) the effectiveness of IAEA`s safeguards program and the adequacy of program funding, (2) the management of U.S. technical assistance to the IAEA`s safeguards program, and (3) the effectiveness of IAEA`s program for advising United Nations (UN) member states about nuclear power plant safety and the adequacy of program funding. Under its statute and the Treaty on the Non-Proliferation of Nuclear Weapons, IAEA is mandated to administer safeguards to detect diversions of significant quantities of nuclear material from peaceful uses. Because of limits on budget growth and unpaid contributions, IAEA has had difficulty funding the safeguards program. IAEA also conducts inspections of facilities or locations containing declared nuclear material, and manages a program for reviewing the operational safety of designated nuclear power plants. The U.S. technical assistance program for IAEA safeguards, overseen by an interagency coordinating committee, has enhanced the agency`s inspection capabilities, however, some weaknesses still exist. Despite financial limitations, IAEA is meeting its basic safety advisory responsibilities for advising UN member states on nuclear safety and providing requested safety services. However, IAEA`s program for reviewing the operational safety of nuclear power plants has not been fully effective because the program is voluntary and UN member states have not requested IAEA`s review of all nuclear reactors with serious problems. GAO believes that IAEA should have more discretion in selecting reactors for review.

  20. Current intervention strategies for the microbial safety of sprouts.

    Science.gov (United States)

    Sikin, Adi Md; Zoellner, Claire; Rizvi, Syed S H

    2013-12-01

    Sprouts have gained popularity worldwide due to their nutritional values and health benefits. The fact that their consumption has been associated with numerous outbreaks of foodborne illness threatens the $250 million market that this industry has established in the United States. Therefore, sprout manufacturers have utilized the U.S. Food and Drug Administration recommended application of 20,000 ppm of calcium hypochlorite solution to seeds before germination as a preventative method. Concentrations of up to 200 ppm of chlorine wash are also commonly used on sprouts. However, chlorine-based treatment achieves on average only 1- to 3-log reductions in bacteria and is associated with negative health and environmental issues. The search for alternative strategies has been widespread, involving chemical, biological, physical, and hurdle processes that can achieve up to 7-log reductions in bacteria in some cases. The compilation here of the current scientific data related to these techniques is used to compare their efficacy for ensuring the microbial safety of sprouts and their practicality for commercial producers. Of specific importance for alternative seed and sprout treatments is maintaining the industry-accepted germination rate of 95% and the sensorial attributes of the final product. This review provides an evaluation of suggested decontamination technologies for seeds and sprouts before, during, and after germination and concludes that thermal inactivation of seeds and irradiation of sprouts are the most practical stand-alone microbial safety interventions for sprout production.

  1. Safety case for the disposal of spent nuclear fuel at Olkiluoto - Synthesis 2012

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-12-15

    TURVA-2012 is Posiva's safety case in support of the Preliminary Safety Analysis Report (PSAR 2012) and application for a construction licence for a spent nuclear fuel repository. Consistent with the Government Decisions-in- Principle, this foresees a repository developed in bedrock at the Olkiluoto site according to the KBS-3 method, designed to accept spent nuclear fuel from the lifetime operations of the Olkiluoto and Loviisa reactors. Synthesis 2012 presents a synthesis of Posiva Oy's Safety Case 'TURVA-2012' portfolio. It summarises the design basis for the repository at the Olkiluoto site, the assessment methodology and key results of performance and safety assessments. It brings together all the lines of argument for safety, evaluation of compliance with the regulatory requirements, and statement of confidence in long-term safety and Posiva's safety analyses. The TURVA-2012 safety case demonstrates that the proposed repository design provides a safe solution for the disposal of spent nuclear fuel, and that the performance and safety assessments are fully consistent with all the legal and regulatory requirements related to long-term safety as set out in Government Decree 736/2008 and in guidance from the nuclear regulator - the STUK. Moreover, Posiva considers that the level of confidence in the demonstration of safety is appropriate and sufficient to submit the construction licence application to the authorities. The assessment of long-term safety includes uncertainties, but these do not affect the basic conclusions on the long-term safety of the repository. (orig.)

  2. Current Status of Obstetric Anaesthesia: Improving Satisfaction and Safety

    Directory of Open Access Journals (Sweden)

    J Sudharma Ranasinghe

    2009-01-01

    Full Text Available The Centers for Disease Control and Prevention (CDC reported in 2003 that although the maternal mortal-ity rate has decreased by 99% since 1900, there has been no further decrease in the last two decades [1] . A more recent report indicates a rate of 11.8 per 100,000 live births [2] , although anaesthesia-related maternal mortality and morbidity has considerably decreased over the lastfew decades. Despite the growing complexity of problems and increasing challenges such as pre-existing maternal disease, obesity, and the increasing age of pregnant mothers, anaesthesia related maternal mortality is extremely rare in the developed world. The current safety has been achievedthrough changes in training, service, technical advances and multidisciplinary approach to care. The rates of general anaesthesia for cesarean delivery have decreased and neuraxial anaesthetics have become the most commonly used techniques. Neuraxial techniques are largely safe and effective, but potential complications, though rare, can be severe.

  3. Report transparency and nuclear safety 2007 - CISBIO; Rapport transparence et securite nucleaire 2007 - CISBIO

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This report presents the activities of CISBIO, nuclear base installation, for the year 2007. CISBIO realizes at Saclay most of the radiopharmaceuticals and drugs distributed in France for the nuclear medicine. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. (A.L.B.)

  4. Criticality safety and sensitivity analyses of PWR spent nuclear fuel repository facilities

    NARCIS (Netherlands)

    Maucec, M; Glumac, B

    2005-01-01

    Monte Carlo criticality safety and sensitivity calculations of pressurized water reactor (PWR) spent nuclear fuel repository facilities for the Slovenian nuclear power plant Krsko are presented. The MCNP4C code was deployed to model and assess the neutron multiplication parameters of pool-based stor

  5. Criticality safety and sensitivity analyses of PWR spent nuclear fuel repository facilities

    NARCIS (Netherlands)

    Maucec, M; Glumac, B

    2005-01-01

    Monte Carlo criticality safety and sensitivity calculations of pressurized water reactor (PWR) spent nuclear fuel repository facilities for the Slovenian nuclear power plant Krsko are presented. The MCNP4C code was deployed to model and assess the neutron multiplication parameters of pool-based stor

  6. Management concepts and safety applications for nuclear fuel facilities

    Energy Technology Data Exchange (ETDEWEB)

    Eisner, H.; Scotti, R.S. [George Washington Univ., Washington, DC (United States). School of Engineering and Applied Science; Delicate, W.S. [KEVRIC Co., Inc., Silver Spring, MD (United States)

    1995-05-01

    This report presents an overview of effectiveness of management control of safety. It reviews several modern management control theories as well as the general functions of management and relates them to safety issues at the corporate and at the process safety management (PSM) program level. Following these discussions, structured technique for assessing management of the safety function is suggested. Seven modern management control theories are summarized, including business process reengineering, the learning organization, capability maturity, total quality management, quality assurance and control, reliability centered maintenance, and industrial process safety. Each of these theories is examined for-its principal characteristics and implications for safety management. The five general management functions of planning, organizing, directing, monitoring, and integrating, which together provide control over all company operations, are discussed. Under the broad categories of Safety Culture, Leadership and Commitment, and Operating Excellence, key corporate safety elements and their subelements are examined. The three categories under which PSM program-level safety issues are described are Technology, Personnel, and Facilities.

  7. 78 FR 47014 - Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear...

    Science.gov (United States)

    2013-08-02

    ... COMMISSION Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear... 1 of RG 1.169, ``Configuration Management Plans for Digital Computer Software Used in Safety Systems... Accession No. ML12236A132. 2. Revision 1 of RG 1.169, ``Configuration Management Plans for Digital...

  8. Implementation plan for the Defense Nuclear Facilities Safety Board Recommendation 90-7. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Borsheim, G.L.; Cash, R.J.; Dukelow, G.T.

    1992-12-01

    This document revises the original plan submitted in March 1991 for implementing the recommendations made by the Defense Nuclear Facilities Safety Board in their Recommendation 90-7 to the US Department of Energy. Recommendation 90-7 addresses safety issues of concern for 24 single-shell, high-level radioactive waste tanks containing ferrocyanide compounds at the Hanford Site. The waste in these tanks is a potential safety concern because, under certain conditions involving elevated temperatures and low concentrations of nonparticipating diluents, ferrocyanide compounds in the presence of oxidizing materials can undergo a runaway (propagating) chemical reaction. This document describes those activities underway by the Hanford Site contractor responsible for waste tank safety that address each of the six parts of Defense Nuclear Facilities Safety Board Recommendation 90-7. This document also identifies the progress made on these activities since the beginning of the ferrocyanide safety program in September 1990. Revised schedules for planned activities are also included.

  9. Paul Scherrer Institut Scientific Report 2001. Volume IV: Nuclear Energy and Safety

    Energy Technology Data Exchange (ETDEWEB)

    Smith, B.L. (ed.)

    2002-03-01

    The year 2001 was marked by the extensive audit of energy research at PSI. The audit took place on 21/22 June, and nuclear energy research was evaluated by five international experts. It was possible to present the quality and relevance of our research in a convincing way. This, together with optimal use of the available resources in our department Nuclear Energy and Safety (NES), prompted the highly welcome result that the auditors attested a high degree of scientific quality to the NES projects in general, with some of them judged to be of world-class standard. They recommended all audited projects be maintained, adequate resources to be allocated accordingly and, if necessary, an increase of public funding in nuclear energy research to be granted to achieve this. Finally, it was recommended that energy research should be explicitly mentioned in the statement of the ultimate mission of PSI. At the level of 'daily work', efforts in several directions related to the future of the Hotlab were one of the main focuses during the past year. On the one hand, the safety-related backfitting of the facility (particularly in regard to fire protection) has been continued, and was coupled with intensive planning studies, and with a thorough radiological cleaning of the labs; this invariably led to some impediment to the current research activities. Despite external burdens, which have led to some delays and additional costs, three of the four refurbishment phases have been completed, and the corresponding laboratories were brought back into operation after inspection and approval by the regulatory authority HSK. Given the size and complexity of the project, progress must be considered very satisfactory. A list of scientific publications in 2000 is also provided.

  10. Implementation of the obligations of the convention on nuclear safety. Fourth Swiss report in accordance with Article 5

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-15

    Switzerland has signed the Convention on Nuclear Safety. Most of the requirements of the articles of the Convention were already standard practice in Switzerland. In the last years, all Swiss nuclear power plants (NPPs) as well as the Swiss Federal Nuclear Safety Inspectorate (HSK) built up documented quality management systems. The independence of HSK from licensing authorities is fulfilled on a technical level. In 2005, a new Nuclear Energy Act came into force requiring formal independence of the supervisory authorities from the licensing authorities. A separate act to legally settle the Inspectorate's fully independent status was adopted by Parliament. HSK participates in international projects and is represented in numerous nuclear safety working groups in order to ensure the exchange of scientific, technical and regulatory know-how. The regulatory processes applied to the licensing and safety surveillance of nuclear installations and their operation are up to date with the current state of science and technology. Deterministic and probabilistic safety evaluations guide and prioritise inspections and provide the basis for a graded approach to safety review and assessment. The surveillance of the NPPs' operating, control and safety systems, their component performance and integrity, their organisational and human aspects as well as the management, conditioning and interim storage of radioactive waste are permanent features of the supervisory authority's activities. Within the frame of a new integrated oversight process there is an annual systematic assessment of nuclear safety for each NPP based on the analysis of events, inspection results and operator licensing reviews. The assurance of low radiation doses to both NPP workers and the general public is an additional goal that is directly associated with the safe operation of NPPs. In case of an accident in a nuclear installation, contingency plans are in place and are continually updated

  11. Nuclear Safety Culture Assessment for a Newcomer Country: Case Study of Jordan

    Energy Technology Data Exchange (ETDEWEB)

    Khasawneh, Khalid; Park, Yun Woon [KAIST, Daejeon (Korea, Republic of)

    2016-05-15

    For countries initiating or considering to start their nuclear power programs; developing a successful safety culture is of a great challenge, owing to lack of experience and the sensitive nature of the nuclear industry in general. The Jordanian case was chosen since Jordan is in the early stages of its nuclear program and the establishment of an effective safety culture is crucial to guarantee the safe operation of its future nuclear facilities. It also should be noted that Fukushima accident has adversely affected the progress of the Jordanian nuclear program driven by the negative public opinion. The government shifts the policies toward enhancing the nuclear safety by enforcing the communication between the engaged parties and openness and transparency with public. In the wake of Fukushima accident the Jordanian government reassured the appropriate siting criteria and siting review, the leadership and the organizations commitment to nuclear safety by adopting advanced reactor technology, the consideration of modern operator accident mitigation strategies and the increased and close cooperation with IAEA and adherence to evolving international safety standards. The progress in the Jordanian nuclear power project in order to satisfy the IAEA requirements was quantified and ranked. A good progress was shown in some aspects, for example in the multicultural and multi-national elements and the establishment of an independent and effective regulatory body. However, some elements, concerning the understanding of the safety culture, management system of the regulatory body and the cultural assessment was not satisfied and an urgent need to focus on and enhance those aspects are required by the Jordanian government. Some elements, for example the leadership, communication and competence, have partial fulfillment of the IAEA requirements. However enhancing those aspects is required in the short and the mid-term in order to guarantee a well-established nuclear power

  12. Improving the regulation of safety at DOE nuclear facilities. Final report: Appendices

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    The report strongly recommends that, with the end of the Cold War, safety and health at DOE facilities should be regulated by outside agencies rather than by any regulatory scheme, DOE must maintain a strong internal safety management system; essentially all aspects of safety at DOE`s nuclear facilities should be externally regulated; and existing agencies rather than a new one should be responsible for external regulation.

  13. Improving the regulation of safety at DOE nuclear facilities. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    The report strongly recommends that, with the end of the Cold War, safety and health at DOE facilities should be regulated by outside agencies rather than by DOE itself. The three major recommendations are: under any regulatory scheme, DOE must maintain a strong internal safety management system; essentially all aspects of safety at DOE`s nuclear facilities should be externally regulated; and existing agencies rather than a new one should be responsible for external regulation.

  14. Sustainable and safe nuclear fission energy technology and safety of fast and thermal nuclear reactors

    CERN Document Server

    Kessler, Günter

    2012-01-01

    Unlike existing books of nuclear reactor physics, nuclear engineering and nuclear chemical engineering this book covers a complete description and evaluation of nuclear fission power generation. It covers the whole nuclear fuel cycle, from the extraction of natural uranium from ore mines, uranium conversion and enrichment up to the fabrication of fuel elements for the cores of various types of fission reactors. This is followed by the description of the different fuel cycle options and the final storage in nuclear waste repositories. In addition the release of radioactivity under normal and possible accidental conditions is given for all parts of the nuclear fuel cycle and especially for the different fission reactor types.

  15. WASTE PROCESSING ANNUAL NUCLEAR SAFETY RELATED R AND D REPORT FOR CY2008

    Energy Technology Data Exchange (ETDEWEB)

    Fellinger, A.

    2009-10-15

    The Engineering and Technology Office of Waste Processing identifies and reduces engineering and technical risks associated with key waste processing project decisions. The risks, and actions taken to mitigate those risks, are determined through technology readiness assessments, program reviews, technology information exchanges, external technical reviews, technical assistance, and targeted technology development and deployment (TDD). The Office of Waste Processing TDD program prioritizes and approves research and development scopes of work that address nuclear safety related to processing of highly radioactive nuclear wastes. Thirteen of the thirty-five R&D approved work scopes in FY2009 relate directly to nuclear safety, and are presented in this report.

  16. Efforts toward enhancing seismic safety at Kashiwazaki Kariwa nuclear power station

    Energy Technology Data Exchange (ETDEWEB)

    Yamashita, Kazuhiko

    2010-09-15

    Kashiwazaki-Kariwa Nuclear Power Station, 8212MW, was struck by M6.8 quakes in July 2007. TEPCO has steadily been conducting restoration and post-earthquake equipment integrity assessment, aiming to make it a disaster-resistant power station. 2 units among 7 resumed commercial operation by June 2010. This earthquake has provided a great deal of knowledge and information useful for nuclear safety improvement. It has also served as a valuable reference for the IAEA in developing earthquake-related guidelines. TEPCO would like to share the knowledge and information thereby contributing to improving the safety of nuclear power generation. We will introduce some of our activities.

  17. Safety assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto. Complementary evaluations of safety

    Energy Technology Data Exchange (ETDEWEB)

    Neall, Fiona; Pastina, Barbara; Snellman, Margit; Smith, Paul; Gribi, P.; Johnson, Lawrence

    2008-12-15

    The KBS-3H design is a variant of the more general KBS-3 method for the geological disposal of spent nuclear fuel in Finland and Sweden. In the KBS-3H design, multiple assemblies containing spent fuel are emplaced horizontally in parallel, approximately 300 m long, slightly inclined deposition drifts. The copper canisters, each with a surrounding layer of bentonite clay, are placed in perforated steel shells prior to deposition in the drifts; the assembly is called the 'supercontainer'. The other KBS-3 variant is the KBS-3V design, in which the copper canisters are emplaced vertically in individual deposition holes surrounded by bentonite clay but without steel supercontainer shells. SKB and Posiva have conducted a Research, Development and Demonstration programme over the period 2002-2007 with the overall aim of establishing whether KBS-3H represents a feasible alternative to KBS-3V. As part of this programme, the long-term safety of a KBS-3H repository has been assessed in the KBS-3H safety studies. In order to focus the safety studies, the Olkiluoto site in the municipality of Eurajoki, which is the proposed site for a spent fuel repository in Finland, was used as a hypothetical site for a KBS-3H repository. The present report is part of a portfolio of reports discussing the long-term safety of the KBS-3H repository. The overall outcome of the KBS-3H safety studies is documented in the summary report, 'Safety assessment for a KBS-3H repository for spent nuclear fuel at Olkiluoto'. The purpose and scope of the KBS-3H complementary evaluations of safety report is provided in Posiva's Safety Case Plan, which is based on Regulatory Guide YVL 8.4 and on international guidelines on complementary lines of argument to long-term safety that are considered an important element of a post-closure safety case for geological repositories. Complementary evaluations of safety require the use of evaluations, evidence and qualitative supporting arguments

  18. Eddy Current Examination of Spent Nuclear Fuel Canister Closure Welds

    Energy Technology Data Exchange (ETDEWEB)

    Arthur D. Watkins; Dennis C. Kunerth; Timothy R. McJunkin

    2006-04-01

    The National Spent Nuclear Fuel Program (NSNFP) has developed standardized DOE SNF canisters for handling and interim storage of SNF at various DOE sites as well as SNF transport to and SNF handling and disposal at the repository. The final closure weld of the canister will be produced remotely in a hot cell after loading and must meet American Society of Mechanical Engineers (ASME) Section III, Division 3 code requirements thereby requiring volumetric and surface nondestructive evaluation to verify integrity. This paper discusses the use of eddy current testing (ET) to perform surface examination of the completed welds and repair cavities. Descriptions of integrated remote welding/inspection system and how the equipment is intended function will also be discussed.

  19. Paul Scherrer Institute Scientific Report 2000. Volume IV: Nuclear Energy and Safety

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Brian; Gschwend, Beatrice [eds.

    2001-03-01

    Nuclear energy related research in Switzerland is concentrated at PSI's Nuclear Energy and Safety Research Department (NES). The activities of the department are concentrated on three main domains of: Safety and related problems of operating plants; safety features of future reactor and fuel cycles; waste management. Comprehensive assessments of energy systems are carried out in cooperation with PSI's General Energy Research Department. Many of the programs are part of collaborations with universities, industry, or international organisations. Progress in 2000 in these topical areas is described in this report. A list of scientific publications in 2000 is also provided.

  20. Safety assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto. Summary report

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Paul; Neall, Fiona; Snellman, Margit; Pastina, Barbara; Nordman, Henrik; Johnson, Lawrence; Hjerpe, Thomas

    2008-03-15

    The KBS-3 method, based on multiple barriers, is the proposed spent fuel disposal method both in Sweden and Finland. KBS-3H and KBS-3V are the two design alternatives of the KBS-3 spent fuel disposal method. Posiva and SKB have conducted a joint research, demonstration and development (RDandD) programme in 2002-2007 with the overall aim of establishing whether KBS-3H represents a feasible alternative to the reference alternative KBS-3V. The overall objectives of the present phase covering the period 2004-2007 have been to demonstrate that the horizontal deposition alternative is technically feasible and to demonstrate that it fulfils the same long-term safety requirements as KBS-3V. The safety studies conducted as part of this programme include a safety assessment of a preliminary design of a KBS-3H repository for spent nuclear fuel located about 400 m underground at the Olkiluoto site, which is the proposed site for a spent fuel repository in Finland. This safety assessment is summarised in the present report. The scientific basis of the safety assessment includes around 30 years of scientific RandD and technical development in the Swedish and Finnish KBS-3V programmes. Much of this scientific basis is directly applicable to KBS-3H. This has allowed the KBS-3H safety studies to focus on those issues that are unique to this design alternative, identified in a systematic 'difference analysis' of KBS-3H and KBS-3V. This difference analysis has shown that the key differences in the evolution and performance of KBS-3H and KBS-3V relate mainly to the engineered barrier system and to the impact of local variations in the rate of groundwater inflow on buffer saturation along the KBS-3H deposition drifts. No features or processes specific to KBS-3H have been identified that could lead to a loss or substantial degradation of the safety functions of the engineered barriers over a million year time frame. Radionuclide release from the repository near field in the

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

    CERN Document Server

    CERN. Geneva

    2013-01-01

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

  2. Standardization of Administered Activities in Pediatric Nuclear Medicine: A Report of the First Nuclear Medicine Global Initiative Project, Part 2-Current Standards and the Path Toward Global Standardization.

    Science.gov (United States)

    Fahey, Frederic H; Bom, Henry Hee-Seung; Chiti, Arturo; Choi, Yun Young; Huang, Gang; Lassmann, Michael; Laurin, Norman; Mut, Fernando; Nuñez-Miller, Rodolfo; O'Keeffe, Darin; Pradhan, Prasanta; Scott, Andrew M; Song, Shaoli; Soni, Nischal; Uchiyama, Mayuki; Vargas, Luis

    2016-07-01

    The Nuclear Medicine Global Initiative (NMGI) was formed in 2012 and consists of 13 international organizations with direct involvement in nuclear medicine. The underlying objectives of the NMGI are to promote human health by advancing the field of nuclear medicine and molecular imaging, encourage global collaboration in education, and harmonize procedure guidelines and other policies that ultimately lead to improvements in quality and safety in the field throughout the world. For its first project, the NMGI decided to consider the issues involved in the standardization of administered activities in pediatric nuclear medicine. It was decided to divide the final report of this project into 2 parts. Part 1 was published in this journal in the spring of 2015. This article presents part 2 of the final report. It discusses current standards for administered activities in children and adolescents that have been developed by various professional organizations. It also presents an evaluation of the current practice of pediatric nuclear medicine specifically with regard to administered activities as determined by an international survey of 313 nuclear medicine clinics and centers from 29 countries. Lastly, it provides recommendations for a path toward global standardization of the administration of radiopharmaceuticals in children.

