WorldWideScience

Sample records for convention on nuclear safety

  1. 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

  2. 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.

  3. 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.

  4. 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.

  5. Convention on Nuclear Safety. Second national report on the implementation by france of the obligations of the Convention; Convention sur la surete nucleaire. Deuxieme rapport national sur la mise en oeuvre par la France des obligations de la Convention

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-09-15

    The first national report on the implementation by france of the obligation under the Convention is structured along its Articles. the french Nuclear safety Authority ensured the co ordination of the report, with contributions from other regulators and nuclear operators. this report was distributed at the middle of April 2003 to the other Contracting party (on 3 november to 14, 2003 at the IAEA headquarters. (author)

  6. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-15

    Switzerland signed the Convention on Nuclear Safety (CNS). In accordance with Article 5 of CNS, Switzerland has submitted 4 country reports for Review Meetings of Contracting Parties. This 5{sup th} report by the Swiss Federal Nuclear Safety Inspectorate (ENSI) provides an update on compliance with CNS obligations. The report attempts to give appropriate consideration to issues that aroused particular interest at the 4{sup th} Review Meeting. It starts with general political information on Switzerland, a brief history of nuclear power and an overview of Swiss nuclear facilities. This is followed by a comprehensive overview of the status of nuclear safety in Switzerland (as of July 2010) which indicates how Switzerland complies with the key obligations of the Convention. ENSI updated a substantial proportion of its guidelines which are harmonised with the safety requirements of the Western European Nuclear Regulators Association (WENRA) based on IAEA Safety Standards. On 1{sup st} January 2009, ENSI became formally independent of the Swiss Federal Office of Energy. It is now a stand-alone organisation controlled by its own management board. Switzerland recently started a process to select a site for the disposal of radioactive waste in deep geological formations. The first generation of NPPs in Switzerland has been the subject of progressive back-fitting. The second generation of NPPs incorporated various safety and operating improvements in their initial design. All Swiss NPPs have undergone the safety review process required under the Convention and have incorporated the improvements identified in the respective safety review reports. The Swiss policy of continuous improvements to NPPs ensures a high level of safety. The legislation and regulatory framework for nuclear installations is well established. It provides the formal basis for the supervision and the continuous improvement of nuclear installations. The Nuclear Energy Act and its ordinance came into force

  8. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-15

    Switzerland signed the Convention on Nuclear Safety (CNS). In accordance with Article 5 of CNS, Switzerland has submitted 4 country reports for Review Meetings of Contracting Parties. This 5{sup th} report by the Swiss Federal Nuclear Safety Inspectorate (ENSI) provides an update on compliance with CNS obligations. The report attempts to give appropriate consideration to issues that aroused particular interest at the 4{sup th} Review Meeting. It starts with general political information on Switzerland, a brief history of nuclear power and an overview of Swiss nuclear facilities. This is followed by a comprehensive overview of the status of nuclear safety in Switzerland (as of July 2010) which indicates how Switzerland complies with the key obligations of the Convention. ENSI updated a substantial proportion of its guidelines which are harmonised with the safety requirements of the Western European Nuclear Regulators Association (WENRA) based on IAEA Safety Standards. On 1{sup st} January 2009, ENSI became formally independent of the Swiss Federal Office of Energy. It is now a stand-alone organisation controlled by its own management board. Switzerland recently started a process to select a site for the disposal of radioactive waste in deep geological formations. The first generation of NPPs in Switzerland has been the subject of progressive back-fitting. The second generation of NPPs incorporated various safety and operating improvements in their initial design. All Swiss NPPs have undergone the safety review process required under the Convention and have incorporated the improvements identified in the respective safety review reports. The Swiss policy of continuous improvements to NPPs ensures a high level of safety. The legislation and regulatory framework for nuclear installations is well established. It provides the formal basis for the supervision and the continuous improvement of nuclear installations. The Nuclear Energy Act and its ordinance came into force

  10. 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.

  11. 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

  12. Development of the national report of the Mexican United States for the Convention on Nuclear Safety of the IAEA; Desarrollo del informe nacional de los Estados Unidos Mexicanos para la Convencion sobre seguridad nuclear del OIEA

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz L, P. [Jefe del Area de Ingenieria, Departamento de Evaluacion, Gerencia de Seguridad Nuclear, Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Mexico D.F. (Mexico)

    2006-07-01

    In this work the content of the National Report of the Mexican United States in it revision 2 is presented, which was presented for it exam by the member countries of the Convention on Nuclear Safety, in April, 2005. The conclusion of this Report, with base in the existent objective evidence, is that the Laguna Verde Central continues maintaining a level of similar safety to that of other nuclear power plants of its type, not existing conditions at the moment that they can be identified as adverse for a sure operation and that, therefore, plans don't exist to advance the closing of this installation, before the end of its useful life. The questions that the member countries formulated to the Report of Mexico, the answers that were provided to these questions, as well as the conclusions of the 3 Exam Meeting of April, 2005 are also included. The next National Report, in it revision 3, it will cover the period from the January 1, 2004 to December 31, 2006, it was developed from January to August, 2007, it delivered to the IAEA on September of the same year and it was presented in the IAEA Headquarters (IAEA) in the 4 Exam Meeting on April, 2008. (Author)

  13. 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.

  14. 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.

  15. Convention on Nuclear Safety - CNS. Report by the government of the Federal Republic of Germany for the sixth review conference in March/April 2014; Uebereinkommen ueber nukleare Sicherheit. Bericht der Regierung der Bundesrepublik Deutschland fuer die Sechste Ueberpruefungstagung im Maerz/April 2014

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-01

    The report by the government of the Federal Republic of Germany for the sixth review conference (Convention on Nuclear Safety - CNS) in March/April 2014 covers the following issues: reappraisal of nuclear energy in the Federal Republic of Germany; measures as consequence of the reactor accident in the nuclear power plant Fukushima; safety regulations; execution of the IRRS follow-up mission in Germany; safety management and technical qualification of the occupational personnel; safety surveillance; radiation protection, overview on important safety topics; events and incidents larger INES 0. Assessment of the existing nuclear facilities; progress and changes since 2011; future activities.

  16. 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.

  17. Convention on Nuclear Safety - CNS. Report by the government of the Federal Republic of Germany for the seventh review conference in March/April 2017; Uebereinkommen ueber nukleare Sicherheit. Bericht der Regierung der Bundesrepublik Deutschland fuer die Siebte Ueberpruefungstagung im Maerz/April 2017

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2016-06-22

    The CNS (Convention on Nuclear Safety) report by the government of the Federal Republic of Germany for the seventh review conference in March/April 2017 covers the following topics: Summary of the most important results since the sixth review conference: existing nuclear facilities, frame for legislation and execution, licensing system, regulatory authority, governmental organizations, responsibility of the licensee, priority of safety, financing and personnel, human factors, quality assurance, safety assessment, radiation protection, emergency preparedness, site selection for nuclear facilities, design and construction, operation.

  18. 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.

  19. 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.

  20. 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).

  1. Adoption of protocols to amend the Paris convention on third party liability in the field of nuclear energy and the Brussels convention supplementary to the Paris convention

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S. W.; Jang, K. H.; Oh, B. J.; Song, J. M.; Jung, M. M.; Kim, H. J. [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

    2004-07-01

    To keep in line with the world-wide tendency to strengthen the nuclear third party liability system after the Chernobyl accident, the Protocols to amend the Paris Convention on Third Party Liability in the Field of Nuclear Energy and the Brussels Convention Supplementary to the Paris Convention was adopted on 12 February, 2004. The most important feature of the revised Paris Convention is an increase in the nuclear operator's liability amount from 15 million SDRs to a new minimum of 700 million Euros. For the additional compensation to those provided by the domestic liability regime, the revised Brussels Supplementary Convention will maintain its basic three-tier compensation system but with significantly increased amounts(As a result the total amount to be compensated according to the three tiers will be 15 billions Euros). The protocols to amend the Paris Convention on Third Party Liability in the Field of Nuclear Energy will come into force when ratified by two thirds of the Signatory States, and the protocol to amend the Brussels Convention Supplementary to the Paris Convention will come into force when ratified by all the Brussels Supplementary Convention Signatory States.

  2. 75 FR 43945 - Convention on Supplementary Compensation for Nuclear Damage Contingent Cost Allocation

    Science.gov (United States)

    2010-07-27

    ... Convention on Supplementary Compensation for Nuclear Damage Contingent Cost Allocation AGENCY: Department of... for Nuclear Damage Contingent Cost Allocation'') (42 U.S.C. 17373). Section 934 implements the... (e.g., nuclear reactors, fuel storage facilities) as a means to evaluate items based on...

  3. 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.).

  4. 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...

  5. 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

  6. 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.).