  3. Fourth national report of Brazil for the nuclear safety convention. Sep. 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-09-15

    This Fourth National Report of Brazil is a new update to include relevant information of the period of 2004-2007. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

  4. Characterization and improvement of the nuclear safety culture through self-assessment

    Energy Technology Data Exchange (ETDEWEB)

    Levin, H.A. [Synergy Consulting Services Corp., Great Falls, VA (United States); McGehee, R.B. [Wise Carter Child & Caraway, Jackson, MS (United States); Cottle, W.T. [Houston Lighting & Power, Wadsworth, TX (United States)

    1996-12-31

    Organizational culture has a powerful influence on overall corporate performance. The ability to sustain superior results in ensuring the public`s health and safety is predicated on an organization`s deeply embedded values and behavioral norms and how these affect the ability to change and seek continuous improvement. The nuclear industry is developing increased recognition of the relationship of culture to nuclear safety performance as a critical element of corporate strategy. This paper describes a self-assessment methodology designed to characterize and improve the nuclear safety culture, including processes for addressing employee concerns. This methodology has been successfully applied on more than 30 occasions in the last several years, resulting in measurable improvements in safety performance and quality and employee motivation, productivity, and morale. Benefits and lessons learned are also presented.

  5. Improved Management of Part Safety Classification System for Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jin Young; Park, Youn Won; Park, Heung Gyu; Park, Hyo Chan [BEES Inc., Daejeon (Korea, Republic of)

    2016-10-15

    As, in recent years, many quality assurance (QA) related incidents, such as falsely-certified parts and forged documentation, etc., were reported in association with the supply of structures, systems, components and parts to nuclear power plants, a need for a better management of safety classification system was addressed so that it would be based more on the level of parts . Presently, the Korean nuclear power plants do not develop and apply relevant procedures for safety classifications, but rather the safety classes of parts are determined solely based on the experience of equipment designers. So proposed in this paper is a better management plan for safety equipment classification system with an aim to strengthen the quality management for parts. The plan was developed through the analysis of newly introduced technical criteria to be applied to parts of nuclear power plant.

  6. Application of Solar Chimney Concept to Solve Potential Safety Issues of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Khasawneh, Khalid; PARK, Youn Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    LUHS. In addition to its dual functionality; it provides a complete independent and diverse means of safety functions supporting, a free carbon oxide power production source and allow following the world's trend toward the usage of renewable energy sources. The Solar Chimney Power Plant was suggested to be employed as a supporting system for NPPs to provide emergency power, in case of SBO, and emergency cooling, in case of LUHS. It provides a complete independent and diverse means of safety function supporting. Following the SCPP operation requirements of the availability of high solar irradiation, the UAE region provides a perfect environment for its implementation; furthermore, it can be linked to the under-construction NPPs at Al-Barakah site to deliver alternative emergency power and emergency cooling. Due to the inherent unreliability of the currently utilized EDGs and the AAC power sources, a postulated SBO event could affect the safety of the NPP in general, and for the specific case of the UAE NPPs, a LUHS caused by oil spill accident in the UHS could be experienced, given the massive oil related activates being performed in the Arabian Gulf. Comparing the similarity between Al-Barakah site and the Loviisa NPP in Finland; looking for solution and alternatives for the enhancement of their reactors safety should be considered by the UAE nuclear regulator.

  7. Regulatory oversight report 2008 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2008 ueber die nukleare Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-04-15

    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.

  8. Uncertainty Quantification for Safety Verification Applications in Nuclear Power Plants

    Science.gov (United States)

    Boafo, Emmanuel

    There is an increasing interest in computational reactor safety analysis to systematically replace the conservative calculations by best estimate calculations augmented by quantitative uncertainty analysis methods. This has been necessitated by recent regulatory requirements that have permitted the use of such methods in reactor safety analysis. Stochastic uncertainty quantification methods have shown great promise, as they are better suited to capture the complexities in real engineering problems. This study proposes a framework for performing uncertainty quantification based on the stochastic approach, which can be applied to enhance safety analysis. (Abstract shortened by ProQuest.).

  9. KAERI software safety guideline for developing safety-critical software in digital instrumentation and control system of nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jang Soo; Kim, Jang Yeol; Eum, Heung Seop

    1997-07-01

    Recently, the safety planning for safety-critical software systems is being recognized as the most important phase in the software life cycle, and being developed new regulatory positions and standards by the regulatory and the standardization organization. The requirements for software important to safety of nuclear reactor are described in such positions and standards. Most of them are describing mandatory requirements, what shall be done, for the safety-critical software. The developers of such a software. However, there have been a lot of controversial factors on whether the work practices satisfy the regulatory requirements, and to justify the safety of such a system developed by the work practices, between the licenser and the licensee. We believe it is caused by the reason that there is a gap between the mandatory requirements (What) and the work practices (How). We have developed a guidance to fill such gap, which can be useful for both licenser and licensee to conduct a justification of the safety in the planning phase of developing the software for nuclear reactor protection systems. (author). 67 refs., 13 tabs., 2 figs.

  10. KAERI software safety guideline for developing safety-critical software in digital instrumentation and control system of nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jang Soo; Kim, Jang Yeol; Eum, Heung Seop

    1997-07-01

    Recently, the safety planning for safety-critical software systems is being recognized as the most important phase in the software life cycle, and being developed new regulatory positions and standards by the regulatory and the standardization organization. The requirements for software important to safety of nuclear reactor are described in such positions and standards. Most of them are describing mandatory requirements, what shall be done, for the safety-critical software. The developers of such a software. However, there have been a lot of controversial factors on whether the work practices satisfy the regulatory requirements, and to justify the safety of such a system developed by the work practices, between the licenser and the licensee. We believe it is caused by the reason that there is a gap between the mandatory requirements (What) and the work practices (How). We have developed a guidance to fill such gap, which can be useful for both licenser and licensee to conduct a justification of the safety in the planning phase of developing the software for nuclear reactor protection systems. (author). 67 refs., 13 tabs., 2 figs.

  11. How the nuclear safety team conducts emergency exercises at the IEA-R1 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Vaz, Antonio C.A.; Silva, Davilson G.; Toyoda, Eduardo Y.; Santia, Paulo S.; Conti, Thadeu N.; Semmler, Renato; Carvalho, Ricardo N., E-mail: acavaz@ipen.br, E-mail: dgsilva@ipen.br, E-mail: eytoyoda@ipen.br, E-mail: psantia@ipen.br, E-mail: tnconti@ipen.br, E-mail: rsemmler@ipen.b, E-mail: rncarval@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    This work introduces the Diagram of Emergency Exercise Coordination designed by the Nuclear Safety Team for better Emergency Exercise coordination. The Nuclear Safety Team was created with the mission of avoiding, preventing and mitigating the causes and effects of accidents at the IEA-R1. The facility where we conduct our work is located in an area of a huge population, what increases the responsibility of our mission: conducting exercises and training are part of our daily activities. During the Emergency Exercise, accidents ranked 0-4 on INES (International Nuclear Events Scale) are simulated and involve: Police Department, Fire Department, workers, people from the community, and others. In the last exercise held in June 2014, the scenario contemplated a terrorist organization action that infiltrated in a group of students who were visiting the IEA-R1, tried to steal fresh fuel element to fabricate a dirty bomb. Emergency procedures and plans, timeline and metrics of the actions were applied to the Emergency Exercise evaluation. The next exercise will be held in November, with the simulation of the piping of the primary cooling circuit rupture, causing the emptying of the pool and the lack of cooling of the fuel elements in the reactor core: this will be the scenario. The skills acquired and the systems improvement have been very important tools for the reactor operation safety and the Nuclear Safety Team is making technical efforts so that these Emergency Exercises may be applied to other nuclear and radiological facilities. Equally important for the process of improving nuclear safety is the emphasis placed on implementing quality improvements to the human factor in the nuclear safety area, a crucial element that is often not considered by those outside the nuclear sector. Surely, the Diagram of Emergency Exercise Coordination application will improve and facilitate the organization, coordination and evaluation tasks. (author)

  12. 77 FR 50722 - Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

    Science.gov (United States)

    2012-08-22

    ... COMMISSION Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants... regulatory guide (DG), DG-1208, ``Software Unit Testing for Digital Computer Software used in Safety Systems... entitled ``Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear...

  13. Criticality Safety Analysis Of As-loaded Spent Nuclear Fuel Casks

    Energy Technology Data Exchange (ETDEWEB)

    Banerjee, Kaushik [ORNL; Scaglione, John M [ORNL

    2015-01-01

    The final safety analysis report (FSAR) or the safety analysis report (SAR) for a particular spent nuclear fuel (SNF) cask system documents models and calculations used to demonstrate that a system meets the regulatory requirements under all normal, off-normal, and accident conditions of spent fuel storage, and normal and accident conditions of transportation. FSAR/SAR calculations and approved content specifications are intended to be bounding in nature to certify cask systems for a variety of fuel characteristics with simplified SNF loading requirements. Therefore, in general, loaded cask systems possess excess and uncredited criticality margins (i.e., the difference between the licensing basis and the as-loaded calculations). This uncredited margin could be quantified by employing more detailed cask-specific evaluations that credit the actual as-loaded cask inventory, and taking into account full (actinide and fission product) burnup credit. This uncredited criticality margin could be potentially used to offset (1) uncertainties in the safety basis that needs to account for the effects of system aging during extended dry storage prior to transportation, and (2) increases in SNF system reactivity over a repository performance period (e.g., 10,000 years or more) as the system undergoes degradation and internal geometry changes. This paper summarizes an assessment of cask-specific, as-loaded criticality margins for SNF stored at eight reactor sites (215 loaded casks were analyzed) under fully flooded conditions to assess the margins available during transportation after extended storage. It is observed that the calculated keff margin varies from 0.05 to almost 0.3 Δkeff for the eight selected reactor sites, demonstrating that significant uncredited safety margins are present. In addition, this paper evaluates the sufficiency of this excess margin in applications involving direct disposal of currently loaded SNF casks.

  14. Criticality Safety Analysis Of As-loaded Spent Nuclear Fuel Casks

    Energy Technology Data Exchange (ETDEWEB)

    Banerjee, Kaushik [ORNL; Scaglione, John M [ORNL

    2015-01-01

    The final safety analysis report (FSAR) or the safety analysis report (SAR) for a particular spent nuclear fuel (SNF) cask system documents models and calculations used to demonstrate that a system meets the regulatory requirements under all normal, off-normal, and accident conditions of spent fuel storage, and normal and accident conditions of transportation. FSAR/SAR calculations and approved content specifications are intended to be bounding in nature to certify cask systems for a variety of fuel characteristics with simplified SNF loading requirements. Therefore, in general, loaded cask systems possess excess and uncredited criticality margins (i.e., the difference between the licensing basis and the as-loaded calculations). This uncredited margin could be quantified by employing more detailed cask-specific evaluations that credit the actual as-loaded cask inventory, and taking into account full (actinide and fission product) burnup credit. This uncredited criticality margin could be potentially used to offset (1) uncertainties in the safety basis that needs to account for the effects of system aging during extended dry storage prior to transportation, and (2) increases in SNF system reactivity over a repository performance period (e.g., 10,000 years or more) as the system undergoes degradation and internal geometry changes. This paper summarizes an assessment of cask-specific, as-loaded criticality margins for SNF stored at eight reactor sites (215 loaded casks were analyzed) under fully flooded conditions to assess the margins available during transportation after extended storage. It is observed that the calculated keff margin varies from 0.05 to almost 0.3 Δkeff for the eight selected reactor sites, demonstrating that significant uncredited safety margins are present. In addition, this paper evaluates the sufficiency of this excess margin in applications involving direct disposal of currently loaded SNF casks.

  15. The development of safety relief valve for nuclear service

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Chil Sung; Kim, Kang Tae; Kim, Ji Heon; Jang, Ki Jong [Smart Valve Com., Seoul (Korea, Republic of); Hong, Kee Seong [Korea Hydro and Nuclear Power Co., Ltd., Seoul (Korea, Republic of)

    2003-07-01

    Safety relief valve is the important equipment used to protect the pressure facility from overpressure. The objective of the study is the development of safety relief valve which protects the boiler and pressure vessel from over pressure by discharging or sucking the operating medium when the pressure of system is reaching the set pressure of the system. It is important to find out the relationship between trim shape and performance, so the characteristics of flow field at the inside of safety relief valve were investigated through computational fluid dynamics analysis. The study shows that safety relief valve is developed though the design using the analysis between flow characteristics and spring force, the experiential verification.

  16. 75 FR 9232 - Measuring Progress on Food Safety: Current Status and Future Directions; Public Workshop

    Science.gov (United States)

    2010-03-01

    ... HUMAN SERVICES Food and Drug Administration Measuring Progress on Food Safety: Current Status and Future... about current and potential measurements for assessing progress in food safety and associated... workshop, contact Juanita Yates, Center for Food Safety and Applied Nutrition (HFS-009), Food and...

  17. Safety culture in nuclear power plants. Proceedings; Sicherheitskultur im Kernkraftwerk. Seminarbericht

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-01

    As a consequence of the INSAG-4 report on `safety culture`, published by the IAEA in 1991, the Federal Commission for the Safety of Nuclear Power Plants (KSA) decided to hold a one-day seminar as a first step in this field. The KSA is an advisory body of the Federal Government and the Federal Department of Transport and Energy (EVED). It comments on applications for licenses, observes the operation of nuclear power plants, assists with the preparation of regulations, monitors the progress of research in the field of nuclear safety, and makes proposals for research tasks. The objective of this seminar was to familiarise the participants with the principles of `safety culture`, with the experiences made in Switzerland and abroad with existing concepts, as well as to eliminate existing prejudices. The main points dealt with at this seminar were: - safety culture from the point of view of operators, - safety culture from the point of view of the authorities, - safety culture: collaboration between power plants, the authorities and research organisations, - trends and developments in the field of safety culture. Invitations to attend this seminar were extended to the management boards of companies operating Swiss nuclear power plants, and to representatives of the Swiss authorities responsible for the safety of nuclear power plants. All these organisations were represented by a large number of executive and specialist staff. We would like to express our sincerest thanks to the Head of the Federal Department of Transport and Energy for his kind patronage of this seminar. (author) figs., tabs., refs.

  18. Comprehensive Nuclear-Test-Ban Treaty: Background and Current Developments

    Science.gov (United States)

    2013-01-02

    Offer Tools for Nuclear Testing—and Solving Nuclear Mysteries ,” Washington Post, November 1, 2011, p. 1. Horovitz, Liviu, “A Detour Strategy for the...Today, October 2009, pp. 46-52. Kimball, Daryl, “Reconsidering the Nuclear Test Ban Treaty: Sorting Fact from Fiction ,” Arms Control Association

  19. Survey of systems safety analysis methods and their application to nuclear waste management systems

    Energy Technology Data Exchange (ETDEWEB)

    Pelto, P.J.; Winegardner, W.K.; Gallucci, R.H.V.

    1981-11-01

    This report reviews system safety analysis methods and examines their application to nuclear waste management systems. The safety analysis methods examined include expert opinion, maximum credible accident approach, design basis accidents approach, hazard indices, preliminary hazards analysis, failure modes and effects analysis, fault trees, event trees, cause-consequence diagrams, G0 methodology, Markov modeling, and a general category of consequence analysis models. Previous and ongoing studies on the safety of waste management systems are discussed along with their limitations and potential improvements. The major safety methods and waste management safety related studies are surveyed. This survey provides information on what safety methods are available, what waste management safety areas have been analyzed, and what are potential areas for future study.

  20. POSSIBILITIES FOR ASSESSMENT AND OPTIMIZATION OF NPP PHYSICAL PROTECTION SYSTEMS IN UKRAINE ON THE BASIS OF NUCLEAR SAFETY ANALYSIS

    Energy Technology Data Exchange (ETDEWEB)

    Shcherbinin, Konstantin

    2011-10-01

    The design requirements for physical protection systems currently adopted at Ukrainian NPPs were established in the middle of the nineties on the basis of deterministic analyses and expert evaluations of the vulnerabilities of reactor facilities. At the present time the in-depth assessment of the nuclear safety of Ukrainian NPPs with VVER-1000/B320 reactors has been completed using Probabilistic Safety Assessment (PSA). PSA has established and provided a qualitative assessment of the significance of the equipment for maintaining the integrity of a reactor core and preventing an abnormal radioactive release. The availability of qualitative assessments of the importance of equipment for nuclear safety allows one to assess the existing physical protection system using (1) comparative analysis: to determine whether all equipment and zones that may be affected, as established by the nuclear safety assessment, are actually included into the vital zones protected by the existing physical protection system; (2) specific analysis of dominant contributors: since nuclear safety analyses provide qualitative assessment of the equipment’s importance for safety, it is easy to select a limited group of essential equipment that makes the major contribution to safety, and (3) specific equipment analysis included in dominant emergency sets: part of the components might not be included in the essential equipment group, but it might be included in the dominant emergency sets. If some equipment is found not to be covered by the physical protection system, it is possible, using qualitative assessment of the importance of this equipment for safety, to assess the required degree of enhancement of physical protection. Such analysis will permit an assessment of the sufficiency of the existing physical protection system, to define the "tight" system areas and, therefore, to develop a justified optimization of a PPS with the objective of implementing priority upgrades to enhance safety, and

  1. Assessment of policy issues in nuclear safety regulation according to circumstantial changes

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Soon Heung; Lee, Byong Ho; Baek, Won Pil; Lee, Kwang Gu; Huh, Gyun Young; Hahn, Young Tae [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    2000-03-15

    The objective of the work is to assess various issues in nuclear safety regulation in consideration of circumstantial changes. Emphasis is given to the safety of operating NPPs. It is concluded that the Periodic Safety Review (PSR) should be implemented in Korea as soon as possible, in harmonization with the regulation for life extension of NPPs. The IAEA guidelines, including 10 year intervals and 11 safety factors, should be used as the basic guidelines. The approach to improve regulatory effectiveness is also reviewed and a transition to 'knowledge-based regulation' is suggested.

  2. Current treatment for anorexia nervosa: efficacy, safety, and adherence

    Directory of Open Access Journals (Sweden)

    Lindsay P Bodell

    2010-10-01

    Full Text Available Lindsay P Bodell, Pamela K KeelDepartment of Psychology, Florida State University, Tallahassee, FL, USAAbstract: Anorexia nervosa (AN is a serious psychiatric illness associated with significant medical and psychiatric morbidity, psychosocial impairment, increased risk of death, and chronicity. Given the severity of the disorder, the establishment of safe and effective treatments is necessary. Several treatments have been tried in AN, but few favorable results have emerged. This paper reviews randomized controlled trials in AN, and provides a synthesis of existing data regarding the efficacy, safety, and adherence associated with pharmacologic and psychological interventions. Randomized controlled trials for the treatment of AN published in peer-reviewed journals were identified by electronic and manual searches. Overall, pharmacotherapy has limited benefits in the treatment of AN, with some promising preliminary findings associated with olanzapine, an antipsychotic agent. No single psychological intervention has demonstrated clear superiority in treating adults with AN. In adolescents with AN, the evidence base is strongest for the use of family therapy over alternative individual psychotherapies. Results highlight challenges in both treating individuals with AN and in studying the effects of those treatments, and further emphasize the importance of continued efforts to develop novel interventions. Treatment trials currently underway and areas for future research are discussed.Keywords: anorexia nervosa, treatment, pharmacotherapy, psychotherapy, randomized controlled trials

  3. Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol. 11, No. 1--Vol. 17, No. 6

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W.B.; Klein, A.

    1977-02-23

    This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970), through Vol. 17, No. 6 (Nov.-Dec. 1976). The index includes a chronological list of articles (including abstract) followed by KWIC and Author Indexes. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 350 technical articles in the last six years of publication.

  4. Standardized System of Nuclear Safety Information for the Promotion of Transparency and Openness

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Gihyung; Kim, Sanghyun; Lee, Gyehwi; Yoon, Yeonhwa; Song, Song Hyerim; Jeong, Jina [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Byun, Jaehyung; Seo, Jonghwan [Dong-A Univ., Busan (Korea, Republic of)

    2013-05-15

    There has been an increasing emphasis on the need for increased disclosure of information through the home page of the Korea Institute of Nuclear Safety (KINS), responsible for nuclear safety regulations, and the Nuclear Safety Information Center (NSIC) to enhance public understanding of nuclear safety. However, due to the dazzled structure of the existing KINS and NSIC home pages, improvements in accessibility and convenience are necessary. At the same time, content standardization is required to increase operational efficiency and provide coherent information. In this study, the Delphi method was used to select the major contents to make available on the home page as well as the main user base definition for the home page layout development. Also, internal and external expert groups were created to conduct AHP (Analytic Hierarchy Process) analysis and develop the comparative analysis items for the U. S. Nuclear Regulatory Commission(NRC)/KINS/NSIC home pages. Afterwards, problems and points of improvements for the home page system, design, and profile were derived using heuristic analysis. The implications arising from the Delphi analysis results were applied to the home page layout. In the nuclear safety information standardized system construction process, the comparative analysis conducted using the AHP and heuristic analyses of the NRC home page resulted in deriving improvements for the Guidance, Organization, and Trustworthy items of the KINS/NSIC home page. Furthermore, through the Delphi analysis, a clear purpose and core values were set for the KINS web site, and the needs of the main user base were identified. By developing the home page layout, user interest and utility were raised to improve the organization method and layout. Through this study, KINS was able to construct a nuclear safety information standardized system and increase transparency and openness by providing feature enhancements in information provision as well as user accessibility and

  5. Paul Scherrer Institute Scientific Report 1999. Volume IV: Nuclear Energy and Safety

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Brian; Gschwend, Beatrice [eds.

    2000-07-01

    Nuclear energy related research in Switzerland is concentrated at PSI's Nuclear Energy and Safety Research Department (NES). The total effort invested in nuclear energy research in 1999 amounted to about 185 py/a and 4.7 MCHF of investment and maintenance costs. Approximately half of the salary, investment and maintenance costs are externally funded, primarily by the Swiss Utilities, the national co-operative for the disposal of nuclear waste (NAGRA), the Federal Office of Energy (BFE) through the nuclear safety inspectorate (HSK) and the Federal Office for Science and Education (BBW) in connection with the EU Framework Programmes; an increasing part of external funding is coming from domestic and foreign industry (nuclear component and fuel suppliers). The activities of the department are concentrated on three main domains of: Safety and related problems of operating plants; safety features of future reactor and fuel cycles; waste management. 4 % of the total resources are invested in addressing more global aspects of energy. Many of the programs are part of collaborations with universities, industry, or international organisations. Progress in 1999 in these topical areas is described in this report. A list of scientific publications in 1999 is also provided.

  6. Paul Scherrer Institute Scientific Report 1998. Volume IV: Nuclear Energy and Safety

    Energy Technology Data Exchange (ETDEWEB)

    Birchley, Jon; Ringele, Ruth [eds.

    1999-09-01

    Nuclear energy related research in Switzerland is concentrated at PSI`s Nuclear Energy and Safety Research Department (NES). The total effort invested in nuclear energy research in 1998 amounted to about 195 py/a and 4.5 millions CHF of investment and maintenance costs. Approximately half of the salary, investment and maintenance costs are externally funded, primarily by the Swiss Utilities, the national co-operative for the disposal of nuclear waste (NAGRA), the Federal Office of Energy (BFE) through the nuclear safety inspectorate (HSK) and the Federal Office for Science and Education (BBW) in connection with the EC Framework Programmes; an increasing part of external funding is coming from domestic and foreign industry (nuclear component and fuel suppliers). The activities of the department are concentrated on three main domains of: Safety and related problems of operating plants; safety features of future reactor and fuel cycles; waste management. 4 % of the total resources are invested in addressing more global aspects of energy. Many of the programs are part of collaborations with universities, industry, or international organisations. A list of scientific publications in 1998 is included. (author) figs., tabs., refs.