  7. National Report presented by the Mexican United States to satisfy the compromises of the Nuclear Safety Convention; Informe Nacional que presentan los Estados Unidos Mexicanos para satisfacer los compromisos de la Convencion de Seguridad Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    National Commission of Nuclear Safety and Safeguards, Mexico City (Mexico); Federal Commission for Electricity, Mexico City (Mexico)

    1998-12-31

    In order to satisfy to the compromises derived of the ratification by part of the Mexican Government for the Nuclear Safety Convention it is presented this National Report which is based on the directives proposed as a result of the preparatory meetings held in the IAEA Headquarters in the city of Vienna, Austria. This National Report represents a document summary and activities realized at present in relation with the only nuclear facility in Mexico: the Nuclear Power Plant in Laguna Verde, Veracruz. This report consists of two parts: In the first one it is described how have been satisfied each one of the compromises. The second one talks about the Laws and Regulations on nuclear activities in the country. (Author)

  8. 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.

  9. [ILO conventions on occupational safety and health with reference to ratification status of Japan].

    Science.gov (United States)

    Takahashi, K; Okubo, T

    1995-07-01

    This paper grouped together recent ILO conventions relevant to occupational safety and health (OSH) in order to clarify their characteristics and form an overview. There are 13 such conventions adopted by ILO during the period 1960-1993. Each of these conventions have distinct goals to cover respective areas of OSH, which was contrasted with each other. Conventions are subject to ratification, thus the ratification status of Japan was statistically compared to that of ILO and OECD member states. As at June 1993, Japan ratified three of such conventions, which was slightly higher than the average number ratified by all ILO member states and ranked 11th among 24 OECD member states. The relative ratification status of Japan on ILO Conventions fared better with those relevant to OSH than others. ILO Conventions are inter-related by reference and note, thus ratification of basic conventions such as C. 155 (Occupational Safety and Health Convention) and C. 148 (Working Environment Convention), neither of which is ratified by Japan, should be prioritized to further promote ratification status in the OSH area.

  10. 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.

  11. Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. Fourth National Report on Compliance with the Joint Convention Obligations. France; Convention commune sur la surete de la gestion du combustible use et sur la surete de la gestion des dechets radioactifs. Quatrieme rapport national sur la mise en oeuvre des obligations de la Convention commune. France

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-09-15

    The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, hereinafter referred to as the 'Joint Convention', is the result of international discussions that followed the adoption of the Convention on Nuclear Safety, in 1994. France signed the Joint Convention at the General Conference of the International Atomic Energy Agency (IAEA) held on 29 September 1997, the very first day the Joint Convention was opened for signature. She approved it on 22 February 2000 and filed the corresponding instruments with the IAEA on 27 April 2000. The Joint Convention entered into force on 18 June 2001. For many years, France has been taking an active part in the pursuit of international actions to reinforce nuclear safety and considers the Joint Convention to be a key step in that direction. The fields covered by the Joint Convention have long been part of the French approach to nuclear safety. This report is the fourth of its kind. It is published in accordance with Article 32 of the Joint Convention and presents the measures taken by France to meet each of her obligations set out in the Convention. The facilities and radioactive materials covered by the Joint Convention are much diversified in nature and are controlled in France by different regulatory authorities (see Section E). Over and above a specific threshold of radioactive content, a facility is referred to as a 'basic nuclear facility' (installation nucleaire de base - INB) and placed under the control of the French Nuclear Safety Authority (Autorite de surete nucleaire - ASN). Below that threshold and provided that the facility involved falls under a category of the nomenclature of classified facilities for other purposes than their radioactive materials, any facility may be considered as a 'classified facility on environmental-protection grounds' (installation classee pour la protection de l'environnement - ICPE) and placed under the

  12. 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)

  13. 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…

  14. International law problems for realisation of the IAEA conventions on notification and assistance in the case of a nuclear accident

    Energy Technology Data Exchange (ETDEWEB)

    Petrov, M.M.

    1993-12-31

    The Chernobyl accident underscored the need for an early warning system and international assistance plan in case of a nuclear accident. Shortly after Chernobyl, two conventions were adopted under the auspices of the IAEA. The convention on Early Notification of a Nuclear Accident, in force since 1986, establishes an early warning system for all nuclear accidents whose effects might cross national boundaries. Under the convention on Assistance in the Case of a Nuclear accident or radiological Emergency,in force since 1987, countries must facilitate prompt assistance in case of a nuclear accident or radiological emergency, to minimize it`s consequences. Issues with the conventions are described.

  15. 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)

  16. 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.

  17. The Nuclear Safety Convention - does it confirm existing German law, and update international law?; Die Nukleare Sicherheitskonvention - Bestaetigung deutschen und Fortschreibung internationalen Rechts?

    Energy Technology Data Exchange (ETDEWEB)

    Lindemann, C. [Bundesministerium fuer Umwelt, Naturschutz und Reaktorsicherheit, Bonn (Germany)

    1995-12-31

    Some selected examples are discussed that are intended to answer the question of whether the NSC in its essence represents a development in confirmation of existing German nuclear law, and whether, assuming its coming into effect, this Convention will mean a step forward in the development of international law. The author examines the value of this codification of international law as such, and some of the obligations and standards such as retrofitting measures or shutdown of reactors below safety standard, and continues with briefly discussing the relationship between the NSC and nuclear liability law, the planned provisions for radiological protection in Art. 15, and the obligations for transboundary notification of safety-relevant events. These stipulations are analysed in comparison to existing international law, and with a view to their implementation under German law. Some provisions of the NSC that are based on standards of international technical guidance are compared with German regulatory guides. (orig./HP) [Deutsch] Anhand ausgewaehlter Beispiele wird geprueft, ob die NSC im Kern eine Bestaetigung des deutschen Atomrechts darstellt und ob sie - ihr Inkrafttreten unterstellt - einen Fortschritt in der Entwicklung des Voelkerrechts bewirkt. Untersucht werden der Wert dieser Kodifizierung an sich, die Verpflichtung zu Nachruestung und ggfs. Schliessung unsicherer Reaktoren in Artikel 6, in knapper Form des Verhaeltnis von NSC und Nuklearhaftungsrecht, die Strahlenschutzvorschrift in Artikel 15 sowie eine Reihe von grenzueberschreitenden Informationspflichten. Dabei wird auch ein Vergleich mit derzeit geltendem Voelkerrecht vorgenommen und die Umsetzung bzw. Umsetzungsmoeglichkeit im deutschen Recht beruecksichtigt. Schliesslich werden einige Vorschriften der NSC, die auf internationalen technischen Regelwerken beruhen, mit deutschem Recht abgeglichen. (orig./HP)

  18. 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

  19. 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)

  20. 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.

  1. 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,

  2. Liability for nuclear damage: an international perspective. Reflections on the revision of the Vienna Convention

    Energy Technology Data Exchange (ETDEWEB)

    Lopuski, J.

    1993-12-31

    This book deals with deals of the complex issues of liability and compensation for nuclear damage which have been considered in the course of the work of the IAEA concerning the revision of the Vienna Convention on nuclear liability. It presents, in an orderly way, personal reflections of its author based on his experience gathered in years 1989-1992 when participating in this work. Necessarily it contains in some of its parts references to documents of the IAEA Standing Committee on Nuclear Liability; these documents because of their length could not be reproduced. Consequently these parts may not be fully intelligible for those who have not participated in or closely followed the Committee`s work. The IAEA work on liability for nuclear damage was initiated in the wake of the impact made on the world`s public opinion by the Chernobyl incident and its transboundary effects; issues of international state liability and full compensation have been raised. But humanitarian ideas have quickly been confronted with cold calculations of the cost of financial protection for victims and an open unwillingness of some nuclear states has been manifested. After three years of discussions no wide consensus could be reached on some basic issues, such as: relationship between international state and civil liability regimes, structure of international legislation, concept of nuclear damage, limits of compensation, role of public funds or jurisdiction. The author presents his approach to these controversial issue, trying to provide at the same time a theoretical outline for the future international legislation on nuclear liability. (author).

  3. 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.)

  4. 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

  5. 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

  6. 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.

  7. 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.

  8. 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)

  9. 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.

  10. 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.)

  11. 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.

  12. 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.

  13. 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.

  14. 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

    An organizational evaluation plays a key role in the monitoring, as well as controlling and steering, of the organizational safety culture. If left unattended, organizations have a tendency to gradually drift into a condition where they have trouble identifying their vulnerabilities and mechanisms or practices that create or maintain these vulnerabilities. The aim of an organizational evaluation should be to promote increased understanding of the sociotechnical system and its changing vulnerabilities. Evaluation contributes to organizational development and management. Evaluations are used in various situations, but when the aim is to learn about possible new vulnerabilities, identify organizational reasons for problems, or prepare for future challenges, the organization is most open to genuine surprises and new findings. It is recommended that organizational evaluations should be conducted when - there are changes in the organizational structures - new tools are implemented - when the people report increased workplace stress or a decreased working climate - when incidents and near-misses increase - when work starts to become routine - when weak signals (such as employees voicing safety concerns or other worries, the organization 'feels' different, organizational climate has changed) are perceived. In organizations that already have a high safety level, safety managers work for their successors. This means that they seldom see the results of their successful efforts to improve safety. This is due to the fact that it takes time for the improvement to become noticeable in terms of increased measurable safety levels. The most challenging issue in an organizational evaluation is the definition of criteria for safety. We have adopted a system safety perspective and we state that an organization has a high potential for safety when - safety is genuinely valued and the members of the organization are motivated to put effort on achieving high levels of safety

  15. 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.

  16. 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.

  17. 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.

  18. 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....

  19. 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.

  20. Nuclear safety in crisis regions

    Energy Technology Data Exchange (ETDEWEB)

    Ustohalova, Veronika; Englert, Matthias

    2017-04-12

    of combat operations. An especially probable and relevant concern in this context is an interruption of the facility's external power supply or an attack on the power grid, so that electricity has to be supplied by the facility's own emergency power system. Over and above direct interference with nuclear facilities, in crisis situations there can also be substantial disruption of institutional control, the safety culture, access to facilities, to information or to international expertise, as well as the availability of specialist personnel. In addition, the physical delivery of fuel, expendable and replacement parts, the technical and scientific support of the nuclear infrastructure, and the training of personnel can be affected. This is a particular problem when manufacturers and suppliers are located abroad, possibly in a country that has become a party to the conflict, as is currently the case between Ukraine and Russia. The incidents discussed include Iran's bombardment of the Iraqi reactor in the course of the Iran/Iraq wars and Israel's threatened preventive military strike against Iranian nuclear facilities. A less well-known case is the example of the Metsamor reactor in Armenia, which illustrates how diverse the links between conflicts and possible impacts on facility safety can be. Military conflicts over many years and the resulting economic hardship and political calculus are having indirect impacts on the risks of this ageing and, moreover, severely earthquake-prone reactor - a volatile combination of factors for nuclear safety. Further examples are Pakistan with its unstable situation in the regions bordering India and Afghanistan; the civil war in former Yugoslavia with the military threats to the Krško nuclear power plant; and the impacts on the nuclear infrastructure resulting from the non-violent but nevertheless far from problem-free partition of Czechoslovakia after the fall of the Iron Curtain safety and the political and

  1. Case Study on Influence Factor Trend Analysis of the Accidents and Events of Nuclear Power Plants by applying Nuclear Safety Culture Framework

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-05-15

    This study 1) established the standard based on frameworks of safety culture principles that show safety culture promotion goals, 2) analyzed the linkages with the frameworks that were established by analyzing each incident cause and weak point from selected 268 cases(rating over INES grade 1) among 4,088 cases (as of April 1, 2015). The 4,088 cases were selected as a result of database analysis from 702 accidents recorded in accident and rating evaluation reports that were published in the National Nuclear Safety Commission and overseas IRS (International Reporting System for operating Experience), and 3) finally conducted a trend analysis studies with these comprehensive results. From the investigations, followings were concluded. 1) In order to analyze the safety culture, analysis methodology is required. 2) Analytical methodology for building sustainable safety culture promoting a virtuous cycle system was developed 3) Among variety of process input data, 970 domestic and overseas incidents were selected as targets and 502 accidents were classified as safety culture related events by utilizing screen filter of IAEA GS-G-3.5 Appendix I and Framework (Nuclear Safety Culture Base Frame) developed by BEES, Inc. for safety culture analysis method. 4) As a result, complex safety culture influence factors for the one reason which was difficult to separate by conventional methods was able to be analyzed. 5) The cumulative data through the system was results of virtuous trend analysis rather than temporary results. Thus, it could be unique cultural factors of the domestic industry and could derive trend differences for domestic safety culture factors accordingly.

  2. 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).

  3. 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)

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. Implementation of the obligations of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. Fourth national report of Switzerland in accordance with Article 32 of the convention

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-10-15

    The report begins with a short description of Switzerland and its most important political structures. The right of referendum allows forcing a vote on changes of the constitution or against a new law. Historically, electricity generated in Switzerland came exclusively from hydropower. In the mid 1950's, interest in the nuclear energy technology was manifested to cover an increasing electricity demand. The implementation of any nuclear programme and project required a legislative frame to ensure safety and radiation protection. A corresponding article was introduced into the Federal Constitution. The Atomic Act was put into force in 1959. It attributed to the Federal Council the exclusive competence to grant licences for the construction of, operation of and modification to nuclear facilities. Licences were based on a detailed review and assessment of nuclear safety. During the 1960's, several projects for nuclear power plants (NPP) were initiated. Four of them reached the stage of realization, leading to the five currently operating units commissioned between 1969 and 1984. These five units contribute roughly 40% of the total national electricity production, the rest being essentially covered by hydro power. The increasing opposition to nuclear power during the 1970's culminated in 1990 in a double decision taken by the Swiss population: a) to accept the further operation of the existing NPPs; b) to impose a ten years moratorium on granting licences for new NPPs. In 2003 two public votes on the prolongation of the above moratorium and on the gradual phase-out of existing NPPs were rejected by the Swiss population. Simultaneously, an entirely new Nuclear Energy Act was passed by the Parliament; it came into force on 1{sup st} February 2005 and replaced the Atomic Act. In February 2007 the Federal Council issued a new national energy strategy, including the building of new large-scale power plants and NPPs in particular. In May 2011 following the

  9. Implementation of the obligations of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. Fourth national report of Switzerland in accordance with Article 32 of the convention

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-10-15

    The report begins with a short description of Switzerland and its most important political structures. The right of referendum allows forcing a vote on changes of the constitution or against a new law. Historically, electricity generated in Switzerland came exclusively from hydropower. In the mid 1950's, interest in the nuclear energy technology was manifested to cover an increasing electricity demand. The implementation of any nuclear programme and project required a legislative frame to ensure safety and radiation protection. A corresponding article was introduced into the Federal Constitution. The Atomic Act was put into force in 1959. It attributed to the Federal Council the exclusive competence to grant licences for the construction of, operation of and modification to nuclear facilities. Licences were based on a detailed review and assessment of nuclear safety. During the 1960's, several projects for nuclear power plants (NPP) were initiated. Four of them reached the stage of realization, leading to the five currently operating units commissioned between 1969 and 1984. These five units contribute roughly 40% of the total national electricity production, the rest being essentially covered by hydro power. The increasing opposition to nuclear power during the 1970's culminated in 1990 in a double decision taken by the Swiss population: a) to accept the further operation of the existing NPPs; b) to impose a ten years moratorium on granting licences for new NPPs. In 2003 two public votes on the prolongation of the above moratorium and on the gradual phase-out of existing NPPs were rejected by the Swiss population. Simultaneously, an entirely new Nuclear Energy Act was passed by the Parliament; it came into force on 1{sup st} February 2005 and replaced the Atomic Act. In February 2007 the Federal Council issued a new national energy strategy, including the building of new large-scale power plants and NPPs in particular. In May 2011 following the

  10. 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.

  11. 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.

  12. 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

  13. Implementation of the obligations of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. Third national report of Switzerland in accordance with Article 32 of the convention

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-09-15

    The report begins with a short description of Switzerland and its most important political structures. The right of referendum allows forcing a vote on changes of the constitution or against a new law. Historically, electricity generated in Switzerland came exclusively from hydropower. In the mid 1950's, interest in the nuclear energy technology was manifested to cover an increasing electricity demand. The implementation of any nuclear programme and project required a legislative frame to ensure safety and radiation protection. A corresponding article was introduced into the Federal Constitution. The Atomic Act was put into force in 1959. It attributed to the Federal Council the exclusive competence to grant licences for the construction of, operation of and modification to nuclear facilities. Licences were based on a detailed review and assessment of nuclear safety. During the 1960's, several projects for nuclear power plants (NPP) were initiated. Four of them reached the stage of realization, leading to the five currently operating units commissioned between 1969 and 1984. These five units contribute roughly 40% of the total national electricity production, the rest being essentially covered by hydro power. The increasing opposition to nuclear power during the 1970's culminated in 1990 in a double decision taken by the Swiss population: a) to accept the further operation of the existing NPPs; b) to impose a ten years moratorium on granting licences for new NPPs. In 2003 two public votes on the prolongation of the above moratorium and on the gradual phase-out of existing NPPs were rejected by the Swiss population. Simultaneously, an entirely new Nuclear Energy Act was passed by the Parliament; it came into force on 1{sup st} February 2005 and replaced the Atomic Act. In February 2007 the Federal Council issued a new national energy strategy, including the building of new large-scale power plants and NPPs in particular. In June 2008 a general licence

  14. 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)

  15. 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.