  7. Development of the Continued Improvement System for Nuclear Safety Culture

    Energy Technology Data Exchange (ETDEWEB)

    Park, H. C.; Park, H. G.; Park, Y. W.; Park, J. Y. [KAIST, Daejeon (Korea, Republic of)

    2016-05-15

    It has been found that almost 80 % of the incidents and accidents occurred recently, such as the Fukushima Daiichi disaster and Domestic SBO accident etc. were analyzed to be caused from human errors. (IAEA NES NG-G-2.1) Which strongly claims the importance of the safety culture system. Accordingly, it should be away from a cursory approach like one-off field survey or Snap shop which were being conducted at present for the continued improvement of safety culture. This study introduces an analytical methodology which approaches the generic form of the safety both consciously and unconsciously expressed with behavior, thoughts, and attitude etc. This study was implemented only for open materials such as Inspection report, incidents and accidents reports, QA documents because of the limitation in accessibility to data. More effective use with securing operational data will be possible in future.

  8. Incorporating organizational factors into probabilistic safety assessment of nuclear power plants through canonical probabilistic models

    Energy Technology Data Exchange (ETDEWEB)

    Galan, S.F. [Dpto. de Inteligencia Artificial, E.T.S.I. Informatica (UNED), Juan del Rosal, 16, 28040 Madrid (Spain)]. E-mail: seve@dia.uned.es; Mosleh, A. [2100A Marie Mount Hall, Materials and Nuclear Engineering Department, University of Maryland, College Park, MD 20742 (United States)]. E-mail: mosleh@umd.edu; Izquierdo, J.M. [Area de Modelado y Simulacion, Consejo de Seguridad Nuclear, Justo Dorado, 11, 28040 Madrid (Spain)]. E-mail: jmir@csn.es

    2007-08-15

    The {omega}-factor approach is a method that explicitly incorporates organizational factors into Probabilistic safety assessment of nuclear power plants. Bayesian networks (BNs) are the underlying formalism used in this approach. They have a structural part formed by a graph whose nodes represent organizational variables, and a parametric part that consists of conditional probabilities, each of them quantifying organizational influences between one variable and its parents in the graph. The aim of this paper is twofold. First, we discuss some important limitations of current procedures in the {omega}-factor approach for either assessing conditional probabilities from experts or estimating them from data. We illustrate the discussion with an example that uses data from Licensee Events Reports of nuclear power plants for the estimation task. Second, we introduce significant improvements in the way BNs for the {omega}-factor approach can be constructed, so that parameter acquisition becomes easier and more intuitive. The improvements are based on the use of noisy-OR gates as model of multicausal interaction between each BN node and its parents.

  9. A Study on the Construct Validity of Safety Culture Oversight Model for Nuclear Power Operating Organization

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Su Jin; Choi, Young Sung; Oh, Jang Jin [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-05-15

    In Korea, the safety policy statement declared in 1994 by government stressed the importance of safety culture and licensees were encouraged to manage and conduct their self-assessments. A change in regulatory position about safety culture oversight was made after the event of SBO cover-up in Kori unit 1 and several subsequent falsification events. Since then KINS has been developing licensee's safety culture oversight system including conceptual framework of oversight, prime focus area for oversight, and specific details on regulatory expectations, all of which are based on defence-in-depth (DiD) safety enhancement approach. Development and gathering of performance data which is related to actual 'safety' of nuclear power plant are needed to identify the relationship between safety culture and safety performance. Authors consider this study as pilot which has a contribution on verifying the construct validity of the model and the effectiveness of survey based research. This is the first attempt that the validity of safety culture oversight model has been investigated with empirical data obtained from Korean nuclear power operating organization.

  10. Aging of turbine drives for safety-related pumps in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Cox, D.F. [Oak Ridge National Lab., TN (United States)

    1995-06-01

    This study was performed to examine the relationship between time-dependent degradation and current industry practices in the areas of maintenance, surveillance, and operation of steam turbine drives for safety-related pumps. These pumps are located in the Auxiliary Feedwater (AFW) system for pressurized-water reactor plants and in the Reactor Core Isolation Cooling and High-Pressure Coolant Injection systems for boiling-water reactor plants. This research has been conducted by examination of failure data in the Nuclear Plant Reliability Data System, review of Licensee Event Reports, discussion of problems with operating plant personnel, and personal observation. The reported failure data were reviewed to determine the cause of the event and the method of discovery. Based on the research results, attempts have been made to determine the predictability of failures and possible preventive measures that may be implemented. Findings in a recent study of AFW systems indicate that the turbine drive is the single largest contributor to AFW system degradation. However, examination of the data shows that the turbine itself is a reliable piece of equipment with a good service record. Most of the problems documented are the result of problems with the turbine controls and the mechanical overspeed trip mechanism; these apparently stem from three major causes which are discussed in the text. Recent improvements in maintenance practices and procedures, combined with a stabilization of the design, have led to improved performance resulting in a reliable safety-related component. However, these improvements have not been universally implemented.

  11. Implementation of the obligations of the Convention on Nuclear Safety. The first Swiss report in accordance with Article 5

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This report is issued according to Article 5 of the International Convention on Nuclear Safety. It has been produced by the Swiss Federal Nuclear Safety Inspectorate. Before submission to the Federal Department of Environment, Transport, Energy and Communication, the report has been commented by the Federal Office of Energy (BFE/OFEN), the Swiss Federal Nuclear Safety Commission (KSA/CSA), and the Swiss nuclear power plants of Beznau, Leibstadt and Muehleberg. The Goesgen nuclear power plant has chosen not to comment on the report. The introduction to the report provides general information about Switzerland, a brief political history of nuclear power and an overview of the nuclear facilities in Switzerland. In the subsequent sections, numbered after the Articles 6 to 19 of the Convention on Nuclear Safety, key aspects are commented on in such a way as to give a clear indication on how the various duties imposed by the Convention are fulfilled in Switzerland.

  12. Safety Management Characteristics Reflected in Interviews at Swedish Nuclear Power Plants: A System Perspective Approach

    Energy Technology Data Exchange (ETDEWEB)

    Salo, Ilkka (Risk Analysis, Social and Decision Research Unit, Dept. of Psychology, Stockholm Univ., Stockholm (Sweden))

    2005-12-15

    The present study investigated safety management characteristics reflected in interviews with participants from two Swedish nuclear power plants. A document analysis regarding the plants' organization, safety policies, and safety culture work was carried out as well. The participants (n=9) were all nuclear power professionals, and the majority managers at different levels with at least 10 years of nuclear power experience. The interview comprised themes relevant for organizational safety and safety management, such as: organizational structures and organizational change, threats to safety, information feedback and knowledge transfer, safety analysis, safety policy, and accident and incident analysis and reporting. The results were in part modeled to important themes derived from a general system theoretical framework suggested by Svenson and developed by Svenson and Salo in relation to studies of 'non-nuclear' safety organizations. A primer to important features of the system theoretical framework is presented in the introductory chapter. The results from the interviews generated interesting descriptions about nuclear safety management in relation to the above themes. Regarding organizational restructuring, mainly centralizations of resources, several examples of reasons for the restructuring and related benefits for this centralization of resources were identified. A number of important reminders that ought to be considered in relation to reorganization were also identified. Regarding threats to the own organization a number of such was interpreted from the interviews. Among them are risks related to generation and competence change-over and risks related to outsourcing of activities. A thorough picture of information management and practical implications related to this was revealed in the interviews. Related to information feedback is the issue of organizational safety indicators and safety indicators in general. The interview answers indicated

  13. Preliminary nuclear safety assessment of the NEPST (Topaz 2) space reactor program

    Science.gov (United States)

    Marshall, A. C.

    The United States (US) Strategic Defense Initiative Organization (SDIO) decided to investigate the possibility of launching a Russian Topaz 2 space nuclear power system. A preliminary nuclear safety assessment was conducted to determine whether or not a space mission could be conducted safely and within budget constraints. As part of this assessment, a safety policy and safety functional requirements were developed to guide both the safety assessment and future Topaz 2 activities. A review of the Russian flight safety program was conducted and documented. Our preliminary nuclear safety assessment included a number of deterministic analyses, such as the following: neutronic analysis of normal and accident configurations, an evaluation of temperature coefficients of reactivity, a reentry and disposal analysis, an analysis of postulated launch abort impact accidents, and an analysis of postulated propellant fire and explosion accidents. Based on the assessment to date, it appears that it will be possible to safely launch the Topaz 2 system in the US with a modification to preclude water flooded criticality. A full scale safety program is now underway.

  14. Complementary Safety Margin Assessment f the Nuclear Installations of the research reactor in Petten, Netherlands

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-02-15

    On March 11, 2011, a large part of the Japanese eastern coastal area was devastated by an earthquake, followed by an immense tsunami. As a result, thousands of people were killed, injured or made homeless. In the days that followed, the situation was further complicated because of the failing nuclear reactors on the Fukushima coast. The local environment suffered from radioactive releases, requiring evacuation zones, and generating international concerns about nuclear safety. In the wake of this disaster the European Union decided to assess safety on all operating nuclear reactors in its member states. This safety evaluation initiated by the European Union focusses on extreme natural hazards, beyond the standard safety evaluations which regularly have to be performed to demonstrate the safety of a nuclear power plant. Consequences of these extreme hazards for the research reactor in Petten, Netherlands, have been evaluated based on available safety analyses, supplemented by engineering judgement. In this way, the robustness of the existing plant has been assessed and possible measures to further increase the safety margins have been identified. This document presents the results of the Complementary Safety margin Assessment (CSA) performed for the 'Onderzoekslocatie Petten'. The distinct difference between this report and former risk analysis reports in general and the existing Safety Report of the Petten reactor is that the maximum resistance of the plant against redefined and more challenging events has been investigated, whereas traditionally the plant design is investigated against certain events that are determined on a historical basis. This different approach requires different analyses and studies, which in turn presents new insights into the robustness of the plant. The main purpose of this report is to answer the questions posed by the Ministry of Economic Affairs, Agriculture and Innovation. It was decided to write at the same time a report in

  15. Second periodic safety review of Angra Nuclear Power Station, unit 1

    Energy Technology Data Exchange (ETDEWEB)

    Martins, Carlos F.O.; Crepaldi, Roberto; Freire, Enio M., E-mail: ottoncf@tecnatom.com.br, E-mail: emfreire46@gmail.com, E-mail: robcrepaldi@hotmail.com [Tecnatom do Brasil Engenharia e Servicos Ltda, Rio de Janeiro, RJ (Brazil); Campello, Sergio A., E-mail: sacampe@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    This paper describes the second Periodic Safety Review (PSR2-A1) of Angra Nuclear Power Station, Unit 1, prepared by Eletrobras Eletronuclear S.A. and Tecnatom do Brasil Engenharia e Servicos Ltda., during Jul.2013-Aug.2014, covering the period of 2004-2013. The site, in Angra dos Reis-RJ, Brazil, comprises: Unit 1, (640 MWe, Westinghouse PWR, operating), Unit 2 (1300 MWe, KWU/Areva, operating) and Unit 3 (1405 MWe, KWU/Areva, construction). The PSR2-A1 attends the Standards 1.26-Safety in Operation of Nuclear Power Plants, Brazilian Nuclear Regulatory Commission (CNEN), and IAEA.SSG.25-Periodic Safety Review of Nuclear Power Plants. Within 18 months after each 10 years operation, the operating organization shall perform a plant safety review, to investigate the evolution consequences of safety code and standards, regarding: Plant design; structure, systems and components behavior; equipment qualification; plant ageing management; deterministic and probabilistic safety analysis; risk analysis; safety performance; operating experience; organization and administration; procedures; human factors; emergency planning; radiation protection and environmental radiological impacts. The Review included 6 Areas and 14 Safety Parameters, covered by 33 Evaluations.After document evaluations and discussions with plant staff, it was generated one General and 33 Specific Guide Procedures, 33 Specific and one Final Report, including: Description, Strengths, Deficiencies, Areas for Improvement and Conclusions. An Action Plan was prepared by Electronuclear for the recommendations. It was concluded that the Unit was operated within safety standards and will attend its designed operational lifetime, including possible life extensions. The Final Report was submitted to CNEN, as one requisite for renewal of the Unit Permanent Operation License. (author)

  16. 10 CFR 50.49 - Environmental qualification of electric equipment important to safety for nuclear power plants.

    Science.gov (United States)

    2010-01-01

    ... important to safety for nuclear power plants. 50.49 Section 50.49 Energy NUCLEAR REGULATORY COMMISSION... nuclear power plants. (a) Each holder of or an applicant for an operating license issued under this part... nuclear power plant for which the certifications required under § 50.82(a)(1) or § 52.110(a)(1) of...

  17. Comprehensive Nuclear-Test-Ban Treaty: Background and Current Developments

    Science.gov (United States)

    2013-06-10

    09/205_119828.html; and Foster Klug and Matthew Pennington, “Photos Show NKorea Nuclear Readiness,” Associated Press/ ABC News, December 28, 2012, http...the CTBT, lack of Chinese ratification, U.S. efforts to seek renegotiation of the ABM Treaty, and efforts to ban nuclear weapons in the Middle East led...Readiness,” Associated Press/ ABC News, December 28, 2012, http://abcnews.go.com/International/wireStory/ap- exclusive-photos-show-nkorea-nuclear

  18. Commercial US nuclear reactors and waste: the current status

    Energy Technology Data Exchange (ETDEWEB)

    Platt, A.M.; Robinson, J.V.

    1980-09-01

    Between March 1 and June 15, 1980, the declared size of the commercial light waste reactor (LWR) nuclear power industry in the US has decreased another 9 GWe. For the presently declared size: the 165 declared reactors will peak at a capacity of 153 GWe in 2001 and will consume about 870,000 MTU as enrichment feed; the theoretical rate of enrichment requirements will peak at about 19,000,000 SWUs/y in the year 2014; as few as two repositories each with capacity equivalent to 100,000 MTU would hold the waste; and predisposal storage reactor basins and AFRs (away-from-reactor basins) would peak at <85,000 MTU in the year 2020 if the two respositories were commissioned in the years 1997 and 2020. It should be noted that the number of declared LWRs has dropped from 226 on December 31, 1974 to 165 as of this writing. The oil equivalent of the energy loss, assuming a 50% efficiency in use as in cars, is 17,000 million barrels. This is about 10 years of the current rate of US consumption of OPEC oil.

  19. Paul Scherrer Institut annual report 1995. Annex IV: PSI nuclear energy and safety

    Energy Technology Data Exchange (ETDEWEB)

    Birchley, J.; Roesel, R.; Doesburg, R. van [eds.] [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1996-09-01

    Nuclear energy research in Switzerland is concentrated at PSI`s Department F4. It is explicitly mentioned in the Institute`s official charter and commands about one fifth of the Institute`s federal resources. Presently, PSI invests approx. 200 py/a in nuclear energy research, one third of this being externally funded; the share of external funding in investment costs totals approx. 50%. This funding is provided by the Swiss utilities and the NAGRA, the Safety Authority (HSK) and the former National Fund for Energy Research (NEFF). PSI`s activities in nuclear research concentrate on three main areas: safety of operating plants, safety features of future reactor concepts and waste management. 7% of personnel are invested in addressing global aspects of energy. (author) figs., tabs., refs.

  20. Emergency response and nuclear risk governance. Nuclear safety at nuclear power plant accidents; Notfallschutz und Risk Governance. Zur nuklearen Sicherheit bei Kernkraftwerksunfaellen

    Energy Technology Data Exchange (ETDEWEB)

    Kuhlen, Johannes

    2014-07-01

    The present study entitled ''Emergency Response and Nuclear Risk Governance: nuclear safety at nuclear power plant accidents'' deals with issues of the protection of the population and the environment against hazardous radiation (the hazards of nuclear energy) and the harmful effects of radioactivity during nuclear power plant accidents. The aim of this study is to contribute to both the identification and remediation of shortcomings and deficits in the management of severe nuclear accidents like those that occurred at Chernobyl in 1986 and at Fukushima in 2011 as well as to the improvement and harmonization of plans and measures taken on an international level in nuclear emergency management. This thesis is divided into a theoretical part and an empirical part. The theoretical part focuses on embedding the subject in a specifically global governance concept, which includes, as far as Nuclear Risk Governance is concerned, the global governance of nuclear risks. Due to their characteristic features the following governance concepts can be assigned to these risks: Nuclear Safety Governance is related to safety, Nuclear Security Governance to security and NonProliferation Governance to safeguards. The subject of investigation of the present study is as a special case of the Nuclear Safety Governance, the Nuclear Emergency governance, which refers to off-site emergency response. The global impact of nuclear accidents and the concepts of security, safety culture and residual risk are contemplated in this context. The findings (accident sequences, their consequences and implications) from the analyses of two reactor accidents prior to Fukushima (Three Mile Iceland in 1979, Chernobyl in 1986) are examined from a historical analytical perspective and the state of the Nuclear Emergency governance and international cooperation aimed at improving nuclear safety after Chernobyl is portrayed by discussing, among other topics, examples of &apos

  1. Nuclear criticality safety experiments, calculations, and analyses: 1958 to 1982. Volume 1. Lookup tables

    Energy Technology Data Exchange (ETDEWEB)

    Koponen, B.L.; Hampel, V.E.

    1982-10-21

    This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains - in chronological order - the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41.

  2. The Nordic nuclear safety research. Plan 1995; Nordisk kernesikkerhedsprogram 1994-1997. Plan for 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-02-01

    The annual plans for the 4-year Nordic nuclear safety program, initiated in 1994, are described. The goals of this program are information exchange and common consensus in the field of nuclear safety, radiation protection and emergency preparedness among the respective Nordic authorities. Awareness of all the safety and radiation protection aspects in the Nordic countries as well as in the neighbouring countries is to be strengthened. The present four-years plan comprehends 7 main projects on reactor safety, waste management, environmental effects and emergency plans. The eighth project is of administrative nature. Numerous national authorities, enterprises and institutions support the program through contribution of unpaid work, providing of laboratory resources etc. (EG).

  3. Safety management at nuclear installations with research reactors. A comparison of five European installations

    Energy Technology Data Exchange (ETDEWEB)

    Troen, H.; Lauridsen, B.

    1997-11-01

    Five European institutions with nuclear research reactors were visited to compare safety management among institutions similar to Risoe. Risoe is a National Laboratory and the main activities are research and development. In 1996 it was decided to look into safety management at Risoe again; the last revision was in 1972. The purpose was to make it more efficient and to emphasise, that the responsibility lies in the operating organisation. Information such as nuclear facilities at the institutions, the safety management organisation, emergency preparedness, and lists of radiation doses to the employees from the years 1995 and 1996 is given in the report. Also international requirements and recommendations are given in short. Furthermore the report contains some reflections on the development in safety management organisations in resent years and the conclusions drawn from the information gathered.

  4. Strengthening safety compliance in nuclear power operations: a role-based approach.

    Science.gov (United States)

    Martínez-Córcoles, Mario; Gracia, Francisco J; Tomás, Inés; Peiró, José M

    2014-07-01

    Safety compliance is of paramount importance in guaranteeing the safe running of nuclear power plants. However, it depends mostly on procedures that do not always involve the safest outcomes. This article introduces an empirical model based on the organizational role theory to analyze the influence of legitimate sources of expectations (procedures formalization and leadership) on workers' compliance behaviors. The sample was composed of 495 employees from two Spanish nuclear power plants. Structural equation analysis showed that, in spite of some problematic effects of proceduralization (such as role conflict and role ambiguity), procedure formalization along with an empowering leadership style lead to safety compliance by clarifying a worker's role in safety. Implications of these findings for safety research are outlined, as well as their practical implications.

  5. Safety features in nuclear power plants to eliminate the need of emergency planning in public domain

    Indian Academy of Sciences (India)

    P K Vijayan; M T Kamble; A K Nayak; K K Vaze; R K Sinha

    2013-10-01

    Following the Fukushima accident, the safety features of Nuclear Power Plants (NPP) are being re-examined worldwide including India to demonstrate capabilities to cope with severe accidents. In order to restore public confidence and support for nuclear power, it is felt necessary to design future NPPs with near zero impact outside the plant boundary and thus enabling elimination of emergency planning in public domain. Authors have identified a set of safety features which are needed to be incorporated in advanced reactors to achieve this goal. These features enabling prevention, termination, mitigation and containment of radioactivity for beyond design basis accidents arising from extreme natural events are essential for achieving the goal of elimination of emergency planning in public domain. Inherent safety characteristics, passive and engineered safety features to achieve these functions are discussed in this paper. Present trends and future developments in this direction are also described briefly.

  6. Additional Studies of the Criticality Safety of Failed Used Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Marshall, William BJ J [ORNL; Wagner, John C [ORNL

    2013-01-01

    Commercial used nuclear fuel (UNF) in the United States is expected to remain in storage for periods potentially greater than 40 years. Extended storage (ES) time and irradiation to high-burnup values (>45 GWd/t) may increase the potential for fuel failure during normal and accident conditions involving storage and transportation. Fuel failure, depending on the severity, could result in changes to the geometric configuration of the fuel, which has safety and regulatory implications. The likelihood and extent of fuel reconfiguration and its impact on the safety of the UNF is not well understood. The objective of this work is to assess and quantify the impact of fuel reconfiguration due to fuel failure on criticality safety of UNF in storage and transportation casks. Criticality analyses are conducted considering representative UNF designs covering a range of enrichments and burnups in multiple cask systems. Prior work developed a set of failed fuel configuration categories and specific configurations were evaluated to understand trends and quantify the consequences of worst-case potential reconfiguration progressions. These results will be summarized here and indicate that the potential impacts on subcriticality can be rather significant for certain configurations (e.g., >20% keff). It can be concluded that the consequences of credible fuel failure configurations from ES or transportation following ES are manageable (e.g., <5% keff). The current work expands on these efforts and examines some modified scenarios and modified approaches to investigate the effectiveness of some techniques for reducing the calculated increase in keff. The areas included here are more realistic modeling of some assembly types and the effect of reconfiguration of some assemblies in the storage and transportation canister.

  7. Role of RELAP/SCDAPSIM in Nuclear Safety

    Directory of Open Access Journals (Sweden)

    C. M. Allison

    2010-01-01

    Full Text Available The RELAP/SCDAPSIM code, designed to predict the behaviour of reactor systems during normal and accident conditions, is being developed as part of the international SCDAP Development and Training Program (SDTP. SDTP consists of nearly 60 organizations in 28 countries supporting the development of technology, software, and training materials for the nuclear industry. The program members and licensed software users include universities, research organizations, regulatory organizations, vendors, and utilities located in Europe, Asia, Latin America, and the United States. Innovative Systems Software (ISS is the administrator for the program. RELAP/SCDAPSIM is used by program members and licensed users to support a variety of activities. The paper provides a brief review of some of the more important activities including the analysis of research reactors and Nuclear Power Plants, design and analysis of experiments, and training.

  8. Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Main report

    Energy Technology Data Exchange (ETDEWEB)

    Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

    1982-03-01

    Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). The study results are presented in two volumes. Volume 1 (Main Report) contains the results in summary form.

  9. A stable regulatory frame, a key for the health and safety in nuclear renaissance; Un marco regulador estable, clave para la salud y la seguridad en el renacimiento nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Klein, D.

    2008-07-01

    Thirty one nations currently operate 439 reactors, and there are 34 reactors under construction in 11 nations. In addition, the U.S. Department of Energy (DOE) estimates that in a little more than two decades, 55 countries will operate 630 reactors and that by mid-century, 86 countries could have operating commercial reactors. Any measure, a nuclear renaissance is upon us. According to U.S. government estimates, within the next two decades 24 countries will be building and operating nuclear reactors for the first time. One concern for me is that many of these nations have neither a nuclear infrastructure nor nuclear experience. The current nuclear resurgence brings with it the unique opportunity to enhance the safety and security of the new reactors. (Author)

  10. Current Status and Future Perspective of Nuclear Cardiology

    Energy Technology Data Exchange (ETDEWEB)

    Chung, June Key [Seoul National University College of Medicine, Seoul (Korea, Republic of)

    2009-06-15

    Coronary artery disease is on the rise over the world. Myocardial perfusion SPECT is a well established technique to detect coronary artery disease and to assess left ventricular function. In addition, it has the unique ability to predict the prognosis of the patients. Moreover, the application of ECG-gated images provided the quantitative data and improved the accuracy. This approach has been proved to be cost-effective and suitable for the emerging economies as well as developed countries. However, the utilization of nuclear cardiology procedures vary widely considering the different countries and region of the world. Korea exits 2-3 times less utilization than Japan, and 20 times than the United States. Recently, with the emerging of new technology, namely cardiac CT, cardiac MR and stress echocardiography, the clinical usefulness of nuclear cardiology has been called in question and its role has been redefined. For the proper promotion of nuclear cardiology, special educations should be conducted since the nuclear cardiology has the contact points between nuclear medicine and cardiology. Several innovations are in horizon which will impact the diagnostic accuracy as well as imaging time and cost savings. Development of new tracers, gamma camera technology and hybrid systems will open the new avenue in cardiac imaging. The future of nuclear cardiology based on molecular imaging is very exciting. The newly defined biologic targets involving atherosclerosis and vascular vulnerability will allow the answers for the key clinical questions. Hybrid techniques including SPECT/CT indicate the direction in which clinical nuclear cardiology may be headed in the immediate future. To what extent nuclear cardiology will be passively absorbed by other modalities, or will actively incorporate other modalities, is up to the present and next generation of nuclear cardiologists.

  11. A Qualitative Assessment of Current CCF Guidance Based on a Review of Safety System Digital Implementation Changes with Evolving Technology

    Energy Technology Data Exchange (ETDEWEB)

    Korsah, Kofi [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Muhlheim, Michael David [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wood, Richard [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-04-01

    The US Nuclear Regulatory Commission (NRC) is initiating a new rulemaking project to develop a digital system common-cause failure (CCF) rule. This rulemaking will review and modify or affirm the NRC's current digital system CCF policy as discussed in the Staff Requirements Memorandum to the Secretary of the Commission, Office of the NRC (SECY) 93-087, Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light Water Reactor (ALWR) Designs, and Branch Technical Position (BTP) 7-19, Guidance on Evaluation of Defense-in-Depth and Diversity in Digital Computer-Based Instrumentation and Control Systems, as well as Chapter 7, Instrumentation and Controls, in NRC Regulatory Guide (NUREG)-0800, Standard Review Plan for Review of Safety Analysis Reports for Nuclear Power Plants (ML033580677). The Oak Ridge National Laboratory (ORNL) is providing technical support to the NRC staff on the CCF rulemaking, and this report is one of several providing the technical basis to inform NRC staff members. For the task described in this report, ORNL examined instrumentation and controls (I&C) technology implementations in nuclear power plants in the light of current CCF guidance. The intent was to assess whether the current position on CCF is adequate given the evolutions in digital safety system implementations and, if gaps in the guidance were found, to provide recommendations as to how these gaps could be closed.

  12. Assessment of Safety Culture within the Pakistan Nuclear Regulatory Authority (PNRA)

    Energy Technology Data Exchange (ETDEWEB)

    Afzal, Muhammad [Pakistan Nuclear Regulatory Authority, Islamabad (Pakistan); Choi, Kwang Sik [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-10-15

    The objective of this study is to assess the SC of the Pakistan Nuclear Regulatory Authority (PNRA) by developing a performance indicator-based questionnaire. Aspects that potentially play important roles in developing perceptions of SC, including age, type of job, gender and duty hours of regulatory staff, are given due importance in this study. The study also identifies the strengths and weaknesses in the SC of the PNRA and can be used as a model study to assess the SC of other RBs. The questionnaire, developed to assess the SC of the PNRA, was in line with the PNRA's own defined attributes for SC. In the past, significant efforts have been made to ensure the safe operation of NPPs by improving designs and operating procedures; however, the nuclear accident at the Fukushima NPP in Japan in March 2011 revealed that the currently allotted hardware safety margins are not sufficient, and much work is needed to improve safety management in terms of SC. Initially, the concept of SC was introduced for operating organizations to ensure safe operation of NPPs; nonetheless, more recent investigations of nuclear events and accidents, especially Fukushima, and at Davis-Besse, in the US, have revealed that a strong focus is required to address and improve the SC of Regulatory Bodies (RBs). Strong SC is considered a vital tool for RBs to achieve their objectives and discharge their responsibilities in an effective and efficient manner. Though the relationship between the SC of RBs and that of operating organizations is not straight forward, it is believed that the former has a strong influence over the latter. The questionnaire was consistent in terms of the credible nature of its questions, and the response group covered different levels of PNRA staff, from managers to lower level staff. The results show that the PNRA staff have a very good understanding of the nature and significance of attributes of SC and are doing their best to exercise the same within the

  13. Organizational analysis and safety for utilities with nuclear power plants: perspectives for organizational assessment. Volume 2. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Nadel, M.V.; Scott, W.G.; Connor, P.E.; Kerwin, N.; Kennedy, J.K. Jr.

    1983-08-01

    This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. Volume 1 of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety. The six chapters of this volume discuss the major elements in our general approach to safety in the nuclear industry. The chapters include information on organizational design and safety; organizational governance; utility environment and safety related outcomes; assessments by selected federal agencies; review of data sources in the nuclear power industry; and existing safety indicators.

  14. Report on nuclear installations safety and security control. Rapport sur le controle de la surete et de la securite des installations nucleaires. Surete des installations. Securite et information

    Energy Technology Data Exchange (ETDEWEB)

    Birraux, C.; Serusclat, F.

    1990-01-01

    This report of the parliamentary office for evaluation of scientific and technological choices bearing on the safety and security of nuclear installations is divided into 2 volumes bearing on: - Volume I: nuclear installations safety. - nuclear safety and international organizations. - works separation: Finland, Belgium and Federal Republic of Germany. - French organization. - Volume II: security and information. - French nuclear security. - Public information.

  15. Development of nuclear fuel cycle technologies - bases of long-term provision of fuel and environmental safety of nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Solonin, M.I.; Polyakov, A.S.; Zakharkin, B.S.; Smelov, V.S.; Nenarokomov, E.A.; Mukhin, I.V. [SSC, RF, A.A. Bochvar ALL-Russia Research Institute of Inorganic Materials, Moscow (Russian Federation)

    2000-07-01

    To-day nuclear power is one of the options, however, to-morrow it may become the main source of the energy, thus, providing for the stable economic development for the long time to come. The availability of the large-scale nuclear power in the foreseeable future is governed by not only the safe operation of nuclear power plants (NPP) but also by the environmentally safe management of spent nuclear fuel, radioactive waste conditioning and long-term storage. More emphasis is to be placed to the closing of the fuel cycle in view of substantial quantities of spent nuclear fuel arisings. The once-through fuel cycle that is cost effective at the moment cannot be considered to be environmentally safe even for the middle term since the substantial build-up of spent nuclear fuel containing thousands of tons Pu will require the resolution of the safe management problem in the nearest future and is absolutely unjustified in terms of moral ethics as a transfer of the responsibility to future generations. The minimization of radioactive waste arisings and its radioactivity is only feasible with the closed fuel cycle put into practice and some actinides and long-lived fission radionuclides burnt out. The key issues in providing the environmentally safe fuel cycle are efficient processes of producing fuel for NPP, radionuclide after-burning included, a long-term spent nuclear fuel storage and reprocessing as well as radioactive waste management. The paper deals with the problems inherent in producing fuel for NPP with a view for the closed fuel cycle. Also discussed are options of the fuel cycle, its effectiveness and environmental safety with improvements in technologies of spent nuclear fuel reprocessing and long-lived radionuclide partitioning. (authors)

  16. Future nuclear reactors. Evolution of the safety approach; Reacteurs du futur. Evolution de l`approche de surete

    Energy Technology Data Exchange (ETDEWEB)

    Vidard, M. [Electricite de France, 75 - Paris (France). Service Etudes et Projets Thermiques et Nucleaires

    1998-10-01

    The cumulated experience on operating nuclear power plants and the progress of safety knowledge allow to conceive reactors with high standard of safety and with optimized building and operating costs. In this article we present the proceedings followed by electricity producers, the main western nuclear plant builders and safety authorities to warrant the required level of safety. The main safety characteristics of new PWR projects are reviewed. A comparison is made between EPR, SYSTEM 80+, APWR and AP600 projects. Safety is also based on the quality of building and the excellence of operating staff. (A.C.) 16 refs.

  17. Price-Anderson Nuclear Safety Enforcement Program. 1996 Annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

    This first annual report on DOE`s Price Anderson Amendments Act enforcement program covers the activities, accomplishments, and planning for calendar year 1996. It also includes the infrastructure development activities of 1995. It encompasses the activities of the headquarters` Office of Enforcement in the Office of Environment, Safety and Health (EH) and Investigation and the coordinators and technical advisors in DOE`s Field and Program Offices and other EH Offices. This report includes an overview of the enforcement program; noncompliances, investigations, and enforcement actions; summary of significant enforcement actions; examples where enforcement action was deferred; and changes and improvements to the program.

  18. Posiva's application for a decision in principle concerning a disposal facility for spent nuclear fuel. STUK's statement and preliminary safety appraisal

    Energy Technology Data Exchange (ETDEWEB)

    Ruokola, E. [ed.

    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.)

  19. Introduction of the Amendment of IAEA Safety Requirements Reflected Lessons Learned from Fukushima Nuclear Accident

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, Sang-Kyu; Ahn, Hyung-Joon; Kim, Sun-Hae; Cheong, Jae-Hak [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-10-15

    The following five Safety Requirements publications were amended: Governmental, Legal and Regulatory Framework for Safety (GSR Part 1, 2010), Site Evaluation for Nuclear Installations (NS-R-3, 2003), Safety of Nuclear Power Plants: Design (SSR-2/1, 2012), Safety of Nuclear Power Plants: Commissioning and Operation (SSR-2/2, 2011), and Safety Assessment for Facilities and Activities (GSR Part 4, 2009). Figure 1 shows IAEA Safety Standards Categories Major amendments of five Safety Requirements publications were introduced and analyzed in this study. The five IAEA safety requirements publications which are GSR Part 1 and 4, NS-R-3 and SSR-2/1 and 2, were amended to reflect the lesson learned from the Fukushima accident and other operating experiences. Specially, 36 provisions were modified and the new 29 provision with 1 requirement (No. 67: Emergency response facilities on the site) of the SSR-2/1 were established. Since the Fukushima accident happened, a new word, design extension conditions (DECs) which cover substantially the beyond design basis accidents (BDBA), including severe accident conditions, was created and more elaborated by the world nuclear experts. Design extension conditions could include conditions in events without significant fuel degradation and conditions with core melting. Figure 2 shows the range of the DECs. The amendment of the five IAEA safety requirements publications are focused at the prevention of initiating events, which would lead to the DECs, and mitigation of the consequences of DECs by the enhanced defense in depth principle. The following examples of the IAEA requirements to prevent the initiating events are: margins for withstanding external events; margins for avoiding cliff edge effects; safety assessment for multiple facilities or activities at a single site; safety assessment in cases where resources at a facility are shared; consideration of the potential occurrence of events in combination; establishing levels of hazard

  20. Educating Next Generation Nuclear Criticality Safety Engineers at the Idaho National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    J. D. Bess; J. B. Briggs; A. S. Garcia

    2011-09-01

    One of the challenges in educating our next generation of nuclear safety engineers is the limitation of opportunities to receive significant experience or hands-on training prior to graduation. Such training is generally restricted to on-the-job-training before this new engineering workforce can adequately provide assessment of nuclear systems and establish safety guidelines. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) can provide students and young professionals the opportunity to gain experience and enhance critical engineering skills. The ICSBEP and IRPhEP publish annual handbooks that contain evaluations of experiments along with summarized experimental data and peer-reviewed benchmark specifications to support the validation of neutronics codes, nuclear cross-section data, and the validation of reactor designs. Participation in the benchmark process not only benefits those who use these Handbooks within the international community, but provides the individual with opportunities for professional development, networking with an international community of experts, and valuable experience to be used in future employment. Traditionally students have participated in benchmarking activities via internships at national laboratories, universities, or companies involved with the ICSBEP and IRPhEP programs. Additional programs have been developed to facilitate the nuclear education of students while participating in the benchmark projects. These programs include coordination with the Center for Space Nuclear Research (CSNR) Next Degree Program, the Collaboration with the Department of Energy Idaho Operations Office to train nuclear and criticality safety engineers, and student evaluations as the basis for their Master's thesis in nuclear engineering.

  1. Discussion on Fostering Strong Nuclear Safety Culture in Nuclear Power Plants in China%核电企业卓越核安全文化建设和培育

    Institute of Scientific and Technical Information of China (English)

    姜福明

    2011-01-01

    This paper described the most recent development of nuclear safety culture in nuclear industry. nuclear industry Focus areas are recommended to foster a strong nuclear safety culture ( SNSC ) the world in Chinese with the view of our current development, aiming to accelerate the formation of SNSC%介绍了核电界核安全文化的新发展,并结合中国核电界核安全文化现状和实践对卓越核安全文化建设和培育提出了建议,旨在加快核安全文化建设和培育。

  2. People detection in nuclear plants by video processing for safety purpose

    Energy Technology Data Exchange (ETDEWEB)

    Jorge, Carlos Alexandre F.; Mol, Antonio Carlos A., E-mail: calexandre@ien.gov.b, E-mail: mol@ien.gov.b [Instituto de Engenharia Nuclear (IEN/CNEN), Rio de Janeiro, RJ (Brazil); Seixas, Jose M.; Silva, Eduardo Antonio B., E-mail: seixas@lps.ufrj.b, E-mail: eduardo@lps.ufrj.b [Coordenacao dos Programas de Pos-Graduacao de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Eletrica; Cota, Raphael E.; Ramos, Bruno L., E-mail: brunolange@poli.ufrj.b [Universidade Federal do Rio de Janeiro (EP/UFRJ), RJ (Brazil). Dept. de Engenharia Eletronica e de Computacao

    2011-07-01

    This work describes the development of a surveillance system for safety purposes in nuclear plants. The final objective is to track people online in videos, in order to estimate the dose received by personnel, during the execution of working tasks in nuclear plants. The estimation will be based on their tracked positions and on dose rate mapping in a real nuclear plant at Instituto de Engenharia Nuclear, Argonauta nuclear research reactor. Cameras have been installed within Argonauta's room, supplying the data needed. Both video processing and statistical signal processing techniques may be used for detection, segmentation and tracking people in video. This first paper reports people segmentation in video using background subtraction, by two different approaches, namely frame differences, and blind signal separation based on the independent component analysis method. Results are commented, along with perspectives for further work. (author)

  3. Evaluation of the Finnish nuclear safety research program 'SAFIR2010'

    Energy Technology Data Exchange (ETDEWEB)

    2010-07-01

    A panel of three members has been asked by the Ministry of Employment and the Economy (MEE) to evaluate SAFIR2010, the Finnish research program on nuclear power plant safety. The program was established for the period 2007-2010 to help maintain expertise in nuclear safety, to integrate young people into the research in order to help assure the future availability of expertise, and to support international collaborations. The program is directed by a Steering Group, appointed by MEE, with representatives from all organizations involved with nuclear safety in Finland. SAFIR2010 has consisted of approximately 30 projects from year to year that fall into eight subject areas: 1. Organization and human factors 2. Automation and control room 3. Fuel and reactor physics 4. Thermal hydraulics 5. Severe accidents 6. Structural safety of reactor circuit 7. Construction safety 8. Probabilistic safety analysis (PSA) For each of these areas there are Reference Groups that provide oversight of the projects within their jurisdiction. The panel carried out its evaluation by reviewing copies of relevant documents and, during a one-week period 17-22 January 2010, meeting with key individuals. The results of the panel are provided as general conclusions, responses to questions posed by MEE, challenges and recommendations and comments on specific projects in each subject area. The general conclusions reflect the panel's view that SAFIR2010 is meeting its objectives and carrying out quality research. The questions addressed are: (a.) Are the achieved results in balance with the funding? Are the results exploited efficiently in practice? (b.) How well does the expertise cover the field? Is the entire SAFIR2010 programme balanced to all different fields in nuclear safety? Does it raise efficiently new experts? (c.) Have the 2006 evaluation results been implemented successfully into SAFIR2010 program? (d.) Challenges and recommendations. In general the panel was very positive about

  4. Current Ground Test Options for Nuclear Thermal Propulsion (NTP)

    Science.gov (United States)

    Gerrish, Harold P., Jr.

    2014-01-01

    (approximately 1 GW) with a maximum burn time of 1 hour. The concept utilized lessons learned from NF-1. The strategy breaks down the exhaust into parallel paths to allow flexibility with engine size and mass flow of exhaust. Similar to NF-1, the exhaust is slowed down, cooled, filtered of particulates, filtered of noble gases, and then the clean hydrogen is flared to open air. Another concept proposed by Steve Howe (currently Director of the Center for Space Nuclear Research) to simplify the NTP exhaust filtering is to run the hydrogen exhaust into boreholes underground to filter the exhaust. The two borehole site locations proposed are at the NTS and at the Idaho National Laboratory (INL). At NTS, the boreholes are 8' diameter and 1200' deep. The permeability of hydrogen through the soil and its buoyancy will allow it to rise up through the soil and allow the filtering of noble gases and radioactive particulates. The exhaust needs to be cooled to 600C before entering the borehole to avoid soil glazing. Preliminary analysis shows a small buildup of back pressure with time which depends on permeability. Noble gases entering the borehole walls deep can take a long time before reaching the surface. Other factors affecting permeability include borehole pressure, water saturation, and turbulence. Also, a possible need to pump out contaminated water collected at the bottom of the borehole. At INL, the borehole concept is slightly different. The underground borehole has openings to the soil at special depths which have impermeable interbeds above the water table and below the surface to allow the exhaust to travel horizontal between the impermeable layers. Preliminary results indicate better permeability than at NTS. The last option is total containment of the exhaust during the test run. The concept involves slowing down the flow to subsonic in a water cooled diffuser. The hydrogen is burned off in an oxygen rich afterburner with the only products being steam, oxygen, and some noble

  5. Current challenges and opportunities in nonclinical safety testing of biologics.

    Science.gov (United States)

    Kronenberg, Sven; Baumann, Andreas; de Haan, Lolke; Hinton, Heather J; Moggs, Jonathan; Theil, Frank-Peter; Wakefield, Ian; Singer, Thomas

    2013-12-01

    Nonclinical safety testing of new biotherapeutic entities represents its own challenges and opportunities in drug development. Hot topics in this field have been discussed recently at the 2nd Annual BioSafe European General Membership Meeting. In this feature article, discussions on the challenges surrounding the use of PEGylated therapeutic proteins, selection of cynomolgus monkey as preclinical species, unexpected pharmacokinetics of biologics and the safety implications thereof are summarized. In addition, new developments in immunosafety testing of biologics, the use of transgenic mouse models and PK and safety implications of multispecific targeting approaches are discussed. Overall, the increasing complexity of new biologic modalities and formats warrants tailor-made nonclinical development strategies and experimental testing.

  6. Formulating Human Resources Development Strategies for Nuclear R and D, Safety and Security

    Energy Technology Data Exchange (ETDEWEB)

    Min, B. J.; Kim, M. K.; Son, M. Y.

    2010-05-15

    Enforced by the recent launch of the 4th National Power Expansion Plan and the 1st Basic Plan for National Energy Policy with an ambitious goal of achieving 'Low CO2 Emission and Green Growth', a rapid expansion of nuclear technology development has been reemphasized. In addition, the nation, being a potential exporter of nuclear power plants and nuclear technologies strives to explore their exports markets. In response, it is inevitable to set the priority in human resource development (HRD) as nuclear technology development both requires and fosters HRD which in turn, enables to meet the successful implementation of nuclear power expansion. A continuous, consistent and well-managed programme of HRD is crucial to assure continuity over time in the needed capacities, skills and knowledge, and to establish and maintain a cadre of manpower variously trained in different nuclear-related skills and educated in nuclear relevant fields. The objective of the study is to conduct comprehensive quantitative analyses to estimate future human resources requirements, particularly in the field of nuclear R and D, safety and security in order to establish an appropriate long-term nuclear HRD plan

  7. Current Status of Nuclear Medicine Practice in the Middle East.

    Science.gov (United States)

    Paez, Diana; Becic, Tarik; Bhonsle, Uday; Jalilian, Amir R; Nuñez-Miller, Rodolfo; Osso, Joao Alberto

    2016-07-01

    The practice of nuclear medicine (NM) in the Middle East region has experienced an important growth in the last 2 decades and has become crucial in providing healthcare to the region's population of about 395 million people. Even though there are some countries in which the services provided are limited to basic coverage of studies with (99m)Tc and (131)I, most have well-established practices covering most of the available studies in this medical specialty; this is the case in for example, Iran, Israel, Kuwait, Saudi Arabia, and Turkey. According to data provided by the NM professionals in the 17 countries included in the present publication, which was collected by the International Atomic Energy Agency in 2015, the total number of gamma cameras in the region is 910 with an average of 2.3 gamma cameras per million inhabitants. Out of these, 107 cameras, or 12%, are SPECT/CT cameras. There are 194 operating PET/CT scanners, translating to one PET/CT scanner for 2.04 million people on average. The availability of PET/CT scanners in relation to population is the highest in Lebanon and Kuwait, with 2.2 and 1.7 scanners per million people, respectively. There is a total of 628 NM centers in the 17 countries, whereas most NM centers belong to the public healthcare system and in most of the countries are widely spread and not confined exclusively to capital cities. As for the radionuclide therapies, (131)I is used regularly in diagnostic workup as well as in therapeutic applications in all the countries included in this analysis. Only five countries have the capability of assembling (99)Mo-(99m)Tc generators (Egypt, Iran, Saudi Arabia, Israel, and Turkey), and cold kits are produced in several countries. Although there are no capabilities in the region to produce (99)Mo from nuclear reactors, a total of 46 cyclotrons are operated for production of PET radionuclides. The most widely used PET tracer in the region is (18)F-FDG followed by (18)F-NaF; concomitantly, the

  8. Cooperation in Nuclear Waste Management, Radiation Protection, Emergency Preparedness, Reactor Safety and Nuclear Non-Proliferation in Eastern Europe

    Energy Technology Data Exchange (ETDEWEB)

    Dassen, Lars van; Delalic, Zlatan; Ekblad, Christer; Keyser, Peter; Turner, Roland; Rosengaard, Ulf; German, Olga; Grapengiesser, Sten; Andersson, Sarmite; Sandberg, Viviana; Olsson, Kjell; Stenberg, Tor

    2009-10-15

    The Swedish Radiation Safety Authority (SSM) is trusted with the task of implementing Sweden's bilateral assistance to Russia, Ukraine, Georgia, Belarus and Armenia in the fields of reactor safety, nuclear waste management, nuclear non-proliferation as well as radiation protection and emergency preparedness. In these fields, SSM also participates in various projects financed by the European Union. The purpose of this project-oriented report is to provide the Swedish Government and other funding agencies as well as other interested audiences in Sweden and abroad with an encompassing understanding of our work and in particular the work performed during 2008. the activities are divided into four subfields: Nuclear waste management; Reactor safety; Radiation safety and emergency preparedness; and, Nuclear non-proliferation. SSM implements projects in the field of spent nuclear fuel and radioactive waste management in Russia. The problems in this field also exist in other countries, yet the concentration of nuclear and radioactive materials are nowhere higher than in north-west Russia. And given the fact that most of these materials stem from the Cold War era and remain stored under conditions that vary from 'possibly acceptable' to 'wildly appalling' it is obvious that Sweden's first priority in the field of managing nuclear spent fuel and radioactive waste lies in this part of Russia. The prioritisation and selection of projects in reactor safety are established following thorough discussions with the partners in Russia and Ukraine. For specific guidance on safety and recommended safety improvements at RBMK and VVER reactors, SSM relies on analyses and handbooks established by the IAEA in the 1990s. In 2008, there were 16 projects in reactor safety. SSM implements a large number of projects in the field of radiation protection and emergency preparedness. The activities are at a first glance at some distance from the activities covered and

  9. 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...