  16. 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.

  17. 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.

  18. 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.

  19. 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.

  20. 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.

  1. 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?.

  2. 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.

  3. 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

  4. 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.

  5. 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.

  6. 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.

  7. 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

  8. Norwegian national report. Joint convention on the safety of spent fuel management and on the safety of radioactive waste management. [National report from Norway, fourth review meeting, 14-23 May 2012

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-11-15

    This report contains the national report from Norway to the fourth review meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management to be held 14 to 23 May 2012. (Author)

  9. 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.

  10. 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.

  11. Implementation of the obligations of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. Third national report of Switzerland in accordance with Article 32 of the convention

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-09-15

    The report begins with a short description of Switzerland and its most important political structures. The right of referendum allows forcing a vote on changes of the constitution or against a new law. Historically, electricity generated in Switzerland came exclusively from hydropower. In the mid 1950's, interest in the nuclear energy technology was manifested to cover an increasing electricity demand. The implementation of any nuclear programme and project required a legislative frame to ensure safety and radiation protection. A corresponding article was introduced into the Federal Constitution. The Atomic Act was put into force in 1959. It attributed to the Federal Council the exclusive competence to grant licences for the construction of, operation of and modification to nuclear facilities. Licences were based on a detailed review and assessment of nuclear safety. During the 1960's, several projects for nuclear power plants (NPP) were initiated. Four of them reached the stage of realization, leading to the five currently operating units commissioned between 1969 and 1984. These five units contribute roughly 40% of the total national electricity production, the rest being essentially covered by hydro power. The increasing opposition to nuclear power during the 1970's culminated in 1990 in a double decision taken by the Swiss population: a) to accept the further operation of the existing NPPs; b) to impose a ten years moratorium on granting licences for new NPPs. In 2003 two public votes on the prolongation of the above moratorium and on the gradual phase-out of existing NPPs were rejected by the Swiss population. Simultaneously, an entirely new Nuclear Energy Act was passed by the Parliament; it came into force on 1{sup st} February 2005 and replaced the Atomic Act. In February 2007 the Federal Council issued a new national energy strategy, including the building of new large-scale power plants and NPPs in particular. In June 2008 a general licence

  12. 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)

  13. 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

  14. 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

  15. Development of a dynamical systems model of plant programmatic performance on nuclear power plant safety risk

    Energy Technology Data Exchange (ETDEWEB)

    Hess, Stephen M. [Sensortex, Inc., 515 Schoolhouse Road, Kennett Square, PA 19348 (United States)]. E-mail: smhess@sensortex.com; Albano, Alfonso M. [Department of Physics, Bryn Mawr College, Bryn Mawr, PA 19010 (United States); Gaertner, John P. [Electric Power Research Institute, 1300 Harris Boulevard, Charlotte, NC 28262 (United States)

    2005-10-01

    Application of probabilistic risk assessment (PRA) techniques to model nuclear power plant accident sequences has provided a significant contribution to understanding the potential initiating events, equipment failures and operator errors that can lead to core damage accidents. Application of the lessons learned from these analyses has resulted in significant improvements in plant operation and safety. However, this approach has not been nearly as successful in addressing the impact of plant processes and management effectiveness on the risks of plant operation. The research described in this paper presents an alternative approach to addressing this issue. In this paper we propose a dynamical systems model that describes the interaction of important plant processes on nuclear safety risk. We discuss development of the mathematical model including the identification and interpretation of significant inter-process interactions. Next, we review the techniques applicable to analysis of nonlinear dynamical systems that are utilized in the characterization of the model. This is followed by a preliminary analysis of the model that demonstrates that its dynamical evolution displays features that have been observed at commercially operating plants. From this analysis, several significant insights are presented with respect to the effective control of nuclear safety risk. As an important example, analysis of the model dynamics indicates that significant benefits in effectively managing risk are obtained by integrating the plant operation and work management processes such that decisions are made utilizing a multidisciplinary and collaborative approach. We note that although the model was developed specifically to be applicable to nuclear power plants, many of the insights and conclusions obtained are likely applicable to other process industries.

  16. Memorandum of understanding between the Government of the Kingdom of Norway and the Government of the Kingdom of the Netherlands on early notification of a nuclear accident and exchange of safety related information concerning the operation and management of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    1989-04-18

    This Agreement was concluded in implementation of the IAEA 1986 Convention on Early Notification of a Nuclear Accident. Both Governments undertake to notify each other forthwith of any abnormal radiation levels in their respective countries. They will exchange safety related information on nuclear facilities and inform each other of measures to protect the population and the environment. (NEA).

  17. 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}.

  18. 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.

  19. Integrated safety assessment of Indian nuclear power plants for extreme events: Reducing impact on public mind

    Indian Academy of Sciences (India)

    Anil Kakodkar; Ram Kumar Singh

    2013-10-01

    Nuclear energy professionals need to understand and address the catastrophe syndrome that of late seems to be increasingly at work in public mind in the context of nuclear energy. Classically the nuclear power reactor design and system evolution has been based on the logic of minimization of risk to an acceptable level and its quantification based on a deterministic approach and backed up by a further assessment based on the probabilistic methodology. However, in spite of minimization of risk, the reasons for anxiety and trauma in public mind that still prevails in the context of severe accidents needs to be understood and addressed. Margins between maximum credible accidents factored in the design and the ultimate load withstanding capacities of relevant systems need to be enhanced and guaranteed with a view to minimize release of radioactivity and avoid serious impact in public domain. A more realistic basis for management of an accident in public domain also needs to be quantified for this purpose. Assurance to public on limiting the consequences to a level that does not lead to a trauma is something that we need to be able to credibly demonstrate and confirm. The findings from Chernobyl reports point to significant psychological effects and related health disorders due to large scale emergency relocation of people that could have been possibly reduced by an order of magnitude without significant additional safety detriment. A combination of probabilistic and deterministic approaches should be evolved further to minimize consequences in public domain through enhancing safety margins and adding greater precision to quantitatively predicting accident progression and its management. The paper presents the case studies of the extreme external event such as tsunami and its impact on the coastal nuclear plants in India, the containment integrity assessment under the extreme internal event of over-pressurization and aircraft impact along with hydrogen deflagration

  20. 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

  1. 46 CFR 2.01-25 - International Convention for Safety of Life at Sea, 1974.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 1 2010-10-01 2010-10-01 false International Convention for Safety of Life at Sea, 1974... Convention for Safety of Life at Sea, 1974. (a) Certificates required. (1) The International Convention for Safety of Life at Sea, 1974, requires one or more of the following certificates to be carried on...

  2. 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.

  3. 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)

  4. 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.

  5. 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.

  6. Simulating experimental investigation on the safety of nuclear heating reactor in loss-of-coolant accidents

    Science.gov (United States)

    Xu, Zhanjie

    1996-12-01

    The 5MW low temperature nuclear heating reactor (NHR-5) is a new and advanced type of nuclear reactor developed by Institute of Nuclear Energy Technology (INET) of Tsinghua University of China in 1989. Its main loop is a thermal-hydraulic system with natural circulation. This paper studies the safety of NHR under the condition of loss-of-coolant accidents (LOCAs) by means of simulant experiments. First, the background and necessity of the experiments are presented, then the experimental system, including the thermal-hydraulic system and the data collection system, and similarity criteria are introduced. Up to now, the discharge experiments with the residual heating power (20% rated heating power) have been carried out on the experimental system. The system parameters including circulation flow rate, system pressure, system temperature, void fraction, discharge mass and so on have been recorded and analyzed. Based on the results of the experiments, the conclusions are shown as follos: on the whole, the reactor is safe under the condition of LOCAs, but the thermal vacillations resulting from the vibration of the circulation flow rate are disadvantageous to the internal parts of the reactor core.

  7. 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

  8. A study on the feasibility and a possible form of local residents participation in nuclear safety regulation

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sang Hoon; Son, Moon Kyu [Korea Association for Nuclear Technology, Taejon (Korea, Republic of); Kim, Seong Sook [Shila Univ., Busan (Korea, Republic of)

    2003-02-15

    It is expected that the results of this study will help policy makers in the government and nuclear industry enhance the confidence of local residents and citizens in the safety of nuclear energy. It is also believed that the citizen confidence on the nuclear energy will help them implement nuclear policies more efficiently and more safely. Considering that the newly sworn-in government is to involve citizens in wide variety of policy areas, this study fits with the policy directions of the new government. Most importantly, desirable citizen participation in public decision-making is to contribute to the enhancement of the working democracy.

  9. On the Seismic Safety of Nuclear Power Plant Sites in South Korea

    Science.gov (United States)

    Choi, H.; Park, S.; Yang, J.; Shim, T.; Im, C. B.