  10. Nuclear safety: Volume 37, Number 3. Technical progress journal, July--September 1996

    Energy Technology Data Exchange (ETDEWEB)

    Muhlheim, M D [ed.

    1996-09-01

    The seven articles in this journal are divided into the following areas: general safety considerations; design features; operating experiences; U.S. Nuclear Regulatory Commission information and analysis; and recent developments. Proposed rule changes since June 30, 1996 are also included.

  11. 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...

  12. Next Generation Nuclear Plant Structures, Systems, and Components Safety Classification White Paper

    Energy Technology Data Exchange (ETDEWEB)

    Pete Jordan

    2010-09-01

    This white paper outlines the relevant regulatory policy and guidance for a risk-informed approach for establishing the safety classification of Structures, Systems, and Components (SSCs) for the Next Generation Nuclear Plant and sets forth certain facts for review and discussion in order facilitate an effective submittal leading to an NGNP Combined Operating License application under 10 CFR 52.

  13. 75 FR 9196 - Letter From Secretary of Energy Accepting Defense Nuclear Facilities Safety Board (Board...

    Science.gov (United States)

    2010-03-01

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF ENERGY Letter From Secretary of Energy Accepting Defense Nuclear Facilities Safety Board (Board) Recommendation 2009-2 AGENCY: Department of Energy. ACTION: Notice. SUMMARY: The Department of Energy (DOE) is making...

  14. Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W.B.; Passiakos, M.

    1982-06-01

    This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index.

  15. Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author. Vol. 11(1)--Vol. 18(6)

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W.B.; Klein, A.

    1978-04-11

    This index to Nuclear Safety covers articles published in Nuclear Safety, Vol. 11, No. 1 (January-February 1970), through Vol. 18, No. 6 (November-December 1977). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 450 technical articles published in Nuclear Safety in the last eight years are listed in this index.

  16. Index to Nuclear Safety: a technical progress review by chrology, permuted title, and author, Volume 11(1) through Volume 20(6)

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W B; Passiakos, M

    1980-06-01

    This index to Nuclear Safety, a bimonthly technical progress review, covers articles published in Nuclear Safety, Volume II, No. 1 (January-February 1970), through Volume 20, No. 6 (November-December 1979). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 600 technical articles published in Nuclear Safety in the last ten years are listed in this index.

  17. Considerations to the nuclear safety in Mexico; Consideraciones a la seguridad nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Salas M, B. [UNAM, Facultad de Ciencias, Departamento de Fisica, Laboratorio de Analisis Radiologicos de Muestras Ambientales, Ciudad Universitaria, 04510 Mexico D.F. (Mexico)]. e-mail: salasmarb@yahoo.com.mx

    2006-07-01

    The uncertain future of the hydrocarbons like main source of energy, force us to think on the nuclear energy as the suitable substitute that we can inherit to those future generations. Mexico therefore should multiply the number of nuclear power centrals and to be in this way prepared for the new challenges, however, it is necessary and advisable, to restate the mexican nuclear plan that includes mainly the transparency. The 'WANO Report' (World Association of Nuclear Operators - for their initials in English), result of a technical audit to the Nuclear Power station of Laguna Verde (CNLV), it is a polemic topic, because in accordance with David Lochbaum of 'The Union of Concerned Scientists' of the United States of America and of John Large of 'Large and Associates' of the Great Britain, the security in the CNLV is questionable. The pronouncements of concern of Abel J. Gonzalez and Ken E. Brockman, high officials of the International Atomic Energy Agency who took knowledge of diverse irregularities in the CNLV, should be analysis reason for to take actions in pro of the future of the nuclear energy in Mexico. (Author)

  18. 76 FR 13397 - DOE Response to Recommendation 2010-2 of the Defense Nuclear Facilities Safety Board, Pulse Jet...

    Science.gov (United States)

    2011-03-11

    ... Response to Recommendation 2010-2 of the Defense Nuclear Facilities Safety Board, Pulse Jet Mixing at the... Defense Nuclear Facilities Safety Board Recommendation 2010-2, concerning Pulse Jet Mixing at the Waste... Board (Board) Recommendation 2010-2, Pulse Jet Mixing at the Waste Treatment and Immobilization...

  19. 78 FR 47011 - Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

    Science.gov (United States)

    2013-08-02

    ... COMMISSION Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants..., ``Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants.'' This... software elements if those systems include software. This RG is one of six RG revisions addressing...

  20. The effects of solar-geomagnetically induced currents on electrical systems in nuclear power stations

    Energy Technology Data Exchange (ETDEWEB)

    Subudhi, M. [Brookhaven National Lab., Upton, NY (United States); Carroll, D.P. [Florida Univ., Gainesville, FL (United States); Kasturi, S. [MOS, Inc., Melville, NY (United States)

    1994-01-01

    This report presents the results of a study to evaluate the potential effects of geomagnetically induced currents (GICs) caused by the solar disturbances on the in-plant electrical distribution system and equipment in nuclear power stations. The plant-specific electrical distribution system for a typical nuclear plant is modeled using the ElectroMagnetic Transient Program (EMTP). The computer model simulates online equipment and loads from the station transformer in the switchyard of the power station to the safety-buses at 120 volts to which all electronic devices are connected for plant monitoring. The analytical model of the plant`s electrical distribution system is studied to identify the transient effects caused by the half-cycle saturation of the station transformers due to GIC. This study provides results of the voltage harmonics levels that have been noted at various electrical buses inside the plant. The emergency circuits appear to be more susceptible to high harmonics due to the normally light load conditions. In addition to steady-state analysis, this model was further analyzed simulating various plant transient conditions (e.g., loss of load or large motor start-up) occurring during GIC events. Detail models of the plant`s protective relaying system employed in bus transfer application were included in this model to study the effects of the harmonic distortion of the voltage input. Potential harmonic effects on the uniterruptable power system (UPS) are qualitatively discussed as well.

  1. Worldwide advanced nuclear power reactors with passive and inherent safety: What, why, how, and who

    Energy Technology Data Exchange (ETDEWEB)

    Forsberg, C.W.; Reich, W.J.

    1991-09-01

    The political controversy over nuclear power, the accidents at Three Mile Island (TMI) and Chernobyl, international competition, concerns about the carbon dioxide greenhouse effect and technical breakthroughs have resulted in a segment of the nuclear industry examining power reactor concepts with PRIME safety characteristics. PRIME is an acronym for Passive safety, Resilience, Inherent safety, Malevolence resistance, and Extended time after initiation of an accident for external help. The basic ideal of PRIME is to develop power reactors in which operator error, internal sabotage, or external assault do not cause a significant release of radioactivity to the environment. Several PRIME reactor concepts are being considered. In each case, an existing, proven power reactor technology is combined with radical innovations in selected plant components and in the safety philosophy. The Process Inherent Ultimate Safety (PIUS) reactor is a modified pressurized-water reactor, the Modular High Temperature Gas-Cooled Reactor (MHTGR) is a modified gas-cooled reactor, and the Advanced CANDU Project is a modified heavy-water reactor. In addition to the reactor concepts, there is parallel work on super containments. The objective is the development of a passive box'' that can contain radioactivity in the event of any type of accident. This report briefly examines: why a segment of the nuclear power community is taking this new direction, how it differs from earlier directions, and what technical options are being considered. A more detailed description of which countries and reactor vendors have undertaken activities follows. 41 refs.

  2. A comparative study on the effective safety of nuclear technology in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Soh, Young Jin [Daegu University, Daegu (Korea); Kim, Young Pyoung [Korea University, Seoul (Korea); Jung, Yoon Soo [Myoungji University, Seoul (Korea); Chung, Ik Jae; Choi, Byung Sun [Seoul National University, Seoul (Korea)

    2001-12-01

    The main purpose of this research is to analyze Korean perception of nuclear risk in comparison with other technological risks. In order to understand the characteristics of risk perception, the concept of 'effective safety' is clarified and defined. This research also covers such issues as relative riskiness of major risks, risk attitude, risk attribution, behavioral pattern for risky situation, and risk knowledge. A nation-wide survey was conducted for this study with a sample size of 1870. It was based on the purposive quota sampling to compare nuclear risk and other technological risks selected are 6 groups of risk; nuclear risk, environmental risk, traffic risk, chemical materials, industrial safety, and other recent risks. Accross these groups, a total of 25 risks are examined. 52 refs., 14 figs., 125 tabs. (Author)

  3. Development of nuclear power and impacts on public safety and security

    Energy Technology Data Exchange (ETDEWEB)

    Bochmann, H.P.

    1985-07-01

    The author summarizes the contribution of nuclear power to the overall power supply in the FRG, impacts of the nuclear power industry on public safety and security, and the legal instruments available to protect the public. He concludes his discussion of facts and arguments with the following statements: protection against interference or any other harmful actions of third parties aimed against nuclear installations must be devised so as to practically guarantee prevention of sabotage or any acts of terrorism. Preventive measures have to be made with an eye to what is sensible in practice, as perfectionism might have the adverse effect. The available concept of integrated protection and engineered safety, which has been set up in 1977, will be a sufficient means of reacting to near developments and information in a flexible and effective manner.

  4. Climate considerations in long-term safety assessments for nuclear waste repositories.

    Science.gov (United States)

    Näslund, Jens-Ove; Brandefelt, Jenny; Liljedahl, Lillemor Claesson

    2013-05-01

    For a deep geological repository for spent nuclear fuel planned in Sweden, the safety assessment covers up to 1 million years. Climate scenarios range from high-end global warming for the coming 100 000 years, through deep permafrost, to large ice sheets during glacial conditions. In contrast, in an existing repository for short-lived waste the activity decays to low levels within a few tens of thousands of years. The shorter assessment period, 100 000 years, requires more focus on climate development over the coming tens of thousands of years, including the earliest possibility for permafrost growth and freezing of the engineered system. The handling of climate and climate change in safety assessments must be tailor-made for each repository concept and waste type. However, due to the uncertain future climate development on these vast time scales, all safety assessments for nuclear waste repositories require a range of possible climate scenarios.

  5. Climate Considerations in Long-Term Safety Assessments for Nuclear Waste Repositories

    Energy Technology Data Exchange (ETDEWEB)

    Naeslund, Jens-Ove; Brandefelt, Jenny; Claesson Liljedahl, Lillemor [Svensk Kaernbraenslehantering AB, Stockholm (Sweden)], E-mail: jens-ove.naslund@skb.se

    2013-05-15

    For a deep geological repository for spent nuclear fuel planned in Sweden, the safety assessment covers up to 1 million years. Climate scenarios range from high-end global warming for the coming 100 000 years, through deep permafrost, to large ice sheets during glacial conditions. In contrast, in an existing repository for short-lived waste the activity decays to low levels within a few tens of thousands of years. The shorter assessment period, 100 000 years, requires more focus on climate development over the coming tens of thousands of years, including the earliest possibility for permafrost growth and freezing of the engineered system. The handling of climate and climate change in safety assessments must be tailor-made for each repository concept and waste type. However, due to the uncertain future climate development on these vast time scales, all safety assessments for nuclear waste repositories require a range of possible climate scenarios.

  6. Discussion on software aging management of nuclear power plant safety digital control system.

    Science.gov (United States)

    Liang, Huihui; Gu, Pengfei; Tang, Jianzhong; Chen, Weihua; Gao, Feng

    2016-01-01

    Managing the aging of digital control systems ensures that nuclear power plant systems are in adequate safety margins during their life cycles. Software is a core component in the execution of control logic and differs between digital and analog control systems. The hardware aging management for the digital control system is similar to that for the analog system, which has matured over decades of study. However, software aging management is still in the exploratory stage. Software aging evaluation is critical given the higher reliability and safety requirements of nuclear power plants. To ensure effective inputs for reliability assessment, this paper provides the required software aging information during the life cycle. Moreover, the software aging management scheme for safety digital control system is proposed on the basis of collected aging information.

  7. The nuclear law: safety. 2006-2010; Le droit nucleaire: la surete 2006-2010

    Energy Technology Data Exchange (ETDEWEB)

    Bringuier, P. [Montpellier-1 Univ., UMR 5815, 34 (France)

    2010-11-15

    The author discusses the legal evolutions related to nuclear safety between 2006 and 2010. He identifies three main topics of unequal importance. Firstly, he comments the implementation of an international reference framework which has been completed at the European level and which aims at the harmonization of safety and security rules. Secondly, he comments the creation of the French Nuclear Safety Authority (ASN, Autorite de Surete Nucleaire). Thirdly, he comments the recast of the standard framework in order to update the French law with respect to the international reference framework. This leaded to a new distribution of power and authority, to more complete and constraining procedures, and to the definition of procedures for each step of an installation life cycle

  8. Organizational analysis and safety for utilities with nuclear power plants: an organizational overview. Volume 1. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Scott, W.G.; Connor, P.E.

    1983-08-01

    This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. A model is introduced for the purposes of organizing the literature review and showing key relationships among identified organizational factors and nuclear power plant safety. Volume I of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety.

  9. The Nordic nuclear safety research. Report 1994; Nordisk kernesikkerhedsprogram 1994-1997. Rapport for 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-02-01

    This is a report on the first year of the fifth four-year Nordic Nuclear Safety Research (NKS) program (1994-1997). Three major fields of research have been identified: reactor safety; radioactive waste; and environmental impact. A total of seven projects are now under way within that framework. Together with additional financial support from a number of ministries and companies in the nuclear power field, the total NKS budget will be some USD 1.5 million per year. To this should be added contributions in kind by participating organizations, worth at least another USD 2 million per year, without which this program would not be possible. Finland and Sweden presently operate a total of 16 power producing reactors. Denmark, Finland, Norway and Sweden operate research reactors. There is a plant for nuclear fuel production in Sweden. All five Nordic countries have intermediate waste storages. In Finland and Sweden repositories for low and intermediate level waste are in operation, and repositories for spent fuel are being planned. In addition, there are a number of power, research and naval reactors and other nuclear installations in Nordic surroundings, both in Eastern and Western Europe. Hence, nuclear safety, radiation protection, waste management, radioecology and emergency preparedness issues are of common interest to all Nordic countries. These two reactor safety projects constitute a new angle of reactor safety in the NKS perspective: One project (AFA-1) deals with long-lived low and medium level waste in this respect. Environmental impact of radioactive releases is studied in two radioecology projects. Another aspect of environmental impact is emergency preparedness. A separate project, SAM, has been set up to organize, coordinate and follow up the technical and scientific work. (EG).

  10. Managing plutonium in Britain. Current options[Mixed oxide nuclear fuels; Nuclear weapons

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This is the report of a two day meeting to discuss issues arising from the reprocessing of plutonium and production of mixed oxide nuclear fuels in Britain. It was held at Charney Manor, near Oxford, on June 25 and 26, 1998, and was attended by 35 participants, including government officials, scientists, policy analysts, representatives of interested NGO's, journalists, a Member of Parliament, and visiting representatives from the US and Irish governments. The topic of managing plutonium has been a consistent thread within ORG's work, and was the subject of one of our previous reports, CDR 12. This particular seminar arose out of discussions earlier in the year between Dr. Frank Barnaby and the Rt. Hon. Michael Meacher MP, Minister for the Environment. With important decisions about the management of plutonium in Britain pending, ORG undertook to hold a seminar at which all aspects of the subject could be aired. A number of on-going events formed the background to this initiative. The first was British Nuclear Fuels' [BNFL] application to the Environment Agency to commission a mixed oxide fuel [MOX] plant at Sellafield. The second was BNFL's application to vary radioactive discharge limits at Sellafield. Thirdly, a House of Lords Select Committee was in process of taking evidence, on the disposal of radioactive waste. Fourthly, the Royal Society, in a recent report entitled Management of Separated Plutonium, recommended that 'the Government should commission a comprehensive review... of the options for the management of plutonium'. Four formal presentations were made to the meeting, on the subjects of Britain's plutonium policy, commercial prospects for plutonium use, problems of plutonium accountancy, and the danger of nuclear terrorism, by experts from outside the nuclear industry. It was hoped that the industry's viewpoint would also be heard, and BNFL were invited to present a paper, but declined on the grounds that they

  11. Measurement of Nuclear Dependence in Inclusive Charged Current Neutrino Scattering

    Energy Technology Data Exchange (ETDEWEB)

    Tice, Brian George [Rutgers Univ., New Brunswick, NJ (United States)

    2014-01-01

    Neutrino experiments use heavy nuclei (C, Fe, Pb) to achieve necessary statistics. However, the use of heavy nuclei exposes these experiments to the nuclear dependence of neutrino-nucleus cross sections, which are poorly known and difficult to model. This dissertation presents an analysis of the nuclear dependence of inclusive chargedcurrent neutrino scattering using events in carbon, iron, lead, and scintillator targets of the MINERvA detector. MINERvA (Main INjector ExpeRiment for -A) is a few-GeV neutrinonucleus scattering experiment at Fermilab.

  12. The current status of nuclear research reactor in Thailand

    Energy Technology Data Exchange (ETDEWEB)

    Sittichai, C.; Kanyukt, R.; Pongpat, P. [Office of Atomic Energy for Peace, Bangkok (Thailand)

    1998-10-01

    Since 1962, the Thai Research Reactor has been serving for various kinds of activities i.e. the production of radioisotopes for medical uses and research and development on nuclear science and technology, for more than three decades. The existing reactor site should be abandoned and relocated to the new suitable site, according to Thai cabinet`s resolution on the 27 December 1989. The decommissioning project for the present reactor as well as the establishment of new nuclear research center were planned. This paper discussed the OAEP concept for the decommissioning programme and the general description of the new research reactor and some related information were also reported. (author)

  13. On the safety of persons accompanying nuclear medicine patients.

    Science.gov (United States)

    Díaz Barreto, Marlenin; López Bejerano, Gladys M; Varela Corona, Consuelo; Fleitas Estévez, Ileana

    2012-12-01

    The presence of caretakers/comforters during nuclear medicine examinations is relatively common. These caretakers receive higher doses than the general public, who receive only environmental/background exposure. The aim of this research was to know about the doses received by two significant groups of caretakers: comforters of cancer patients (Group I) and mothers of small children (Group II). The patients were scheduled to undergo two different diagnostic studies: Inmuno-Scintigraphy using a monoclonal antibody bound to (99m)Tc (for adults) and Renal Scintigraphy using (99m)Tc-dimercaptosuccinic acid (for children). The average effective doses were 0.27 and 0.29 mSv for Groups I and II, respectively. Additionally, environmental monitoring was performed in the waiting room for injected patients (Room I) and inside the procedure room (Room II). Equivalent environmental doses of 0.28 and 0.24 mSv for Rooms 1 and II, respectively, were found, which are similar to values reported by other authors.

  14. The ORSphere Benchmark Evaluation and Its Potential Impact on Nuclear Criticality Safety

    Energy Technology Data Exchange (ETDEWEB)

    John D. Bess; Margaret A. Marshall; J. Blair Briggs

    2013-10-01

    In the early 1970’s, critical experiments using an unreflected metal sphere of highly enriched uranium (HEU) were performed with the focus to provide a “very accurate description…as an ideal benchmark for calculational methods and cross-section data files.” Two near-critical configurations of the Oak Ridge Sphere (ORSphere) were evaluated as acceptable benchmark experiments for inclusion in the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP Handbook). The results from those benchmark experiments were then compared with additional unmoderated and unreflected HEU metal benchmark experiment configurations currently found in the ICSBEP Handbook. For basic geometries (spheres, cylinders, and slabs) the eigenvalues calculated using MCNP5 and ENDF/B-VII.0 were within 3 of their respective benchmark values. There appears to be generally a good agreement between calculated and benchmark values for spherical and slab geometry systems. Cylindrical geometry configurations tended to calculate low, including more complex bare HEU metal systems containing cylinders. The ORSphere experiments do not calculate within their 1s uncertainty and there is a possibility that the effect of the measured uncertainties for the GODIVA I benchmark may need reevaluated. There is significant scatter in the calculations for the highly-correlated ORCEF cylinder experiments, which are constructed from close-fitting HEU discs and annuli. Selection of a nuclear data library can have a larger impact on calculated eigenvalue results than the variation found within calculations of a given experimental series, such as the ORCEF cylinders, using a single nuclear data set.

  15. Lessons learnt from ITER safety & licensing for DEMO and future nuclear fusion facilities

    CERN Document Server

    Taylor, Neill

    2013-01-01

    One of the strong motivations for pursuing the development of fusion energy is its potentially low environmental impact and very good safety performance. But this safety and environmental potential can only be fully realized by careful design choices. For DEMO and other fusion facilities that will require nuclear licensing, S&E objectives and criteria should be set at an early stage and taken into account when choosing basic design options and throughout the design process. Studies in recent decades of the safety of fusion power plant concepts give a useful basis on which to build the S&E approach and to assess the impact of design choices. The experience of licensing ITER is of particular value, even though there are some important differences between ITER and DEMO. The ITER project has developed a safety case, produced a preliminary safety report and had it examined by the French nuclear safety authorities, leading to the licence to construct the facility. The key technical issues that arose during ...

  16. Patient Participation: Current Knowledge and Applicability to Patient Safety

    OpenAIRE

    Longtin, Yves; Sax, Hugo; Leape, Lucian L; Sheridan, Susan E.; Donaldson, Liam; Pittet, Didier

    2010-01-01

    Patient participation is increasingly recognized as a key component in the redesign of health care processes and is advocated as a means to improve patient safety. The concept has been successfully applied to various areas of patient care, such as decision making and the management of chronic diseases. We review the origins of patient participation, discuss the published evidence on its efficacy, and summarize the factors influencing its implementation. Patient-related factors, such as accept...

  17. SAFIR2014. The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014. Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    Simola, K. (ed.)

    2013-02-15

    The Finnish Nuclear Power Plant Safety Research Programme 2011-2014, SAFIR2014, is a 4-year publicly funded national technical and scientific research programme on the safety of nuclear power plants. The programme is funded by the State Nuclear Waste Management Fund (VYR), as well as other key organisations operating in the area of nuclear energy. The programme provides the necessary conditions for retaining knowledge needed for ensuring the continuance of safe use of nuclear power, for developing new know-how and for participation in international co-operation. The SAFIR2014 Steering Group, responsible of the strategic alignements of the programme, consists of representatives of the Finnish Nuclear Safety Authority (STUK), Ministry of Employment and the Economy (MEE), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oyj (TVO), Fortum Power and Heat Oy (Fortum), Fennovoima Oy, Lappeenranta University of Technology (LUT), Aalto University (Aalto), Finnish Funding Agency for Technology and Innovation (Tekes), Finnish Institute of Occupational Health (TTL) and the Swedish Radiation Safety Authority (SSM). The research programme is divided into nine areas: Man, organisation and society, Automation and control room, Fuel research and reactor analysis, Thermal hydraulics, Severe accidents, Structural safety of reactor circuits, Construction safety, Probabilistic risk analysis (PRA), and Development of research infrastructure. A reference group is assigned to each of these areas to respond for the strategic planning and to supervise the projects in its respective field. Research projects are selected annually based on a public call for proposals. Most of the projects are planned for the entire duration of the programme, but there can also be shorter one- or two-year projects. The annual volume of the SAFIR2014 programme in 2011-2012 has been 9,5-9,9 M euro. Main funding organisations were the State Nuclear Waste Management Fund (VYR) with over 5 M euro and

  18. Review of nuclear power plant safety cable aging studies with recommendations for improved approaches and for future work.

    Energy Technology Data Exchange (ETDEWEB)

    Gillen, Kenneth Todd; Bernstein, Robert

    2010-11-01

    Many U. S. nuclear power plants are approaching 40 years of age and there is a desire to extend their life for up to 100 total years. Safety-related cables were originally qualified for nuclear power plant applications based on IEEE Standards that were published in 1974. The qualifications involved procedures to simulate 40 years of life under ambient power plant aging conditions followed by simulated loss of coolant accident (LOCA). Over the past 35 years or so, substantial efforts were devoted to determining whether the aging assumptions allowed by the original IEEE Standards could be improved upon. These studies led to better accelerated aging methods so that more confident 40-year lifetime predictions became available. Since there is now a desire to potentially extend the life of nuclear power plants way beyond the original 40 year life, there is an interest in reviewing and critiquing the current state-of-the-art in simulating cable aging. These are two of the goals of this report where the discussion is concentrated on the progress made over the past 15 years or so and highlights the most thorough and careful published studies. An additional goal of the report is to suggest work that might prove helpful in answering some of the questions and dealing with some of the issues that still remain with respect to simulating the aging and predicting the lifetimes of safety-related cable materials.

  19. Regulatory oversight report 2007 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2007 ueber die nukleare Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-04-15

    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.

  20. Accidental safety analysis methodology development in decommission of the nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Park, G. H.; Hwang, J. H.; Jae, M. S.; Seong, J. H.; Shin, S. H.; Cheong, S. J.; Pae, J. H.; Ang, G. R.; Lee, J. U. [Seoul National Univ., Seoul (Korea, Republic of)

    2002-03-15

    Decontamination and Decommissioning (D and D) of a nuclear reactor cost about 20% of construction expense and production of nuclear wastes during decommissioning makes environmental issues. Decommissioning of a nuclear reactor in Korea is in a just beginning stage, lacking clear standards and regulations for decommissioning. This work accident safety analysis in decommissioning of the nuclear facility can be a solid ground for the standards and regulations. For source term analysis for Kori-1 reactor vessel, MCNP/ORIGEN calculation methodology was applied. The activity of each important nuclide in the vessel was estimated at a time after 2008, the year Kori-1 plant is supposed to be decommissioned. And a methodology for risk analysis assessment in decommissioning was developed.

  1. The Fukushima Dai-ichi Accident and its implications for the safety of nuclear power

    Science.gov (United States)

    Barletta, William

    2016-05-01

    Five years ago the dramatic events in Fukushima that followed the massive earthquake and subsequent tsunami that struck Japan on March 11, 2011 sharpened the focus of scientists, engineers and general public on the broad range of technical, environmental and societal issues involved in assuring the safety of the world's nuclear power complex. They also called into question the potential of nuclear power to provide a growing, sustainable resource of CO2-free energy. The issues raised by Fukushima Dai-ichi have provoked urgent concern, not only because of the potential harm that could result from severe accidents or from intentional damage to nuclear reactors or to facilities involved in the nuclear fuel cycle, but also because of the extensive economic impact of those accidents and of the measures taken to avoid them.

  2. National nuclear power plant safety research 2007-2010. Proposal for SAFIR2010 framework plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    A country utilising nuclear energy is presumed to possess a sufficient infrastructure to cover the education and research in this field, besides the operating organisations of the plants and a regulatory body. The starting point of public nuclear safety research programmes is that they provide the necessary conditions for retaining the knowledge needed for ensuring the continuance of safe and economic use of nuclear power, for development of new know-how and for participation in international cooperation. In fact, the Finnish organisations engaged in research in this sector have been an important resource which the various ministries, the Radiation and Nuclear Safety Authority (STUK) and the power companies have had at their disposal. Ministry of Trade and Industry appointed a group to write the Framework Plan of the new programme. This report contains a proposal for the general outline of the programme, preliminarily entitled as SAFIR2010 (SAfety of Nuclear Power Plants - Finnish National Research Programme). The plan has been made for the period 2007-2010, but it is based on safety challenges identified for a longer time span as well. Olkiluoto 3, the new nuclear power plant unit under construction has also been taken into account in the plan. The safety challenges set by the existing plants and the new plant unit, as well as the ensuing research needs do, however, converge to a great extent. The research programme is strongly based on the Chapter 7a of the Finnish Nuclear Energy Act. The construction of the new power plant unit will increase the need for experts in the field in Finland. At the same time, the retirement of the existing experts is continuing. These factors together will call for more education and training, in which active research activities play a key role. This situation also makes long-term safety research face a great challenge. The Framework Plan aims to define the important research needs related to the safety challenges. The research into

  3. A Study on the Allowable Safety Factor of Cut-Slopes for Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Myung Soo; Yee, Eric [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2015-10-15

    In this study, the issues of allowable safety factor design criteria for cut-slopes in nuclear facilities is derived through case analysis, a proposed construction work slope design criteria that provides relatively detailed conditions can be applied in case of the dry season and some unclear parts of slope design criteria be modified in case of the rainy season. This safety factor can be further subdivided into two; normal and earthquake factors, a factor of 1.5 is applied for normal conditions and a factor of 1.2 is applied for seismic conditions. This safety factor takes into consideration the effect of ground water and rainfall conditions. However, no criteria for the case of cut-slope in nuclear facilities and its response to seismic conditions is clearly defined, this can cause uncertainty in design. Therefore, this paper investigates the allowable safety factor for cut-slopes in nuclear facilities, reviews conditions of both local and international cut-slope models and finally suggests an alternative method of analysis. It is expected that the new design criteria adequately ensures the stability of the cut-slope to reflect clear conditions for both the supervising and design engineers.

  4. V meeting on results of Research Plan of Nuclear Safety Conseil; V Jornadas sobre Resultados del Plan de Investigacion del CSN

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This book presents the papers presented at the meeting on results of Research Plan of CSN (Nuclear Safety Conseil). The main sessions were : 1.- Nuclear Safety. 2.- Radiation protection and Radioactive wastes. 3.- Riskpercom.

  5. Request for Naval Reactors Comment on Proposed Prometheus Space Flight Nuclear Reactor High Tier Reactor Safety Requirements and for Naval Reactors Approval to Transmit These Requirements to JPL

    Energy Technology Data Exchange (ETDEWEB)

    D. Kokkinos

    2005-04-28

    The purpose of this letter is to request Naval Reactors comments on the nuclear reactor high tier requirements for the PROMETHEUS space flight reactor design, pre-launch operations, launch, ascent, operation, and disposal, and to request Naval Reactors approval to transmit these requirements to Jet Propulsion Laboratory to ensure consistency between the reactor safety requirements and the spacecraft safety requirements. The proposed PROMETHEUS nuclear reactor high tier safety requirements are consistent with the long standing safety culture of the Naval Reactors Program and its commitment to protecting the health and safety of the public and the environment. In addition, the philosophy on which these requirements are based is consistent with the Nuclear Safety Policy Working Group recommendations on space nuclear propulsion safety (Reference 1), DOE Nuclear Safety Criteria and Specifications for Space Nuclear Reactors (Reference 2), the Nuclear Space Power Safety and Facility Guidelines Study of the Applied Physics Laboratory.

  6. Equivalent linear and nonlinear site response analysis for design and risk assessment of safety-related nuclear structures

    Energy Technology Data Exchange (ETDEWEB)

    Bolisetti, Chandrakanth, E-mail: cb76@buffalo.edu [University at Buffalo, The State University of New York, North Campus, 212 Ketter Hall, Amherst, NY 14260 (United States); Whittaker, Andrew S., E-mail: awhittak@buffalo.edu [University at Buffalo, The State University of New York, North Campus, 212 Ketter Hall, Amherst, NY 14260 (United States); Mason, H. Benjamin, E-mail: ben.mason@oregonstate.edu [Oregon State University, 101 Kearney Hall, Corvallis, OR 97331 (United States); Almufti, Ibrahim, E-mail: ibrahim.almufti@arup.com [Advanced Technology + Research, ARUP, 560 Mission Street, Suite 700, San Francisco, CA (United States); Willford, Michael, E-mail: michael.willford@arup.com [Advanced Technology + Research, ARUP, 560 Mission Street, Suite 700, San Francisco, CA (United States)

    2014-08-15

    Highlights: • Performed equivalent linear and nonlinear site response analyses using industry-standard numerical programs. • Considered a wide range of sites and input ground motions. • Noted the practical issues encountered while using these programs. • Examined differences between the responses calculated from different programs. • Results of biaxial and uniaxial analyses are compared. - Abstract: Site response analysis is a precursor to soil-structure interaction analysis, which is an essential component in the seismic analysis of safety-related nuclear structures. Output from site response analysis provides input to soil-structure interaction analysis. Current practice in calculating site response for safety-related nuclear applications mainly involves the equivalent linear method in the frequency-domain. Nonlinear time-domain methods are used by some for the assessment of buildings, bridges and petrochemical facilities. Several commercial programs have been developed for site response analysis but none of them have been formally validated for large strains and high frequencies, which are crucial for the performance assessment of safety-related nuclear structures. This study sheds light on the applicability of some industry-standard equivalent linear (SHAKE) and nonlinear (DEEPSOIL and LS-DYNA) programs across a broad range of frequencies, earthquake shaking intensities, and sites ranging from stiff sand to hard rock, all with a focus on application to safety-related nuclear structures. Results show that the equivalent linear method is unable to reproduce the high frequency acceleration response, resulting in almost constant spectral accelerations in the short period range. Analysis using LS-DYNA occasionally results in some unrealistic high frequency acceleration ‘noise’, which can be removed by smoothing the piece-wise linear backbone curve. Analysis using DEEPSOIL results in abrupt variations in the peak strains of consecutive soil layers

  7. Safety case for the disposal of spent nuclear fuel at Olkiluoto. Complementary considerations 2012

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-12-15

    Complementary Considerations sits within Posiva Oy's Safety Case 'TURVA-2012' report portfolio and has the objective of enhancing confidence in the outcomes of the safety assessment for a spent nuclear fuel repository to be constructed at Olkiluoto, Finland. The main emphasis in this report is on the evidence and understanding that can be gained from observations at the site, including its regional geological environment, and from natural and anthropogenic analogues for the repository, its components and the processes that affect safety. In particular, the report addresses diverse and less quantifiable types of evidence and arguments that are enclosed to enhance confidence in the outcome of the safety assessment. These complementary considerations have been described as evaluations, evidence and qualitative supporting arguments that lie outside the scope of the other reports of the quantitative safety assessment. The experience with natural analogues for the long-term durability of the materials involved and the extent of processes provides high confidence in our understanding of the disposal system and its evolution. For each engineered barrier and key process, there is increasing analogue evidence to support the conceptual models and parameters. Regarding the suitability of the Olkiluoto site to host a spent fuel repository, a number of factors have been identified that indicate the suitability of crystalline host rock in general, and that of the Olkiluoto site in particular. The report also provides radiation background information for the use of complementary indicators, which aid in putting the results of the safety analysis presented in Assessment of Radionuclide Release Scenarios for the Repository System and Biosphere Assessment in a broader perspective to show that the radiation originating from a spent nuclear fuel repository remains in most cases much below natural background radiation or that caused by non-nuclear industries. (orig.)

  8. Safety Management in Non-Nuclear Contexts. Examples from Swedish Railway Regulatory and Company Perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Salo, Ilkka; Svensson, Ola (Risk Analysis, Social and Decision Research Unit, Dept. of Psychology, Stockholm Univ., Stockholm (Sweden))

    2005-06-15

    Nuclear power operations demand safe procedures. In the context of this report, safety management is considered as a key instrument to achieve safety in technology, organization and operations. Outside the area of nuclear operations there exist a number of other technological areas that also demand safe operations. From the perspective of knowledge management, there exists an enormous pool of safety experiences that may be possible to shear or reformulate from one context to another. From this point of view, it seems highly relevant to make efforts to utilize, and try to understand how safety in general is managed in other contexts. There is much to gain from such an approach, not at least from economical, societal, and systems points of views. Because of the vast diversity between technological areas and their operations, a common framework that allow elaboration with common concepts for understanding, must be generated. In preceding studies a number of steps have been taken towards finding such a general framework for modeling safety management. In an initial step a system theoretical framework was outlined. In subsequent steps central concepts from this framework has been applied and evaluated in relation to a number of non-nuclear organizations. The present report brings this intention one step further, and for the first time, a complete analysis of a system consisting of both the regulator and the licensee was carried out, in the above respects. This report focused the Swedish railway system, and the organizations studied were the Swedish Rail Agency (SRA) and SJ (the main rail traffic operator). The data used for this report consisted of various documents about the organizations, and interview data. This report is basically structured around three, more or less, independent studies that are presented in separate chapters. They are: the system theoretical framework that in the following chapters is applied to the two organizations, and one chapter each for the

  9. Safety Management in Non-Nuclear Contexts. Examples from Swedish Railway Regulatory and Company Perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Salo, Ilkka; Svensson, Ola (Risk Analysis, Social and Decision Research Unit, Dept. of Psychology, Stockholm Univ., Stockholm (Sweden))

    2005-06-15

    Nuclear power operations demand safe procedures. In the context of this report, safety management is considered as a key instrument to achieve safety in technology, organization and operations. Outside the area of nuclear operations there exist a number of other technological areas that also demand safe operations. From the perspective of knowledge management, there exists an enormous pool of safety experiences that may be possible to shear or reformulate from one context to another. From this point of view, it seems highly relevant to make efforts to utilize, and try to understand how safety in general is managed in other contexts. There is much to gain from such an approach, not at least from economical, societal, and systems points of views. Because of the vast diversity between technological areas and their operations, a common framework that allow elaboration with common concepts for understanding, must be generated. In preceding studies a number of steps have been taken towards finding such a general framework for modeling safety management. In an initial step a system theoretical framework was outlined. In subsequent steps central concepts from this framework has been applied and evaluated in relation to a number of non-nuclear organizations. The present report brings this intention one step further, and for the first time, a complete analysis of a system consisting of both the regulator and the licensee was carried out, in the above respects. This report focused the Swedish railway system, and the organizations studied were the Swedish Rail Agency (SRA) and SJ (the main rail traffic operator). The data used for this report consisted of various documents about the organizations, and interview data. This report is basically structured around three, more or less, independent studies that are presented in separate chapters. They are: the system theoretical framework that in the following chapters is applied to the two organizations, and one chapter each for the

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

    Energy Technology Data Exchange (ETDEWEB)

    Kahook, S.D.

    1994-04-01

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

  11. Vulnerability, safety and response of nuclear power plants to the hydroclimatic hazards

    Science.gov (United States)

    János Katona, Tamás; Vilimi, András

    2016-04-01

    The Great Tohoku Earthquake and Tsunami, and the severe accident at Fukushima Dai-ichi nuclear power plant 2011 alerted the nuclear industry to danger of extreme rare natural hazards. The subsequent "stress tests" performed by the nuclear industry in Europe and all over the world identifies the nuclear power plant (NPP) vulnerabilities and define the measures for increasing the plant safety. According to the international practice of nuclear safety regulations, the cumulative core damage frequency for NPPs has to be 10-5/a, and the cumulative frequency of early large release has to be 10-6/a. In case of operating plants these annual probabilities can be little higher, but the licensees are obliged to implement all reasonable practicable measures for increasing the plant safety. For achieving the required level of safety, design basis of NPPs for natural hazards has to be defined at the 10-4/a ⎯10-5/a levels of annual exceedance probability. Tornado hazard is some kind of exception, e.g., the design basis annual probability for tornado in the US is equal to 10-7/a. Design of the NPPs shall provide for an adequate margin to protect items ultimately necessary to prevent large or early radioactive releases in the event of levels of natural hazards exceeding those to be considered for design. The plant safety has to be reviewed for accounting the changes of the environmental conditions and natural hazards in case of necessity, but as minimum every ten years in the frame of periodic safety reviews. Long-term forecast of environmental conditions and hazards has to be accounted for in the design basis of the new plants. Changes in hydroclimatic variables, e.g., storms, tornadoes, river floods, flash floods, extreme temperatures, droughts affect the operability and efficiency as well as the safety the NPPs. Low flow rates and high water temperature in the rivers may force to operate at reduced power level or shutdown the plant (Cernavoda NPP, Romania, August 2009). The

  12. Systems Thinking Safety Analysis: Nuclear Security Assessment of Physical Protection System in Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Tae Ho Woo

    2013-01-01

    Full Text Available The dynamical assessment has been performed in the aspect of the nuclear power plants (NPPs security. The physical protection system (PPS is constructed by the cyber security evaluation tool (CSET for the nuclear security assessment. The systems thinking algorithm is used for the quantifications by the Vensim software package. There is a period of 60 years which is the life time of NPPs' operation. The maximum possibility happens as 3.59 in the 30th year. The minimum value is done as 1.26 in the 55th year. The difference is about 2.85 times. The results of the case with time delay have shown that the maximum possibility of terror or sabotage incident happens as 447.42 in the 58th year and the minimum value happens as 89.77 in the 51st year. The difference is about 4.98 times. Hence, if the sabotage happens, the worst case is that the intruder can attack the target of the nuclear material in about one and a half hours. The general NPPs are modeled in the study and controlled by the systematic procedures.

  13. Risks of nuclear energy technology safety concepts of light water reactors

    CERN Document Server

    Kessler, Günter; Schlüter, Franz-Hermann

    2014-01-01

    The book analyses the risks of nuclear power stations. The security concept of reactors is explained. Measures against the spread of radioactivity after a severe accident, accidents of core melting and a possible crash of an air plane on?reactor containment are discussed. The book covers three scientific subjects of the safety concepts of Light Water Reactors: ? A first part describes the basic safety design concepts of operating German Pressurized Water Reactors and Boiling Water Reactors including accident management measures introduced after the reactor accidents of Three Mile Island and Ch

  14. Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

    1982-03-01

    Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and EMTOMB (entombment). The study results are presented in two volumes. Volume 2 (Appendices) contains the detailed data that support the results given in Volume 1, including unit-component data.

  15. About the safety of power transformers in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Petrovan Boiarciuc, M.; Muller, S.; Perigaud, G. [Research Department, SERGI Holding, 186, Avenue du General de Gaulle, 78260 Acheres (France)

    2010-07-01

    Oil-filled transformer explosions are due to electrical arcs occurring in transformer tanks. Within milliseconds, arcs vaporize the surrounding oil and the generated gas is quickly pressurized. The pressure difference between the gas bubble and the surrounding liquid oil generates one dynamic pressure peak which propagates and interacts with the tank. Then, the reflections of the pressure peak build up the static pressure, which rises and leads to the tank rupture since tanks are not designed to withstand such levels of static pressure. This results in dangerous explosions, expensive damages and possible environmental pollution. While protective walls surrounding transformers can contain the explosion and sprinklers can fight the induced fire, the current paper presents a strategy to prevent the transformer tank rupture. Once an electrical fault occurs, the fast depressurization of the tank is induced by quick oil evacuation to a reservoir in order to prevent the tank explosion. To evaluate the efficiency of this strategy, experiments and computer simulations are used. The experiments were performed on large scale transformers equipped with the protection. Besides, simulations of the consequences of an electrical arc occurring in a 200 MVA transformer geometry were run and the pressure maps obtained with and without protection were compared. (authors)

  16. Nuclear Safety Goals and Public Acceptance%核电安全目标与公众接受性

    Institute of Scientific and Technical Information of China (English)

    李朝君; 张春明; 左嘉旭; 陈妍; 付陟玮; 宋维

    2014-01-01

    After Fukushima accident , the international society pays more attention on the safety of nuclear power .Nuclear safety goals have very important impact on the nuclear safety as the criteria of nuclear power plant safety assessment .Public acceptance has important effect on the nuclear power development .Presently , how to improve the safety of the plant and make the public have a better understanding of safety goals is one of the main problems to most of countries in the process of nuclear power expansion .This paper introduces the development of safety goals and the public acceptance of nuclear power expansion ,and discusses how the pub-lic acceptance impact on setting nuclear safety goals and nuclear power expansion .Finally several helpful sug-gestions are made on how to change public acceptance of nuclear power .%安全目标作为核电厂进行安全评价的判定准则,对电厂的安全评价有十分重要的指导作用。公众的接受性对核电的发展有重要影响,提高核电厂的安全性,使公众对安全目标有清楚的认知是发展核电面临的主要问题之一。本文简要介绍安全目标的发展历程,分析公众接受性在核电发展中的作用,讨论公众接受性对制定核电安全目标的影响,提出提高公众接受性的建议。

  17. Comprehensive Nuclear-Test-Ban Treaty: Background and Current Developments

    Science.gov (United States)

    2008-05-28

    considers a U.S. contribution to a global system to monitor events that might violate the CTBT. The FY2008 appropriation was $23.8 million; the FY2009...ratified the CTBT. On December 17, 2007, Representative Tauscher introduced H.Res. 882, “[e] xpressing the sense of the House of Representatives that...Limited, January 13, 2007. 26 “Indian Lawmakers Attack U.S. Nuclear Deal,” Global Security Newswire, November 29, 2007. 27 Kathy Gannon, “New Pakistani

  18. Participation of CIEMAT in 26th annual meeting of the Spanish Nuclear Safety; Participacion del CIEMAT en la 26 reunion anual de la Sociedad Nuclear Espanola

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The book assembles the paper of researches of CIEMAT during the 26th annual meeting of Spanish Nuclear society. The paper were presented during the following sessions: 1. Maintenance and in-service inspection 2. Radioactive wastes 3. Environment 4. R and D management 5. Nuclear Safety 6. Lifetime.

  19. Participation of CIEMAT in 27th annual meeting of the Spanish Nuclear Safety; Participacion del CIEMAT en la 27 Reunion Anual de la Sociedad Nuclear Espanola

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    The book assembles the paper of researches of CIEMAT during the 27th annual meeting of Spanish Nuclear society. The paper were presented during the following sessions: 1. Maintenance and in-service inspection 2. Radioactive wastes. 3. Environment 4. R and D management 5. Nuclear Safety. 6. Lifetime. (Author)

  20. Annual Report To Congress. Department of Energy Activities Relating to the Defense Nuclear Facilities Safety Board, Calendar Year 2003

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2004-02-28

    The Department of Energy (Department) submits an Annual Report to Congress each year detailing the Department’s activities relating to the Defense Nuclear Facilities Safety Board (Board), which provides advice and recommendations to the Secretary of Energy (Secretary) regarding public health and safety issues at the Department’s defense nuclear facilities. In 2003, the Department continued ongoing activities to resolve issues identified by the Board in formal recommendations and correspondence, staff issue reports pertaining to Department facilities, and public meetings and briefings. Additionally, the Department is implementing several key safety initiatives to address and prevent safety issues: safety culture and review of the Columbia accident investigation; risk reduction through stabilization of excess nuclear materials; the Facility Representative Program; independent oversight and performance assurance; the Federal Technical Capability Program (FTCP); executive safety initiatives; and quality assurance activities. The following summarizes the key activities addressed in this Annual Report.