    2016-12-01

    The Korean Peninsula is located at the far eastern part of Eurasian Plate, and within the intra-plate region several hundred km away from the nearest plate boundary. The earthquakes around the Korean Peninsula show the typical characteristics of intra-plate earthquakes. So to speak, those are low seismicity, relatively smaller magnitude than that of inter-plate earthquakes, and spatially irregular epicenters. There are 24 nuclear power plants (NPPs) in operation, 4 NPPs in completion of construction, and 4 NPPs in preparation of construction in South Korea. Even though the seismicity of the Korean Peninsula is known as relatively low, but because there are more than 30 NPPs within not so large territory, thorough the preparedness of NPPs' safety against earthquakes is required. The earthquake preparedness of NPPs in South Korea is composed of 4 stages: site election, design, construction and operation. Since regulatory codes and standards are strictly applied in each stage, the NPPs in South Korea are believed to be safe enough against the maximum potential earthquake ground motion. Through data analysis on geological and seismological characteristics of the region within a radius of 320 km from the site and the detailed geological survey of the area within a radius of 8 km from the site, the design earthquake ground motion of NPPs in South Korea is determined to be 0.2g (in case of newly constructed NPPs is 0.3g) considering the maximum potential earthquake ground motion and some safety margin. The ground motions and surface deformation caused by capable faults are also considered in the seismic design of NPPs. In addition, the Korea Institute of Nuclear Safety as a regulatory technical expert organization, has been operating independent real time earthquake monitoring network as a part of securing the seismic safety of NPP sites in South Korea since late 1990's. If earthquakes with more than magnitude 3.0 are occurred in the Korean Peninsula or the peak ground

  10. 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.

  11. ETSON views on R and D priorities for implementation of the 2014 Euratom Directive on safety of nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    Van Dorsselaere, Jean-Pierre [IRSN/PSN, Saint-Paul-lez-Durance (France); Mustoe, Jeremy; Power, Steve [Amec Foster Wheeler RSD, Birchwood Park, Warrington (United Kingdom); Adorni, Martina [Bel V, Brussels (Belgium); Schaffrath, Andreas [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany); Nieminen, Anna [VTT Technical Research Centre of Finland Ltd. (Finland)

    2016-11-15

    Following the Fukushima-Daiichi accident in 2011, the Council Directive 2014/87/Euratom has reinforced the previous 2009 Directive that had established a Community framework for the safety of nuclear installations. In particular, one new article introduces a high-level EU-wide safety objective of preventing accidents through defence- in-depth and avoiding radioactive releases outside a nuclear installation. For achieving this objective, the research necessary outcomes are mainly a better knowledge of the involved physical phenomena and its capitalization in methodologies and tools such as simulation codes. ETSON, the European Technical Safety Organisation Network, had already identified in its Position Paper in 2011 the main R and D priorities. The present paper underlines that most of these priorities, with a few updates due to progress of knowledge, remain consistent with the objectives of this new Directive. And it illustrates the ETSON involvement through examples of on-going or planned R and D national and international projects.

  12. Assessment of effects of fires on safety of nuclear power plants. Paloturvallisuuden arviointi ydinvoimalassa

    Energy Technology Data Exchange (ETDEWEB)

    Keski-Rahkonen, O.

    1992-01-01

    Experience and probabilistic safety assessments have shown that fires may present a major hazard in a nuclear plant either as initial events or as a factor aggravating the consequences from accidents initiated otherwise. Numerical modelling of fires can be performed in various ways. The oldest approach is based on experimental models where rough correlations are employed. Depending on the type of application more advanced codes are employed in fire analyses. In zone models each compartment is divided into two horizontal layers, which both are at the same temperature. In system models the building to be analyzed is divided into interconnected nodes. The most complicated fire analysis models are field models, which calculate multidimensional fields of temperatures and other quantities by solving numerically the conservation equations for several variables.

  13. 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...

  14. 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...

  15. 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.

  16. 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.

  17. 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...... within the Nordic countries as well as internationally. Two programme areas are defined under the NKS platform: The NKS-R programme on nuclear reactor safety and the NKS-B programme on emergency preparedness. Three articles, giving an introduction to NKS and its two programmes, were published...

  18. Probabilistic safety evaluation: Development of procedures with applications on components used in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Dillstroem, P. [Det Norske Veritas AB, Stockholm (Sweden)

    2000-12-01

    A probabilistic procedure has been developed by SAQ Kontroll AB to calculate two different failure probabilities, P{sub F}: Probability of failure, defect size given by NDT/NDE. Probability of failure, defect not detected by NDT/NDE. Based on the procedure, SAQ Kontroll AB has developed a computer program PROPSE (PRObabilistic Program for Safety Evaluation). Within PROPSE, the following features are implemented: Two different algorithms to calculate the probability of failure are included: Simple Monte Carlo Simulation (MCS), with an error estimate on P{sub F}. First-Order Reliability Method (FORM), with sensitivity factors using the most probable point of failure in a standard normal space. Using these factors, it is possible to rank the parameters within an analysis. Estimation of partial safety factors, given an input target failure probability and characteristic values for fracture toughness, yield strength, tensile strength and defect depth. Extensive validation has been carried out, using the probabilistic computer program STAR6 from Nuclear Electric and the deterministic program SACC from SAQ Kontroll AB. The validation showed that the results from PROPSE were correct, and that the algorithms used in STAR6 were not intended to work for a general problem, when the standard deviation is either 'small' or 'large'. Distributions, to be used in a probabilistic analysis, are discussed. Examples on data to be used are also given.

  19. 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)

  20. 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)

  1. Combining Total Monte Carlo and Benchmarks for Nuclear Data Uncertainty Propagation on a Lead Fast Reactor's Safety Parameters

    OpenAIRE

    Alhassan, Erwin; Sjöstrand, Henrik; Duan, Junfeng; Gustavsson, Cecilia; Koning, Arjan; Pomp, Stephan; Rochman, Dimitri; Österlund, Michael

    2014-01-01

    Analyses are carried out to assess the impact of nuclear data uncertainties on some reactor safety parameters for the European Lead Cooled Training Reactor (ELECTRA) using the Total Monte Carlo method. A large number of Pu-239 random ENDF-format libraries, generated using the TALYS based system were processed into ACE format with NJOY99.336 code and used as input into the Serpent Monte Carlo code to obtain distribution in reactor safety parameters. The distribution in keff obtained was compar...

  2. 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.

  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. 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.

  5. 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.

  6. Quarterly report on Defense Nuclear Facilities Safety Board Recommendation 90-7 for the period ending December 31, 1992

    Energy Technology Data Exchange (ETDEWEB)

    Cash, R.J.; Dukelow, G.T.; Forbes, C.J.

    1993-03-01

    This is the seventh quarterly report on the progress of activities addressing safety issues associated with Hanford Site high-level radioactive waste tanks that contain ferrocyanide compounds. In the presence of oxidizing materials, such as nitrates or nitrites, ferrocyanide can be made to explode in the laboratory by heating it to high temperatures [above 285{degrees}C (545{degrees}F)]. In the mid 1950s approximately 140 metric tons of ferrocyanide were added to 24 underground high-level radioactive waste tanks. An implementation plan (Cash 1991) responding to the Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990) was issued in March 1991 describing the activities that were planned and underway to address each of the six parts of Recommendation 90-7. A revision to the original plan was transmitted to US Department of Energy by Westinghouse Hanford Company in December 1992. Milestones completed this quarter are described in this report. Contents of this report include: Introduction; Defense Nuclear Facilities Safety Board Implementation Plan Task Activities (Defense Nuclear Facilities Safety Board Recommendation for enhanced temperature measurement, Recommendation for continuous temperature monitoring, Recommendation for cover gas monitoring, Recommendation for ferrocyanide waste characterization, Recommendation for chemical reaction studies, and Recommendation for emergency response planning); Schedules; and References. All actions recommended by the Defense Nuclear Facilities Safety Board for emergency planning by Hanford Site emergency preparedness organizations have been completed.

  7. 47{sup th} Annual meeting on nuclear technology (AMNT 2016). Key Topics / Enhanced safety and operation excellence

    Energy Technology Data Exchange (ETDEWEB)

    Bohnstedt, Angelika [Karlsruher Institut fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany). Programm Nukleare Entsorgung, Sicherheit und Strahlenforschung (NUSAFE); Baumann, Erik [AREVA GmbH, Erlangen (Germany). Radiation Protection

    2016-12-15

    Summary report on the Key Topic 'Enhanced Safety and Operation Excellence' Focus Session 'Radiation Protection' of the 47{sup th} Annual Meeting on Nuclear Technology (AMNT 2016) held in Hamburg, 10 to 12 May 2016. Other Sessions of AMNT 2016 have been and will be covered in further issues of atw.

  8. Integration of conventional and nuclear: What does it mean?

    Energy Technology Data Exchange (ETDEWEB)

    Manzo, Vincent A. [Center for Strategic and International Studies, Washington, D.C. (United States); Miles, Aaron R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-08-04

    In October 2015, Secretary of Defense Carter called for NATO to better integrate conventional and nuclear deterrence. Four months later, Assistant Secretary of Defense Robert Scher stated in Senate testimony that the DoD is "working to ensure an appropriate level of integration between nuclear and conventional planning and operations."

  9. 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.

  10. 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.

  11. 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

  12. 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.)

  13. 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.

  14. Research on the improvement of nuclear safety -Improvement of level 1 PSA computer code package-

    Energy Technology Data Exchange (ETDEWEB)

    Park, Chang Kyoo; Kim, Tae Woon; Kim, Kil Yoo; Han, Sang Hoon; Jung, Won Dae; Jang, Seung Chul; Yang, Joon Un; Choi, Yung; Sung, Tae Yong; Son, Yung Suk; Park, Won Suk; Jung, Kwang Sub; Kang Dae Il; Park, Jin Heui; Hwang, Mi Jung; Hah, Jae Joo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    This year is the third year of the Government-sponsored mid- and long-term nuclear power technology development project. The scope of this sub project titled on `The improvement of level-1 PSA computer codes` is divided into three main activities : (1) Methodology development on the underdeveloped fields such as risk assessment technology for plant shutdown and low power situations, (2) Computer code package development for level-1 PSA, (3) Applications of new technologies to reactor safety assessment. At first, in this area of shutdown risk assessment technology development, plant outage experiences of domestic plants are reviewed and plant operating states (POS) are decided. A sample core damage frequency is estimated for over draining event in RCS low water inventory i.e. mid-loop operation. Human reliability analysis and thermal hydraulic support analysis are identified to be needed to reduce uncertainty. Two design improvement alternatives are evaluated using PSA technique for mid-loop operation situation: one is use of containment spray system as backup of shutdown cooling system and the other is installation of two independent level indication system. Procedure change is identified more preferable option to hardware modification in the core damage frequency point of view. Next, level-1 PSA code KIRAP is converted to PC-windows environment. For the improvement of efficiency in performing PSA, the fast cutest generation algorithm and an analytical technique for handling logical loop in fault tree modeling are developed. 48 figs, 15 tabs, 59 refs. (Author).

  15. 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)

  16. NIF conventional facilities construction health and safety plan

    Energy Technology Data Exchange (ETDEWEB)

    Benjamin, D W

    1998-05-14

    The purpose of this Plan is to outline the minimum health and safety requirements to which all participating Lawrence Livermore National Laboratory (LLNL) and non-LLNL employees (excluding National Ignition Facility [NIF] specific contractors and subcontractors covered under the construction subcontract packages (e.g., CSP-9)-see Construction Safety Program for the National Ignition Facility [CSP] Section I.B. ''NIF Construction Contractors and Subcontractors'' for specifics) shall adhere to for preventing job-related injuries and illnesses during Conventional Facilities construction activities at the NIF Project. For the purpose of this Plan, the term ''LLNL and non-LLNL employees'' includes LLNL employees, LLNL Plant Operations staff and their contractors, supplemental labor, contract labor, labor-only contractors, vendors, DOE representatives, personnel matrixed/assigned from other National Laboratories, participating guests, and others such as visitors, students, consultants etc., performing on-site work or services in support of the NIF Project. Based upon an activity level determination explained in Section 1.2.18, in this document, these organizations or individuals may be required by site management to prepare their own NIF site-specific safety plan. LLNL employees will normally not be expected to prepare a site-specific safety plan. This Plan also outlines job-specific exposures and construction site safety activities with which LLNL and non-LLNL employees shall comply.

  17. 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.

  18. A State-of-the-Art Report on Technologies of a Safety Assessment and a Radioactivity Exposure Assessment for the Decommissioning Process of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kwan Seong; Kang, Young Ae; Lee, Dong Gyu; Lee, Kune Woo; Jung, Chong Hun

    2007-09-15

    This report is to provide the reference contents of research and development for technologies of radioactivity exposure and safety assessment for development of the decommissioning technology for nuclear facilities. This report consists of as follows: - Analyzing and discussing on state-of-the-art technologies of a radioactivity exposure assessment of a decommissioning for nuclear facilities - Analyzing and discussing on state-of-the-art technologies of a safety assessment of a decommissioning for nuclear facilities.

  19. 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)

  20. 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)

  1. 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)

  2. 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)

  3. 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)

  4. 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

  5. WNA's worldwide overview on front-end nuclear fuel cycle growth and health, safety and environmental issues.

    Science.gov (United States)

    Saint-Pierre, Sylvain; Kidd, Steve

    2011-01-01

    This paper presents the WNA's worldwide nuclear industry overview on the anticipated growth of the front-end nuclear fuel cycle from uranium mining to conversion and enrichment, and on the related key health, safety, and environmental (HSE) issues and challenges. It also puts an emphasis on uranium mining in new producing countries with insufficiently developed regulatory regimes that pose greater HSE concerns. It introduces the new WNA policy on uranium mining: Sustaining Global Best Practices in Uranium Mining and Processing-Principles for Managing Radiation, Health and Safety and the Environment, which is an outgrowth of an International Atomic Energy Agency (IAEA) cooperation project that closely involved industry and governmental experts in uranium mining from around the world. Copyright © 2010 Health Physics Society

  6. 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.

  7. 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

  8. Presentation of the process External communications on the nuclear facilities operation of the Adjunct Head Office of Nuclear Safety of Comision Nacional de Seguridad Nuclear y Salvaguardias; Presentacion del proceso Comunicaciones externas sobre el funcionamiento de instalaciones nucleares de la Direccion General Adjunta de Seguridad Nuclear de la Comision Nacional de Seguridad Nuclear y Salvaguardias

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa V, J. M., E-mail: jmespinosa@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2012-10-15

    The Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) in use of their attributions granted by the Regulation Law of the constitutional Art. 27 in nuclear matter began the development of the called process External communications on the nuclear facilities operation, with the purpose of negotiating the evaluation of the concerns related with the safety of the nuclear facilities received these of external people to the CNSNS. The process External communications on the nuclear facilities operation will allow to the public's members and the workers that carry out activities inside the mark regulator imposed by the CNSNS that report to this Commission their concerns related with safety for several means (for example, directly to the personnel of the assigned Office, official and public statements, phone communication, electronic mail, etc.) The present article presents the legal mark confers the CNSNS the attributions to develop the mentioned process and exposes the most important elements that compose it. The term External communication on the nuclear facilities operation is defined and also is described how these communications are received, evaluated and closed by the assigned Office. Of equal way the objectives that intents to reach this process are indicated. The intention of the mentioned process is to strengthen the actions that the CNSNS carries out in the execution of its functions to maintain the safety standards in the operation of the nuclear facilities in Mexico. (Author)

  9. 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.

  10. 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.

  11. 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

  12. Improvement on Transportation Safety on Bus by Installing A Speed Limiter in Conventional Engine to Reduce Speed Rate

    Directory of Open Access Journals (Sweden)

    Pranoto Hadi

    2016-01-01

    Full Text Available Driving is one of the conditions when the driver should be given special attention to make the motor vehicle in driving way and the driver should be in a good condition. However, the problem is in a certain condition the driver lost their control speed due to their target and minimize the driving time and it led the high potential to accident. Therefore, speed limiter which applied in the bus is urgently needed to reduce the accident and improve their awareness of road safety. Developed speed limiter is completed by fuel cut-off system to prevent the engine and maintain the speed. Limitation of speed be adapted by government regulation. From the results show that the highest and average speed of 136 km/h and 123.5 km/h is observed by bus speed prior to use speed limiter. After speed limiter applied in the bus, the approved maximum speed is 90 km/h. Those data approve that the speed limiter can reduce 83% from the top speed before speed limiter applied.

  13. Research on the improvement of nuclear safety -The development of LOCA analysis codes for nuclear power plant-

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Won Pyo; Jung, Yung Jong; Kim, Kyung Doo; Jung, Jae Joon; Kim, Won Suk; Han, Doh Heui; Hah, Kooi Suk; Jung, Bub Dong; Lee, Yung Jin; Hwang, Tae Suk; Lee, Sang Yong; Park, Chan Uk; Choi, Han Rim; Lee, Sang Jong; Choi, Jong Hoh; Ban, Chang Hwan; Bae, Kyoo Hwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    The present research aims at development of both a best estimate methodology on LOCA analysis and, as an application, performance analyses of safety systems. SBLOCA analyses have been continued to examine the capacity reduction effect of ECCS since the second project year. As a results, core uncovery, which is requirement of URD has not been occurred in 6`` cold leg break. Although core uncovery has been predicted when DVI line has been broken for DVI+4-Train HPIS, the calculated PCT has lied well within the criterion. The effect of safety injection position and SIT characteristics are also analyzed for LBLOCA. The results show that cold leg injection is the most effective way and the adaption of advanced SIT could lead to elimination of LPSI pump from the safety system. On the other hand, the quantified uncertainties obtained from THTF and FLECHT/SEASET which represents blowdown and reflood phenomena, respectively, have been confirmed using IET(LOFT test). The application uncertainty for Kori unit 3 has been analyzed. Finally, application of the best estimate methodology using the uncertainties concerned with the code, the bais, and the application, leads to overall uncertainty of about 200K for Kori unit 3. 244 figs, 22 tabs, 92 refs. (Author).