  1. Just in Time DSA-The Hanford Nuclear Safety Basis Strategy

    Energy Technology Data Exchange (ETDEWEB)

    Olinger, S. J.; Buhl, A. R.

    2002-02-26

    The U.S. Department of Energy, Richland Operations Office (RL) is responsible for 30 hazard category 2 and 3 nuclear facilities that are operated by its prime contractors, Fluor Hanford Incorporated (FHI), Bechtel Hanford, Incorporated (BHI) and Pacific Northwest National Laboratory (PNNL). The publication of Title 10, Code of Federal Regulations, Part 830, Subpart B, Safety Basis Requirements (the Rule) in January 2001 imposed the requirement that the Documented Safety Analyses (DSA) for these facilities be reviewed against the requirements of the Rule. Those DSA that do not meet the requirements must either be upgraded to satisfy the Rule, or an exemption must be obtained. RL and its prime contractors have developed a Nuclear Safety Strategy that provides a comprehensive approach for supporting RL's efforts to meet its long term objectives for hazard category 2 and 3 facilities while also meeting the requirements of the Rule. This approach will result in a reduction of the total number of safety basis documents that must be developed and maintained to support the remaining mission and closure of the Hanford Site and ensure that the documentation that must be developed will support: compliance with the Rule; a ''Just-In-Time'' approach to development of Rule-compliant safety bases supported by temporary exemptions; and consolidation of safety basis documents that support multiple facilities with a common mission (e.g. decontamination, decommissioning and demolition [DD&D], waste management, surveillance and maintenance). This strategy provides a clear path to transition the safety bases for the various Hanford facilities from support of operation and stabilization missions through DD&D to accelerate closure. This ''Just-In-Time'' Strategy can also be tailored for other DOE Sites, creating the potential for large cost savings and schedule reductions throughout the DOE complex.

  2. To control the nuclear safety and the radiation protection; Controler la surete nucleaire et la radioprotection

    Energy Technology Data Exchange (ETDEWEB)

    Lacoste, A.C. [Direction Generale de la Surete Nucleaire et de la Radioprotection, 75 - Paris (France); Bordarier, Ph. [Autorite de Surete Nucleaire (ASN), 75 - Paris (France); Saint-Raymond, Ph. [Conseil General des Mines, 75 - Paris (France); Repussard, J. [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Clamart (France); Gouze, J.R. [Apave Groupe, 75 - Paris (France); Degos, L. [Haute Autorite de Sante, 93 - Saint-Denis La Plaine (France); Massart, S.; Wiroth, P.; Thezee, Ch.; Petit, G. [Electricite de France (EDF), 75 - Paris (France); Cahen, B.; Hubert, I.; Wiroth, P.; Thezee, Ch.; Petit, G. [Ministere de l' Ecologie et du Developpement Durable, Direction de la Prevention des Pollutions et des Risques (DPPR), 75 - Paris (France); Kaufer, B. [Organisation for Economic Co-Operation and Development, Nuclear Energy Agency (AEN/OCDE), 75 - Paris (France); Taniguchi, T. [Agence Internationale de l' Energie Atomique (AIEA), Vienna (Austria); Revol, H. [Office Parlementaire d' Evaluation des Choix Scientifiques et Technologiques (OPECST), 75 - Paris (France)

    2005-10-15

    Publishing this dossier, the aim is to present the principles and the variety of issues linked to nuclear safety and radiation protection supervision, and the main strategic choices made to use efficiently and effectively A.S.N. supervision means. A.S.N. is responsible for nuclear safety and radiation protection supervision. A.S.N. has to be itself evaluated and supervised by external bodies. The Parliament Office for Evaluation of Scientific and Technological Options (O.P.E.C.S.T.) supervises it; the foreign peers watch and A.S.N. has to be the object of an international audit conducted by its peers under the leadership of I.A.E.A. by the beginning of 2007. (N.C.)

  3. Handbook of nuclear power plant seismic fragilities, Seismic Safety Margins Research Program

    Energy Technology Data Exchange (ETDEWEB)

    Cover, L.E.; Bohn, M.P.; Campbell, R.D.; Wesley, D.A.

    1983-12-01

    The Seismic Safety Margins Research Program (SSMRP) has a gola to develop a complete fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. As part of this program, calculations of the seismic risk from a typical commercial nuclear reactor were made. These calculations required a knowledge of the probability of failure (fragility) of safety-related components in the reactor system which actively participate in the hypothesized accident scenarios. This report describes the development of the required fragility relations and the data sources and data reduction techniques upon which they are based. Both building and component fragilities are covered. The building fragilities are for the Zion Unit 1 reactor which was the specific plant used for development of methodology in the program. Some of the component fragilities are site-specific also, but most would be usable for other sites as well.

  4. Is current EU food safety law geared up for fighting food fraud?

    NARCIS (Netherlands)

    Meulen, van der Bernd

    2015-01-01

    Malicious intent appears to be a blind spot in European Union (EU) food safety law. The current system of law has been created in reaction to food safety incidents. As a consequence it has been designed to deal with accidental problems not with intentionally deceitful actions of people. The horse

  5. Report transparency and nuclear safety 2007 CEA Saclay; Rapport transparence et securite nucleaire 2007 CEA Saclay

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This report presents the activities of the CEA Center of Saclay for the year 2007. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially two public consultation on release authorizations and the Neurospin installations, the dismantling of the 49 nuclear installation, the shutdown of the learning reactor ULYSSE are detailed. (A.L.B.)

  6. Design and Transient Analysis of Passive Safety Cooling Systems for Advanced Nuclear Reactors

    OpenAIRE

    Galvez, Cristhian

    2011-01-01

    The Pebble Bed Advanced High Temperature Reactor (PB-AHTR) is a pebble fueled, liquid salt cooled, high temperature nuclear reactor design that can be used for electricity generation or other applications requiring the availability of heat at elevated temperatures. A stage in the design evolution of this plant requires the analysis of the plant during a variety of potential transients to understand the primary and safety cooling system response. This study focuses on the performance of the pa...

  7. [Modern airway management--current concepts for more patient safety].

    Science.gov (United States)

    Timmermann, Arnd

    2009-04-01

    Effective and safe airway management is one of the core skills among anaesthesiologists and all physicians involved in acute care medicine. However, failure in airway management is still the most frequent single incidence with the highest impact on patient's morbidity and mortality known from closed claims analyses. The anaesthesiologist has to manage the airway in elective patients providing a high level of safety with as little airway injury and interference with the cardio-vascular system as possible. Clinical competence also includes the management of the expected and unexpected difficult airway in different clinical environments. Therefore, it is the anaesthesiologist's responsibility not only to educate and train younger residents, but also all kinds of medical personnel involved in airway management, e.g. emergency physicians, intensive care therapists or paramedics. Modern airway devices, strategies and educational considerations must fulfill these sometimes diverse and large range requirements. Supraglottic airway devices will be used more often in the daily clinical routine. This is not only due the multiple advantages of these devices compared to the tracheal tube, but also because of the new features of some supraglottic airways, which separate the airway from the gastric track and give information of the pharyngeal position. For the event of a difficult airway, new airway devices and concepts should be trained and applied in daily practice.

  8. Safety Assessment of Low-Contaminated Equipment Dismantling at Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Egidijus Babilas

    2015-01-01

    Full Text Available The decommissioning of nuclear facilities requires adequate planning and demonstration that dismantling and decontamination activities can be conducted safely. Existing safety standards require that an appropriate safety assessment be performed to support the decommissioning plan for each facility (International Atomic Energy Agency, 2006. This paper presents safety assessment approach used in Lithuania during the development of the first dismantling and decontamination project for Ignalina NPP. The paper will mainly focus on the identification and assessment of the hazards raised due to dismantling and decontamination activities at Ignalina Nuclear Power Plant and on the assessment of the nonradiological and radiological consequences of the indicated most dangerous initiating event. The drop of heavy item was indicated as one of most dangerous initiating events for the discussed Ignalina Nuclear Power Plant dismantling and decontamination project. For the analysis of the nonradiological impact the finite element model for the load drop force calculation was developed. The radiological impact was evaluated in those accident cases which would lead to the worst radiological consequences. The assessments results show that structural integrity of the building and supporting columns of building structures will be maintained and radiological consequences are lower than the annual regulatory operator dose limit.

  9. International Nuclear Safety Center database on thermophysical properties of reactor materials

    Energy Technology Data Exchange (ETDEWEB)

    Fink, J.K.; Sofu, T.; Ley, H.

    1997-08-01

    The International Nuclear Safety Center (INSC) database has been established at Argonne National Laboratory to provide easily accessible data and information necessary to perform nuclear safety analyses and to promote international collaboration through the exchange of nuclear safety information. The INSC database, located on the World Wide Web at http://www.insc.anl.gov, contains critically assessed recommendations for reactor material properties for normal operating conditions, transients, and severe accidents. The initial focus of the database is on thermodynamic and transport properties of materials for water reactors. Materials that are being included in the database are fuel, absorbers, cladding, structural materials, coolant, and liquid mixtures of combinations of UO{sub 2}, ZrO{sub 2}, Zr, stainless steel, absorber materials, and concrete. For each property, the database includes: (1) a summary of recommended equations with uncertainties; (2) a detailed data assessment giving the basis for the recommendations, comparisons with experimental data and previous recommendations, and uncertainties; (3) graphs showing recommendations, uncertainties, and comparisons with data and other equations; and (4) property values tabulated as a function of temperature.

  10. Lessons Learned for Space Safety from the Fukushima Nuclear Power Plant Accident

    Science.gov (United States)

    Nogami, Manami; Miki, Masami; Mitsui, Masami; Kawada, Ysuhiro; Takeuchi, Nobuo

    2013-09-01

    On March 11 2011, Tohoku Region Pacific Coast Earthquake hit Japan and caused the devastating damage. The Fukushima Nuclear Power Station (NPS) was also severely damaged.The Japanese NPSs are designed based on the detailed safety requirements and have multiple-folds of hazard controls to the catastrophic hazards as in space system. However, according to the initial information from the Tokyo Electric Power Company (TEPCO) and the Japanese government, the larger-than-expected tsunami and subsequent events lost the all hazard controls to the release of radioactive materials.At the 5th IAASS, Lessons Learned from this disaster was reported [1] mainly based on the "Report of the Japanese Government to the IAEA Ministerial Conference on Nuclear Safety" [2] published by Nuclear Emergency Response Headquarters in June 2011, three months after the earthquake.Up to 2012 summer, the major investigation boards, including the Japanese Diet, the Japanese Cabinet and TEPCO, published their final reports, in which detailed causes of this accident and several recommendations are assessed from each perspective.In this paper, the authors examine to introduce the lessons learned to be applied to the space safety as findings from these reports.

  11. Progress and goals for INMM ASC N15 consensus standard ""Administrative practices for the determination and reporting of results of non-destructive assay measurements of nuclear material in situ for safeguards nuclear criticality safety and other purposes

    Energy Technology Data Exchange (ETDEWEB)

    Bracken, David S [Los Alamos National Laboratory; Lamb, Frank W [UNWIN CORPORATION

    2009-01-01

    This paper will discuss the goals and progress to date on the development of INMM Accredited Standard Committee (ASC) N15 consensus standard Administrative Practices for the Determination and Reporting of Results of Non-Destructive Assay Measurements of Nuclear Material in situ for Safeguards, Nuclear Criticality Safety, and Other Purposes. This standard will define administrative practices in the areas of data generation and reporting of NDA assay of holdup deposits with consideration of the stakeholders of the reported results. These stakeholders may include nuclear material accounting and safeguards, nuclear criticality safety, waste management, health physics, facility characterization, authorization basis, radiation safety, and site licensing authorities. Stakeholder input will be solicited from interested parties and incorporated during the development of the document. Currently only one consensus standard exists that explicitly deals with NDA holdup measurements: ASTM C1455 Standard Test Method for Nondestructive Assay of Special Nuclear Material Holdup Using Gamma-Ray Spectroscopic Methods. The ASTM International standard emphasizes the activities involved in actually making measurements, and was developed by safeguards and NDA experts. This new INMM ASC N15 standard will complement the existing ASTM international standard. One of the largest driving factors for writing this new standard was the recent emphasis on in situ NDA measurements by the safeguards community due to the Defense Nuclear Facility Safety Board (DNFSB) recommendation 2007-1 on in situ NDA measurements. Specifically, DNFSB recommendation 2007-1 referenced the lack of programmatic requirements for accurate in situ measurements and the use of measurement results for compliance with safety based requirements. That being the case, this paper will also discuss the progress made on the Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 2007-1 Safety-Related In Situ

  12. Regulatory oversight report 2011 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2011 zur nuklearen Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-06-15

    The Swiss Federal Nuclear Safety Inspectorate ENSI, acting as the regulatory body of the Swiss Confederation, 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. ENSI ensures that the facilities comply with regulations and operate according to the law. Its regulatory responsibilities also include the transport of radioactive materials to and from nuclear facilities and the preparations for a deep geologic repository for nuclear waste. It maintains its own emergency organisation, which is an integral part of a national emergency structure. Building on the legislative framework, ENSI also formulates and updates its own guidelines. It provides the public with information on particular events and findings in nuclear facilities. In 2011, all five nuclear power reactors in Switzerland (Beznau Units 1 and 2, Muehleberg, Goesgen and Leibstadt) were operated safely and ENSI concluded that they had complied with their approved operating conditions. There were 27 reportable events in the nuclear power plants in Switzerland: 7 at Beznau, 5 at Goesgen, 11 at Leibstadt und 4 at Muehleberg. On the international INES scale of 0 to 7, ENSI rated 26 events as Level 0. One event, at the Muehleberg nuclear power plant, was rated as INES Level 1. This related to a potential blockage of the emergency water intake system in the event of extreme flooding. The operator BKW shut down the Muehleberg plant ahead of the scheduled maintenance date and upgraded the system. ZWILAG consists of several interim storage halls, a conditioning plant and a plasma plant (incineration/melting plant). At the end of 2011, the cask storage hall contained 34 transport/storage casks with fuel assemblies and vitrified residue packages

  13. Current Status of Imaging Physics and Instrumentation In Nuclear Medicine

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hee Joung [Institute of Health Science, Yonsei University, Seoul (Korea, Republic of)

    2008-04-15

    Diagnostic and functional imaging device have been developed independently. The recognition that combining of these two devices can provide better diagnostic outcomes by fusing anatomical and functional images. The representative examples of combining devices would be PET/CT and SPECT/CT. Development and their applications of animal imaging and instrumentation have been very active, as new drug development with advanced imaging device has been increased. The development of advanced imaging device resulted in researching and developing for detector technology and imaging systems. It also contributed to develop a new software, reconstruction algorithm, correction methods for physical factors, image quantitation, computer simulation, kinetic modeling, dosimetry, and correction for motion artifacts. Recently, development of MRI and PET by combining them together was reported. True integration of MRI and PET has been making the progress and their results were reported. The recent status of imaging and instrumentation in nuclear medicine is reported in this paper.

  14. Results and current trends of nuclear methods used in agriculture

    Energy Technology Data Exchange (ETDEWEB)

    Horacek, P. (Ceskoslovenska Komise pro Atomovou Energii, Prague)

    1983-11-01

    The significance is evaluated of nuclear methods for agricultural research. The number of breeds induced by radiation mutations is increasing. The main importance of radiation mutation breeding consists in obtaining sources of the desired genetic properties for further hybridization. Radiostimulation is conducted with the aim of increasing yields. The irradiation of foods has not substantially increased worldwide. Very important is the irradiation of excrements and sludges which after such inactivation of pathogenic microorganisms may be used as humus-forming manure or as feed additives. In some countries the method is successfully being used of sexual sterilization for eradication of insect pests. The application of labelled compounds in the nutrition, physiology and protection of plants, farm animals and in food hygiene makes it possible to acquire new and accurate knowledge very quickly. Radioimmunoassay is a highly promising method in this respect. Labelling compounds with the stable /sup 15/N isotope is used for the research of nitrogen metabolism.

  15. Extraction and use of historical extreme climate databases for nuclear power plants safety assessment

    Science.gov (United States)

    Hamdi, Yasser; Bertin, Xavier; Bardet, Lise; Duluc, Claire-Marie; Rebour, Vincent

    2015-04-01

    Safety assessments of nuclear power plants (NPPs) related to natural hazards are a matter of major interest to the nuclear community in France and many European countries. Over the past fewer decades, France has experienced many of these events such as heat waves (2003 and 2006), heavy snowstorms (1958, 1990 and 1992), storms which have given rise to heavy rain and severe floods (1992, 1999, 2010), strong straight-line wind and extreme marine surges (1987, 1999 and 2010) much larger than the other local observations (outliers). These outliers had clearly illustrated the potential to underestimate the extreme surges calculated with the current statistical methods. The estimation of extreme surges then requires the use of a statistical analysis approach having a more solid theoretical framework and using more reliable databases for the assessment of hazards to design NPPs to low or extremely low probabilities of failure. These databases can be produced by collecting historical information (HI) about severe climatic events occurred over short and long timescales. As a matter of fact, natural hazards such as heat waves, droughts, floods, severe storms and snowstorms have affected France and many European countries since the dawn of time. These events would have been such horrific experiences that if they really occurred, there would be unmistakable traces of them. They must have left clues. These catastrophic events have been unforgettably engraved in people's minds and many of them have been traced in archives and history textbooks. The oldest events have certainly left clues and traces somewhere in the geological layers of the earth or elsewhere. The construction of the historical databases and developing probabilistic approaches capable of integrating them correctly is highly challenging for the scientific community (Translating these geological clues to historical data to build historical databases that can be used by the statistical models is a different

  16. Analysis and insights from a dynamical model of nuclear plant safety risk

    Energy Technology Data Exchange (ETDEWEB)

    Hess, Stephen M. [Electric Power Research Institute, 30 Bethel Road, Glen Mills, PA 19342 (United States)]. E-mail: shess@epri.com; Albano, Alfonso M. [School of Economics and Social Sciences, Singapore Management University, 90 Stamford Road, Singapore 178903 (Singapore); Gaertner, John P. [Electric Power Research Institute, 1300 Harris Boulevard, Charlotte, NC 28262 (United States)

    2007-01-15

    In this paper, we expand upon previously reported results of a dynamical systems model for the impact of plant processes and programmatic performance on nuclear plant safety risk. We utilize both analytical techniques and numerical simulations typical of the analysis of nonlinear dynamical systems to obtain insights important for effective risk management. This includes use of bifurcation diagrams to show that period doubling bifurcations and regions of chaotic dynamics can occur. We also investigate the impact of risk mitigating functions (equipment reliability and loss prevention) on plant safety risk and demonstrate that these functions are capable of improving risk to levels that are better than those that are represented in a traditional risk assessment. Next, we analyze the system response to the presence of external noise and obtain some conclusions with respect to the allocation of resources to ensure that safety is maintained at optimal levels. In particular, we demonstrate that the model supports the importance of management and regulator attention to plants that have demonstrated poor performance by providing an external stimulus to obtain desired improvements. Equally important, the model suggests that excessive intervention, by either plant management or regulatory authorities, can have a deleterious impact on safety for plants that are operating with very effective programs and processes. Finally, we propose a modification to the model that accounts for the impact of plant risk culture on process performance and plant safety risk. We then use numerical simulations to demonstrate the important safety benefits of a strong risk culture.

  17. Nuclear safety enhancement of the Instrumentation and Control System at TRIGA SSR 14 MW-Romania

    Energy Technology Data Exchange (ETDEWEB)

    Preda, Marin; Ciocanescu, Marin; Mugurel Ana, Emil; Barbalata, Eugenia [Institute for Nuclear Research, Pitesti (Romania)

    2008-10-29

    In order to comply with the IAEA safety standards and national regulations and to enhance the nuclear safety at TRIGA SSR 14 MW Romanian reactor in 2006 has began a process of instrumentation and control system modifications. By taking account of the operation experience and IAEA guides, the basic requirement for instrumentation and control system modification is the separation between safety and operating components in order to decrease the human error consequences and avoid the common cause failures. Beside that system modernization consists in TRIGA 14 MW console replacement. New instrumentation and control system consists in: - a new reactor operation console, that contains all the necessary modules for reactor operation and parameter display, - three racks for control system that contains all the necessary modules for safety parameter measurement and in scram logic the required redundancy, data acquisition, annunciators, - a terminal boundary rack for connections between field transducers and control room equipments. Modernization did not cover any sensor replacement but keep the actual scram logic and enhance the reactor safety features. The instrumentation and control system is designed, manufactured by INVAP Argentina and will be delivered, installed and tested by the end of 2008. Following to these activities safety documentation will be completed and issued to National Regulatory Body in order to obtain the operation license. Financially the Project is supported by IAEA Vienna and Romanian Government in the framework of a technical cooperation program. (authors)

  18. Processes and Procedures for Application of CFD to Nuclear Reactor Safety Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Richard W. Johnson; Richard R. Schultz; Patrick J. Roache; Ismail B. Celik; William D. Pointer; Yassin A. Hassan

    2006-09-01

    estimates of the flow and energy transport as applied to nuclear reactor safety. However, it is expected that these practices and procedures will require updating from time to time as research and development affect them or replace them with better procedures. The practices and procedures are categorized into five groups. These are: 1.Code Verification 2.Code and Calculation Documentation 3.Reduction of Numerical Error 4.Quantification of Numerical Uncertainty (Calculation Verification) 5.Calculation Validation. These five categories have been identified from procedures currently required of CFD simulations such as those required for publication of a paper in the ASME Journal of Fluids Engineering and from the literature such as Roache [1998]. Code verification refers to the demonstration that the equations of fluid and energy transport have been correctly coded in the CFD code. Code and calculation documentation simply means that the equations and their discretizations, etc., and boundary and initial conditions used to pose the fluid flow problem are fully described in available documentation. Reduction of numerical error refers to practices and procedures to lower numerical errors to negligible or very low levels as is reasonably possible (such as avoiding use of first-order discretizations). The quantification of numerical uncertainty is also known as calculation verification. This means that estimates are made of numerical error to allow the characterization of the numerical

  19. Current trends in safety testing and toxicological research

    Science.gov (United States)

    Zbinden, G.

    1982-06-01

    The paper reviews current concepts of toxicological evaluation of new drugs and other chemicals. Instead of completing a predetermined check-list toxicologists now consider the potential adverse effects of the substances under actual conditions of use. They then design experimental models which have a high probability to predict the toxic effects. Moreover, the enhanced susceptibilities of special risk populations is more and more taken into consideration.

  20. Safety of nuclear installations. An international comparison; Sicherung kerntechnischer Anlagen. Ein internationaler Vergleich

    Energy Technology Data Exchange (ETDEWEB)

    Renner, Andrea; Diwes, Andreas; Reingardt, Martin [Westinghouse Electric Germany GmbH (Germany)

    2010-05-15

    Safeguarding of nuclear power plants against disruptive actions or other external hazards is part of the plant design and presumption of an operation license. The general principle is defense in depth involving different security zones with separate barriers. The safeguards for nuclear installations are organized in three areas of responsibility: governmental measures (police, military), technical (detectors, scanners, illuminations, camera tracking, concrete barriers) and personnel measures (access control, security personnel, alarm) of the operating company. International responsibilities results from the treaty on the non-proliferation of nuclear weapons and several IAEA documents. The authors discuss the national regulations in Germany, Switzerland, United Kingdom and USA. Older NPPs that are not in compliance with actual safety standards will be a topic of increasing importance.

  1. Study of different fitness functions with safety restriction for nuclear reactor reload problem using QDPSO

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Paulo C. de, E-mail: paulocaixeta@poli.ufrj.br [Universidade Federal do Rio de Janeiro (UFRJ), Rio de Janeiro, RJ (Brazil). Departamento de Engenharia Nuclear; Lima, Alan M.M. de; Schirru, Roberto, E-mail: alan@lmp.ufrj.br, E-mail: schirru@lmp.ufrj.br [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    Nuclear Reactor Reload Problem (NRRP) is a classical problem in Nuclear Engineering that has been studied for more than 40 years, which focuses on the economics and safety of the Nuclear Power Plant (NPP). This problem consists in searching for the best loading pattern of fuel assemblies (FA) in the core, aiming to determine the permutation of fuel assemblies that optimizes the uranium utilization, with fitness function evaluated according to specific criteria and methods of nuclear reactor physics, such as the maximum mean power peak and the boron concentration. In this article will be presented different methodologies to obtain a representative fitness function for NRRP, where Quantum particle Swarm optimization (QPSO) was used to determine which one gives the best array of fuel assemblies that will make the maximum EFPD (Effective Full Power Days) with the least computational effort. In this approach, as well as others in literature, was not used Burnable Poison in the simulations and the results will be compared in relation of the maximization of the cycle length considering the boron concentration yield by the reactor physics code, to make sure that the configuration is valid from a safety point of view. This paper was based on Angra 1's seventh reload cycle. (author)

  2. Verification of Safety Margins of Battery Banks Capacity of Class 1E DC System in a Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Lukman, Abdulrauf [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Zhu, Oon-Pyo [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-10-15

    According to Ref 'Station blackout (SBO) is generally a plant condition with complete loss of all alternating current (AC) power from off-site sources, from the main generator and from standby AC power sources important to safety to the essential and nonessential switchgear buses. Direct current (DC) power supplies and uninterruptible AC power supplies may be available as long as batteries can supply the loads, alternate AC power supplies are available'. The above IAEA document indicated the importance of batteries during SBO. Prior to the Fukushima accident, most batteries might be designed with coping capability of four hours. However, the accident showed the need for the coping capability to be increased to at least eight hours. The purpose of this research is to verify the safety capacity margin of the nuclear qualified battery banks of class 1E DC system and test the response to SBO using the load profile of a Korean design nuclear power plant (NPP). The capacity margins of class 1E batteries of DC power system batteries in a nuclear power plant were determined using the load profile of the plant. It was observed that if appropriate manufacturer Kt data are not available, the accuracy of the battery capacity might not be accurately calculated. The result obtained shows that the batteries have the coping capability of two hours for channel A and B, and eight hours for channel C and D. Also capacity margin as show in figure show a reasonable margin for each batteries of the DC system.

  3. Safety indices and their application to nuclear waste management safety assessment

    Energy Technology Data Exchange (ETDEWEB)

    Voss, J.W.

    1979-04-01

    Thirteen indices have been examined to determine their potential applicability to operational waste management safety assessment. Two waste streams are presented on a normalized basis. These are the packaged spent fuel from the once-through fuel cycle and solidified high-level waste from a coprocessed UO/sub 2/--PuO/sub 2/ fuel cycle. Seven of the indices are then calculated for a hypothetical surface storage scenario of the two wastes. The indices are examined on a consistent basis to identify any biases built into them, and to determine the sensitivities of each to various waste situations. The two waste streams are then compared on the basis of the indices to extend the understanding of the analysis techniques. The results of the analysis fall into two categories, index evaluation and fuel cycle waste comparison. Only five of the indices are determined to be applicable to operational waste management safety assessment. The remainder are rejected either because they require very detailed input data; they are specifically designed for geologic isolation; they are extremely controversial in their application; or because they are particularly sensitive to a few specific radionuclides. The waste stream comparison yields three results: (1) the solidified high-level waste from the coprocessed UO/sub 2/--PuO/sub 2/ fuel cycle may be potentially less hazardous than the packaged spent fuel from the once-through fuel cycle; (2) the removal of actinides, and especially plutonium, from spent fuel may reduce the potent hazard associated with the waste; and (3) after one million years of decay, the packaged spent fuel and solidified high-level waste are nearly the same on a hazard potential basis.

  4. Safety Analysis Report for Packaging (SARP): ATMX-500 Railcar nuclear packaging

    Energy Technology Data Exchange (ETDEWEB)

    Griffin, J.F. Peterson, J.B.; Edling, D.A.; Blauvelt, R.K.

    1977-07-08

    A Safety Analysis Report for Packaging (SARP) is described that makes available to all potential users the technical specifications and limits pertinent to the modification and use of the ATMX Railcars for which the Department of Transportation has issued Special Permit No. 5948. The SARP includes discussions of structural integrity, thermal resistance, radiation shielding and radiological safety, nuclear criticality safety, and quality control. Much of the information was previously published in a similar report. A complte physical and technical description of the package is presented. The packaging cnsists of a specially modified ATMX Series 500 Railcar loaded with DOT Specification steel drums or fiberglass coated plywood boxes. The results of the nuclear criticality safety analysis provide the maximum quantities of each fissile isotope which may be shipped as Fissile Class I in 30- and 55-gal drums. A limit of 5 g/ft/sup 3/ was established for wooden boxes. Design and development considerations regarding the packaging concept and modification of the ATMX-500 Railcar are presented. Tables, dimensional sketches, sequential photographs of the structural modifications, technical references, loading and shipping guidelines, and results of Mound Laboratory's experience in using this container are included. An internal review of this SARP was performed in compliance with the requirements of ERDA Manual Chapter 5201-Part V.

  5. Reliability study: digital engineered safety feature actuation system of Korean Standard Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Sudarno [National Nuclear Energy Agency, Batan (Indonesia); Kang, H. G.; Jang, S. C.; Eom, H. S.; Ha, J. J. [KAERI, Taejon (Korea, Republic of)

    2003-04-01

    The usage of digital Instrumentation and Control (I and C) in a nuclear power plant becomes more extensive, including safety related systems. The PSA application of these new designs are very important in order to evaluate their reliability. In particular, Korean Standard Nuclear Power Plants (KSNPPs), typically Ulchin 5 and 6 (UCN 5 and 6) reactor units, adopted the digital safety-critical systems such as Digital Plant Protection System (DPPS) and Digital Engineered Safety Feature Actuation System (DESFAS). In this research, we developed fault tree models for assessing the unavailability of the DESFAS functions. We also performed an analysis of the quantification results. The unavailability results of different DESFAS functions showed that their values are comprised from 5.461E-5 to 3.14E-4. The system unavailability of DESFAS AFAS-1 is estimated as 5.461E-5, which is about 27% less than that of analog system if we consider the difference of human failure probability estimation between both analyses. The results of this study could be utilized in risk-effect analysis of KSNPP. We expect that the safety analysis result will contribute to design feedback.

  6. Safety Analysis Report for Packaging (SARP): ATMX-500 Railcar nuclear packaging

    Energy Technology Data Exchange (ETDEWEB)

    Griffin, J.F. Peterson, J.B.; Edling, D.A.; Blauvelt, R.K.

    1977-07-08

    A Safety Analysis Report for Packaging (SARP) is described that makes available to all potential users the technical specifications and limits pertinent to the modification and use of the ATMX Railcars for which the Department of Transportation has issued Special Permit No. 5948. The SARP includes discussions of structural integrity, thermal resistance, radiation shielding and radiological safety, nuclear criticality safety, and quality control. Much of the information was previously published in a similar report. A complte physical and technical description of the package is presented. The packaging cnsists of a specially modified ATMX Series 500 Railcar loaded with DOT Specification steel drums or fiberglass coated plywood boxes. The results of the nuclear criticality safety analysis provide the maximum quantities of each fissile isotope which may be shipped as Fissile Class I in 30- and 55-gal drums. A limit of 5 g/ft/sup 3/ was established for wooden boxes. Design and development considerations regarding the packaging concept and modification of the ATMX-500 Railcar are presented. Tables, dimensional sketches, sequential photographs of the structural modifications, technical references, loading and shipping guidelines, and results of Mound Laboratory's experience in using this container are included. An internal review of this SARP was performed in compliance with the requirements of ERDA Manual Chapter 5201-Part V.

  7. Implementation of external hazards in Probabilistic Safety Assessment for nuclear power plants

    Science.gov (United States)

    Kumar, Manorma; Klug, Joakim; Raimond, Emmanuel

    2015-04-01

    The paper will focus on the discussion on implementation of external hazards in the probabilistic safety assessment (PSA) methods for the extreme external hazards mainly focused on Seismic, Flooding, Meteorological Hazards (e.g. Storm, Extreme temperature, snow pack), Biological infestation, Lightening hazards, Accidental Aircraft crash and man- made hazards including natural external fire and external explosion. This will include discussion on identification of some good practices on the implementation of external hazards in Level 1 PSA, with a perspective of development of extended PSA and introduction of relevant modelling for external hazards in an existing Level 1 PSA. This paper is associated to the European project ASAMPSAE (www.asampsa.eu) which gathers more than 30 organizations (industry, research, safety control) from Europe, US and Japan and which aims at identifying some meaningful practices to extend the scope and the quality of the existing probabilistic safety analysis developed for nuclear power plants.

  8. Robotic and nuclear safety for an automated/teleoperated glove box system

    Energy Technology Data Exchange (ETDEWEB)

    Domning, E.E. (Lawrence Livermore National Lab., CA (United States)); McMahon, T.T.; Sievers, R.H. (Science Applications International Corp., Pleasanton, CA (United States))

    1991-09-01

    Lawrence Livermore National Laboratory (LLNL) is developing a fully automated system to handle the processing of special nuclear materials (SNM). This work is performed in response to the new goals at the Department of Energy (DOE) for hazardous waste minimization and radiation dose reduction. This fully automated system, called the automated test bed (ATB), consists of an IBM gantry robot and automated processing equipment sealed within a glove box. While the ATB is a cold system, we are designing it as a prototype of the future hot system. We recognized that identification and application of safety requirements early in the design phase will lead to timely installation and approval of the hot system. This paper identifies these safety issues as well as the general safety requirements necessary for the safe operation of the ATB. 4 refs., 2 figs.

  9. Challenges in developing human resources for nuclear safety in South Africa

    Energy Technology Data Exchange (ETDEWEB)

    Tsatsi, Louisa [National Nuclear Regulator, PO BOX 7106, 00046 Centurion (South Africa)

    2008-07-01

    Challenges in developing Human Resources for nuclear safety in South Africa ESKOM Holding Limited which is the South African Government owned utility, operates over 10 power stations. The total installed is about 40 GW, and nuclear contributes only 6 percent. The existing nuclear power station, Koeberg NPP, is comprised of two 900 MW(e) units at the South African west coast near Cape Town. The South African Government has a policy to increase the share of nuclear in the generation mix from 6 percent to 15 percent before the year 2020. The challenge is that there have been a 'greying' of nuclear experts and a shrinking of nuclear engineering and science departments. As a consequence of this, ESKOM has realized that a large number of young engineers and scientists would have to be recruited and then trained in South Africa and abroad. Some people, especially high performers in the industry are continually looking for new challenges and opportunities and though it is important in the nuclear industry to retain these key staff members it have proved to be a serious challenge. The nuclear industry had to consider their national training infrastructures and the South African government in partnership with ESKOM, NECSA and PBMR has started a process of funding university chairs in reactor engineering and allied subjects. These departments undertake research and provide training for the South African nuclear industry. The recruitment process has initially involved the transfer of personnel from ESKOM, NECSA as well as direct recruitment from the market. The primary recruitment process going forward will be from universities and other Further Education Training (FET) institutions with a focus on ESKOM and PBMR providing the specific nuclear training. In this regard, both ESKOM and PBMR provide bursaries, project work and other assistance to selected candidates. Upon completion of studies, the specific training is provided both in-house and with partner national

  10. Safety doctrine synthesis for nuclear submarines construction and operation; Sintese de doutrina de seguranca para projeto e operacao de submarinos nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Guimaraes, Leonam dos Santos; Veiga, Jorge Pinheiro da Costa [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), SP (Brazil). E-mail: leosg@uol.com.br; Brinati, Hernani Luiz [Sao Paulo Univ., SP (Brazil). Escola Politecnica. Dept. de Engenharia Naval

    2000-07-01

    The paper consists in an abstract of the thesis with the same title. This thesis intended to organize and to systematize a Global Safety Doctrine applicable to future national Nuclear Attack Submarines (SSN) considering both nuclear and naval aspects. This doctrine has the form of a set of basic principles, general criteria, specific requirements, design verification process procedures for construction and operation inspection, aiming the assurance of a high level of safety pattern to these warships. Consequently the doctrine would form a consistent and coherent basis for Nuclear Safety Authority (NSA) evaluate the social acceptability of SSN life cycle risks, considering the proposed Safety Objectives, in order to contribute to its competent decisions on submarine licensing. (author)

  11. Nuclear safety research in HGF 2012; Fortschrittsbericht 2012. Programm 'Nukleare Sicherheitsforschung' Helmholtz-Gemeinschaft

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2013-06-15

    After the events at the Japanese nuclear power plant of Fukushima Daiichi, the German Federal government decided that Germany will give up electricity generation from nuclear power within a decade. The last reactor will be disconnected from the power grid in 2022. Helping to make this opt-out safe is one of the duties of the Helmholtz Association with its Nuclear Safety Research Program within the Energy Research Area. Also the demolition of nuclear power plants and the repository problem will keep society, and thus also research, busy for a number of decades to come. Giving up electricity production from nuclear power thus must not mean giving up the required nuclear technology competences. In the fields of reactor safety, demolition, final storage, radiation protection, and crisis management, in critical support of international developments, and for competent evaluation of nuclear facilities around Germany, these competences will be in demand far beyond the German opt-out. This is the reason why the final report by the Ethics Committee on 'Safe Energy Supply' emphasizes the importance of nuclear technology research. Close cooperation on national, European and international levels is indispensable in this effort. Also nuclear safety research in the Helmholtz Association is aligned with the challenges posed by the opt-out of the use of nuclear power. It is important that the high competences in the areas of plant safety and demolition, handling of radioactive waste, and safe final storage as well as radiation protection be preserved. The Nuclear Safety Research Program within the Energy Research Area of the Helmholtz Association therefore will continue studying scientific and technical aspects of the safety of nuclear reactors and the safety of nuclear waste management. These research activities are provident research conducted for society and must be preserved for a long period of time. The work is closely harmonized with the activities of the partners

  12. Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol 11, No. 1 through Vol. 16, No. 6

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W.B.; Klein, A.

    1976-04-01

    This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970) through Vol. 16, No. 6 (Nov.-Dec. 1975). Included in the index is a chronological list of articles (including abstract) followed by both a KWIC index and an Author Index. Nuclear Safety is a bimonthly technical progress review prepared by the Nuclear Safety Information Center and covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 300 technical articles in the last six years of publication.

  13. The Nuclear Safety Council's Instruction IS-30 on program requirements of fire protection at nuclear power plants; La instruccion IS-30 del consejo de Seguridad Nuclear sobre requisitos del programa de proteccion contraincendios en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Peco, J.

    2015-07-01

    The Nuclear Safety Councils Instrumentation IS-30 is the standard that establishes the fire protection program requirements for the Spanish nuclear power plants with operating license in order to satisfy the two fire protection objectives, which are the adoption of the defense-in-depth principle for fire protection and, by fire area confinement, to ensure that one train of components needed to achieve and maintain the safe shutdown conditions is free of fire damage, and that radioactive liberation is minimized. (Author)

  14. Review of decision methodologies for evaluating regulatory actions affecting public health and safety. [Nuclear industry site selection

    Energy Technology Data Exchange (ETDEWEB)

    Hendrickson, P.L.; McDonald, C.L.; Schilling, A.H.

    1976-12-01

    This report examines several aspects of the problems and choices facing the governmental decision maker who must take regulatory actions with multiple decision objectives and attributes. Particular attention is given to the problems facing the U.S. Nuclear Regulatory Commission (NRC) and to the decision attribute of chief concern to NRC, the protection of human health and safety, with emphasis on nuclear power plants. The study was undertaken to provide background information for NRC to use in refining its process of value/impact assessment of proposed regulatory actions. The principal conclusion is that approaches to rationally consider the value and impact of proposed regulatory actions are available. These approaches can potentially improve the decision-making process and enable the agency to better explain and defend its decisions. They also permit consistent examination of the impacts, effects of uncertainty and sensitivity to various assumptions of the alternatives being considered. Finally, these approaches can help to assure that affected parties are heard and that technical information is used appropriately and to the extent possible. The principal aspects of the regulatory decision problem covered in the report are: the legal setting for regulatory decisions which affect human health and safety, elements of the decision-making process, conceptual approaches to decision making, current approaches to decision making in several Federal agencies, and the determination of acceptable risk levels.

  15. SAFIR2010. The Finnish research programme on nuclear power plant safety 2007-2010. Interim report

    Energy Technology Data Exchange (ETDEWEB)

    Puska, E.K. (ed.)

    2009-02-15

    Major part of Finnish public research on nuclear power plant safety during the years 2007-2008 has been carried out in the SAFIR2010 programme. The steering group of SAFIR2010 consists of representatives from Radiation and Nuclear Safety Authority (STUK), Ministry of Employment and the Economy (MEE), VTT Technical Research Centre of Finland (VTT), Teollisuuden Voima Oyj (TVO), Fortum Power and Heat Oyj, Fortum Nuclear Services Oy (Fortum), Tekes - the Finnish Funding Agency for Technology and Innovation (Tekes), Helsinki University of Technology (TKK) and Lappeenranta University of Technology (LUT). In addition to representatives of these organisations, the Steering Group has permanent experts from the Swedish Radiation Safety Authority (SSM) and Fennovoima Oy (Fennovoima). SAFIR2010 research programme is divided in eight research areas that are Organisation and human, Automation and control room, Fuel and reactor physics, Thermal hydraulics, Severe accidents, Structural safety of reactor circuit, Construction safety, and Probabilistic Safety Analysis (PSA). Research projects of the programme are chosen on the basis of annual call for proposals. The annual volume of the SAFIR2010 programme in 2007-2008 has been 6,3-6,7 M euro and approximately 50 person years. Main funding organisations in 2007-2008 were State Waste Management Fund VYR with 2,7-3,0 M euro and VTT with 2,4-2,5 M euro annually. In 2008 research was carried out in 30 projects. The research in the programme has been carried out primarily by VTT Technical Research Centre of Finland. Other research units responsible for the projects solely or in co-operation with other institutions include Lappeenranta University of Technology, Helsinki University of Technology, Tampere University of Technology, Fortum Nuclear Services Oy, Finnish Institute of Occupational Health and Finnish Meteorological Institute. In addition, there have been a few minor subcontractors in some projects. The programme management

  16. SAFIR2010. The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010. Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Puska, E.K.; Suolanen, V. (eds.)

    2011-02-15

    Major part of Finnish public research on nuclear power plant safety during the years 2007-2010 has been carried out in the SAFIR2010 programme. The steering group of SAFIR2010 consisted of representatives from Radiation and Nuclear Safety Authority (STUK), Ministry of Employment and the Economy (MEE), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oyj (TVO), Fortum Power and Heat Oyj, Fortum Nuclear Services Oy (Fortum), Finnish Funding Agency for Technology and Innovation (Tekes), Aalto University School of Science and Technology (Aalto, former Helsinki University of Technology) and Lappeenranta University of Technology (LUT). In addition to representatives of these organisations, the Steering Group had permanent experts from the Swedish Radiation Safety Authority (SSM) and Fennovoima Oy (Fennovoima). SAFIR2010 research programme was divided in eight research areas that were Organisation and human, Automation and control room, Fuel and reactor physics, Thermal hydraulics, Severe accidents, Structural safety of reactor circuit, Construction safety, and Probabilistic Safety Analysis (PSA). Research projects of the programme were chosen on the basis of annual call for proposals. The annual volume of the SAFIR2010-programme in 2007-2010 has been 6,5-7,1 M euro and approximately 50 person years. Main funding organisations in 2007-2010 have been the State Waste Management Fund VYR with 2,7-3,0 M euro and VTT with 2,4-2,7 M euro annually. In 2010 research was carried out in 33 projects. The research in the programme has been carried out primarily by VTT Technical Research Centre of Finland. Other research units responsible for the projects solely or in co-operation with other institutions include Lappeenranta University of Technology, Aalto University (previously Helsinki University of Technology), Tampere University of Technology, Fortum Power and Heat Oy (previously Fortum Nuclear Services Oy), Finnish Institute of Occupational Health and Finnish

  17. Determining safety criteria for reinforced concrete structures of power plants taking the example of a nuclear power plant with RBMK

    Directory of Open Access Journals (Sweden)

    Nikolayev Valery

    2016-01-01

    Full Text Available The paper shows how safety criteria of nuclear power plants with reactor RBMK can be defined based on analytical, numerical and mixed calculation methods using data about strength characteristics of materials with the course of time.

  18. New and recently finalised activities within the NKS Programmes for Nordic cooperation on nuclear reactor safety and emergency preparedness

    DEFF Research Database (Denmark)

    Andgren, Karin; Andersson, Kasper Grann; Magnússon, Sigurður M.

    2015-01-01

    Over the years, NKS has provided funding for hundreds of research activities in fields comprising reactor safety, decommissioning, nuclear and radiological emergency preparedness, and management of radioactive waste. Advanced technologies and methods developed under the NKS framework have been used...

  19. Therapeutic radionuclides in nuclear medicine: current and future prospects.

    Science.gov (United States)

    Yeong, Chai-Hong; Cheng, Mu-hua; Ng, Kwan-Hoong

    2014-10-01

    The potential use of radionuclides in therapy has been recognized for many decades. A number of radionuclides, such as iodine-131 ((131)I), phosphorous-32 ((32)P), strontium-90 ((90)Sr), and yttrium-90 ((90)Y), have been used successfully for the treatment of many benign and malignant disorders. Recently, the rapid growth of this branch of nuclear medicine has been stimulated by the introduction of a number of new radionuclides and radiopharmaceuticals for the treatment of metastatic bone pain and neuroendocrine and other malignant or non-malignant tumours. Today, the field of radionuclide therapy is enjoying an exciting phase and is poised for greater growth and development in the coming years. For example, in Asia, the high prevalence of thyroid and liver diseases has prompted many novel developments and clinical trials using targeted radionuclide therapy. This paper reviews the characteristics and clinical applications of the commonly available therapeutic radionuclides, as well as the problems and issues involved in translating novel radionuclides into clinical therapies.

  20. Somatic cell nuclear transfer cloning: practical applications and current legislation.

    Science.gov (United States)

    Niemann, H; Lucas-Hahn, A

    2012-08-01

    Somatic cloning is emerging as a new biotechnology by which the opportunities arising from the advances in molecular genetics and genome analysis can be implemented in animal breeding. Significant improvements have been made in SCNT protocols in the past years which now allow to embarking on practical applications. The main areas of application of SCNT are: Reproductive cloning, therapeutic cloning and basic research. A great application potential of SCNT based cloning is the production of genetically modified (transgenic) animals. Somatic cell nuclear transfer based transgenic animal production has significant advances over the previously employed microinjection of foreign DNA into pronuclei of zygotes. This cell based transgenesis is compatible with gene targeting and allows both, the addition of a specific gene and the deletion of an endogenous gene. Efficient transgenic animal production provides numerous opportunities for agriculture and biomedicine. Regulatory agencies around the world have agreed that food derived from cloned animals and their offspring is safe and there is no scientific basis for questioning this. Commercial application of somatic cloning within the EU is via the Novel Food regulation EC No. 258/97. Somatic cloning raises novel questions regarding the ethical and moral status of animals and their welfare which has prompted a controversial discussion in Europe which has not yet been resolved.