  14. Some questions on nuclear safety of heavy-water power reactor operating in self-sufficient thorium cycle

    Directory of Open Access Journals (Sweden)

    Bergelson Boris R.

    2008-01-01

    Full Text Available In this paper the comparative calculations of the void coefficient have been made for different types of channel reactors for the coolant density interval 0.8-0.01 g/cm3. These results demonstrate the following. In heavy-water channel reactors, the replacement of D2O coolant by H2O, ensuring significant economic advantage, leads to the essential reducing of nuclear safety of an installation. The comparison of different reactors by the void coefficient demonstrates that at the dehydration of channels the reactivity increase is minimal for HWPR(Th, operating in the self-sufficient mode. The reduction of coolant density in channels in most cases is accompanied by the increase of power and temperatures of fuel assemblies. The calculations show that the reduction of reactivity due to Doppler effect can compensate the effect of dehydration of a channel. However, the result depends on the time dependency of heat-hydraulic processes, occurring in reactor channels in the specific accident. The result obtained in the paper confirms that nuclear safety of HWPR(Th lies on the same level as nuclear safety of CANDU type reactors approved in practice.

  15. 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.

  16. 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)

  17. 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...

  18. 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...

  19. 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.

  20. 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)

  1. 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)

  2. 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)

  3. 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...

  4. 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.

  5. Review guidelines on software languages for use in nuclear power plant safety systems. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Hecht, H.; Hecht, M.; Graff, S.; Green, W.; Lin, D.; Koch, S.; Tai, A.; Wendelboe, D. [SoHaR, Inc., Beverly Hills, CA (United States)

    1996-06-01

    Guidelines for the programming and auditing of software written in high level languages for safety systems are presented. The guidelines are derived from a framework of issues significant to software safety which was gathered from relevant standards and research literature. Language-specific adaptations of these guidelines are provided for the following high level languages: Ada, C/C++, Programmable Logic Controller (PLC) Ladder Logic, International Electrotechnical Commission (IEC) Standard 1131-3 Sequential Function Charts, Pascal, and PL/M. Appendices to the report include a tabular summary of the guidelines and additional information on selected languages.s

  6. The effects of electric power industry restructuring on the safety of nuclear power plants in the United States

    Science.gov (United States)

    Butler, Thomas S.

    Throughout the United States the electric utility industry is restructuring in response to federal legislation mandating deregulation. The electric utility industry has embarked upon an extraordinary experiment by restructuring in response to deregulation that has been advocated on the premise of improving economic efficiency by encouraging competition in as many sectors of the industry as possible. However, unlike the telephone, trucking, and airline industries, the potential effects of electric deregulation reach far beyond simple energy economics. This dissertation presents the potential safety risks involved with the deregulation of the electric power industry in the United States and abroad. The pressures of a competitive environment on utilities with nuclear power plants in their portfolio to lower operation and maintenance costs could squeeze them to resort to some risky cost-cutting measures. These include deferring maintenance, reducing training, downsizing staff, excessive reductions in refueling down time, and increasing the use of on-line maintenance. The results of this study indicate statistically significant differences at the .01 level between the safety of pressurized water reactor nuclear power plants and boiling water reactor nuclear power plants. Boiling water reactors exhibited significantly more problems than did pressurized water reactors.

  7. 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.

  8. 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)

  9. 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...

  10. The impact of conventional and nuclear industries on the population A comparative study of the radioactive and chemical aspects

    CERN Document Server

    Coulon, R; Anguenot, F

    1988-01-01

    This study was carried out to make it possible to assess and localize in an objective manner the extent of the hazards and associated detrimental effects which are inherent in nuclear and non-nuclear industrial activities, among all the hazards to which the population of a given region is exposed. Rather than carry out a purely theoretical and speculative study a region was chosen as a basis to carry out a full- scale exercise, taking into account the existing real situation. The region chosen is situated in the south-east of France (Greater Rhone Delta) where almost all industrial activities can be found: electricity generating industries (thermal and nuclear power stations), the activities associated with them (extraction, processing, storage of waste, etc.) and industrial activities which are sources of pollution (refineries, chemical industries, etc.). To put the risks of all these activities (to workers, the public and the environment) in perspective, the case of other sources of risk, such as certain ag...

  11. ASN annual report 2007 - ASN report abstracts on the state of Nuclear Safety and Radiation Protection in France in 2007; ASN rapport annuel 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    The 2007 annual report of the French nuclear safety authority (ASN) presents the highlights of the year in the domain of nuclear safety and radiation protection in France. The year 2007 was marked by the implementation of a new legislative and regulatory framework created by the 13 June 2006 Act on transparency and security in the nuclear field (TSN) and the 28 June Act on the sustainable management of radioactive materials and wastes. As in the previous two years, the year was relatively satisfactory from the nuclear safety viewpoint and slightly less so with regard to small-scale nuclear activities. For two years now, the medical field has been marked by the declaration to ASN of a number of serious radiotherapy accidents which have led to several deaths or the need for extensive surgery. The following main topics are reviewed in the document: 1 - the decrees implementing the 'TSN' act and the 'Waste' act; 2 - the new ASN, one year on; 3 - ASN regulatory actions in the field of radiotherapy; 4 - regulation of new installations; 5 - the key issues for regulation of existing installations; 6 - nuclear safety and radiation protection research; 7 - policy for management of the post-accident phase of a radiological emergency; 8 - sites and soils polluted by radioactive materials; 9 - international harmonization of nuclear safety and radiation protection.

  12. 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)

  13. Perspectives on the application of order-statistics in best-estimate plus uncertainty nuclear safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Martin, Robert P., E-mail: smsrpm@owt.co [AREVA NP, Inc., 3315 Old Forest Road, Lynchburg, VA (United States); Nutt, William T. [Nuclear Safety Analysis Services, 500 Aloha Street 403, Seattle, WA 98109 (United States)

    2011-01-15

    Research highlights: Historical recitation on application of order-statistics models to nuclear power plant thermal-hydraulics safety analysis. Interpretation of regulatory language regarding 10 CFR 50.46 reference to a 'high level of probability'. Derivation and explanation of order-statistics-based evaluation methodologies considering multi-variate acceptance criteria. Summary of order-statistics models and recommendations to the nuclear power plant thermal-hydraulics safety analysis community. - Abstract: The application of order-statistics in best-estimate plus uncertainty nuclear safety analysis has received a considerable amount of attention from methodology practitioners, regulators, and academia. At the root of the debate are two questions: (1) what is an appropriate quantitative interpretation of 'high level of probability' in regulatory language appearing in the LOCA rule, 10 CFR 50.46 and (2) how best to mathematically characterize the multi-variate case. An original derivation is offered to provide a quantitative basis for 'high level of probability.' At root of the second question is whether one should recognize a probability statement based on the tolerance region method of Wald and Guba, et al., for multi-variate problems, one explicitly based on the regulatory limits, best articulated in the Wallis-Nutt 'Testing Method', or something else entirely. This paper reviews the origins of the different positions, key assumptions, limitations, and relationship to addressing acceptance criteria. It presents a mathematical interpretation of the regulatory language, including a complete derivation of uni-variate order-statistics (as credited in AREVA's Realistic Large Break LOCA methodology) and extension to multi-variate situations. Lastly, it provides recommendations for LOCA applications, endorsing the 'Testing Method' and addressing acceptance methods allowing for limited sample failures.

  14. Structural Safety Analysis Based on Seismic Service Conditions for Butterfly Valves in a Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Sang-Uk Han

    2014-01-01

    Full Text Available The structural integrity of valves that are used to control cooling waters in the primary coolant loop that prevents boiling within the reactor in a nuclear power plant must be capable of withstanding earthquakes or other dangerous situations. In this study, numerical analyses using a finite element method, that is, static and dynamic analyses according to the rigid or flexible characteristics of the dynamic properties of a 200A butterfly valve, were performed according to the KEPIC MFA. An experimental vibration test was also carried out in order to verify the results from the modal analysis, in which a validated finite element model was obtained via a model-updating method that considers changes in the in situ experimental data. By using a validated finite element model, the equivalent static load under SSE conditions stipulated by the KEPIC MFA gave a stress of 135 MPa that occurred at the connections of the stem and body. A larger stress of 183 MPa was induced when we used a CQC method with a design response spectrum that uses 2% damping ratio. These values were lower than the allowable strength of the materials used for manufacturing the butterfly valve, and, therefore, its structural safety met the KEPIC MFA requirements.

  15. Structural safety analysis based on seismic service conditions for butterfly valves in a nuclear power plant.

    Science.gov (United States)

    Han, Sang-Uk; Ahn, Dae-Gyun; Lee, Myeong-Gon; Lee, Kwon-Hee; Han, Seung-Ho

    2014-01-01

    The structural integrity of valves that are used to control cooling waters in the primary coolant loop that prevents boiling within the reactor in a nuclear power plant must be capable of withstanding earthquakes or other dangerous situations. In this study, numerical analyses using a finite element method, that is, static and dynamic analyses according to the rigid or flexible characteristics of the dynamic properties of a 200A butterfly valve, were performed according to the KEPIC MFA. An experimental vibration test was also carried out in order to verify the results from the modal analysis, in which a validated finite element model was obtained via a model-updating method that considers changes in the in situ experimental data. By using a validated finite element model, the equivalent static load under SSE conditions stipulated by the KEPIC MFA gave a stress of 135 MPa that occurred at the connections of the stem and body. A larger stress of 183 MPa was induced when we used a CQC method with a design response spectrum that uses 2% damping ratio. These values were lower than the allowable strength of the materials used for manufacturing the butterfly valve, and, therefore, its structural safety met the KEPIC MFA requirements.

  16. International maritime conventions on safety of fishing vessels%捕捞渔船安全国际海事立法之观察

    Institute of Scientific and Technical Information of China (English)

    刘新山; 任玉清; 贺讯

    2012-01-01

    国际海事组织在过去几十年一直努力推动捕捞渔船安全国际立法工作。通过对主要的涉渔海事公约以及港口国监督措施,特别是《1993年捕捞渔船安全议定书》和《捕捞渔船船员培训、发证和值班标准国际公约》的探讨,建议中国渔业主管部门、渔业界及行业组织重视国际渔业法研究和普及工作,积极行使国际法权利和履行国际法义务,参照相关海事公约及时修改国内海事安全和渔业法规,依法建立全国统一的渔船和渔船船员登记系统,增强对捕捞渔船现代化和渔船船员培训事业的扶持力度,促进中国海洋渔业的稳健发展。%IMO has been exerted its effort to make international laws concerning safety of fishing vessels in the past decades. The paper explores those maritime conventions on fishery and port state control, in particular the 1993 Protocol Relating to the Safety of Fishing Vessels and International Convention on Standards of Training, Certification and Watchkeeping for Fishing Vessel Personnel. It is recommended that the fisheries administrations, fishing industry and industrial associations emphasize studying and disseminating international fisheries laws, exercise and perform actively the international rights and obligations, amend timely the laws and regulations regarding marine safety and fishery by due reference to the related maritime conventions, establish the national register system for fishing vessels and fishing personnel, and strengthen financial support to modernization of fishing vessels and training of fishing personnel to pursue steady development of Chinese marine fishery.

  17. Combining Total Monte Carlo and Benchmarks for nuclear data uncertainty propagation on an LFRs safety parameters

    CERN Document Server

    Alhassan, Erwin; Duan, Junfeng; Gustavsson, Cecilia; Koning, Arjan; Pomp, Stephan; Rochman, Dimitri; Österlund, Michael

    2013-01-01

    Analyses are carried out to assess the impact of nuclear data uncertainties on keff for the European Lead Cooled Training Reactor (ELECTRA) using the Total Monte Carlo method. A large number of Pu-239 random ENDF-formated libraries generated using the TALYS based system were processed into ACE format with NJOY99.336 code and used as input into the Serpent Monte Carlo neutron transport code to obtain distribution in keff. The keff distribution obtained was compared with the latest major nuclear data libraries - JEFF-3.1.2, ENDF/B-VII.1 and JENDL-4.0. A method is proposed for the selection of benchmarks for specific applications using the Total Monte Carlo approach. Finally, an accept/reject criterion was investigated based on chi square values obtained using the Pu-239 Jezebel criticality benchmark. It was observed that nuclear data uncertainties in keff were reduced considerably from 748 to 443 pcm by applying a more rigid acceptance criteria for accepting random files.

  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. 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.

  20. Financial Control and Safety. An investigation on how financial and safety aspects are integrated in the decision making at the Swedish nuclear power plants; Ekonomistyrning och saekerhet. En utredning om hur ekonomi- och saekerhetsaspekter integreras vid beslutsfattandet vid kaernkraftverken

    Energy Technology Data Exchange (ETDEWEB)

    Vaernild, Ola [OV Konsult i Vaesteraas AB, Vaesteraas (Sweden)

    2005-08-01

    The alleged inter-relationship between economy and nuclear safety has been investigated. Through interviews and review of instructions and other documents, information on how management at Swedish nuclear power plants integrates financial control and safety management has been compiled. Owners of nuclear power plants have well founded expectations on that the plants are profitable and that the operations are rationalized in order to reduce costs. This could allegedly threaten the nuclear safety. However, it is not to be expected that there are any obvious relationships between expenditures and safety. The quality of the safety management has to be judged in terms of how well safety requirements are met irrespective of the associated costs. The owners have imposed clear financial objectives on the nuclear power plants. At the same time they have also established policies for nuclear safety. The nuclear power plants have systems for operations management, which basically comprise separate parts for operations planning and quality management. Financial control and safety management are included in the operations planning and quality management respectively. The quality management impose restrictions to be adhered to in the operations planning. This means that from a formal point of view, the safety management is superior to the operations planning. There are examples of simple as well as advanced approaches to financial management at the nuclear power plants. In all cases the methods used are reasonably well adapted to the needs. Typical for all plants is the focus on long-term aspects. Investments are for example analysed in a plant life-time perspective. With regard to safety, profitability calculations are not required to the same extent for safety related investments as for other investments. A number of factors, which tend to warrant that safety aspects are given the appropriate attention in the decision making, have been identified. Examples of such factors are

  1. 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.

  2. Laymen's demand on an understandable safety analysis for a nuclear waste repository. A communication challenge

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, T.L.; Thunberg, A.M. [KASAM - Swedish National Council for Nuclear Waste (Sweden)

    1999-12-01

    This paper is a summary in English of some impressions from a seminar 'Safety Analysis of the Final Disposal of Nuclear Waste. An issue for specialists only or for all of us?' The seminar was held in Swedish and was arranged by KASAM in Nykoeping, Sweden in November 1997. A report in Swedish from the seminar has been published. The seminar was arranged in response to a request from representatives from some of the municipalities concerned by the feasibility studies, which are part of the siting process. They had noticed that it is very hard for people without specialist competence to get an understanding of the safety issues based on the available information. There is a need for a presentation of the safety analysis, which is adopted not only for the need of the safety authorities, which have their own expertise, but also for the need of laymen who are involved in issues about the design, siting and safety of a final repository. Therefore, the seminar was mainly intended for representatives for the citizens (i.e. politicians) from the municipalities involved in the ongoing feasibility studies in Sweden. Some representatives from different environmental organisations opposing final disposal were also invited as well as representatives from the nuclear industry and from the concerned Swedish authorities. The seminar was structured in four sessions The handling of risk in the modern society - risk assessment and risk comparisons; The safety analysis and its role for the citizens; What can actually happen - in our own time and in the future?; Group discussions. In order to give a realistic picture of the intense debate, which at least in some of the municipalities had been very apparent, the organisers had chosen to make SKB and Greenpeace main actors at the seminar, such as they appeared in connection with campaign before the referendum at Malaa. Parts of the seminar were arranged like a hearing, led by a science journalist. The intention with this paper is

  3. Combining Total Monte Carlo and Benchmarks for nuclear data uncertainty propagation on an LFRs safety parameters

    OpenAIRE

    Alhassan, Erwin; Sjöstrand, Henrik; Duan, Junfeng; Gustavsson, Cecilia; Koning, Arjan; Pomp, Stephan; Rochman, Dimitri; Österlund, Michael

    2013-01-01

    Analyses are carried out to assess the impact of nuclear data uncertainties on keff for the European Lead Cooled Training Reactor (ELECTRA) using the Total Monte Carlo method. A large number of Pu-239 random ENDF-formated libraries generated using the TALYS based system were processed into ACE format with NJOY99.336 code and used as input into the Serpent Monte Carlo neutron transport code to obtain distribution in keff. The keff distribution obtained was compared with the latest major nuclea...

  4. SR-CAN - a safety assessment of a repository of spent nuclear fuel: canister performance and effects on the biosphere

    Energy Technology Data Exchange (ETDEWEB)

    Kautsky, U.; Kumblad, L. [Swedish Nuclear Fuel and Waste Management Co. (SKB), Stockholm (Sweden)

    2004-07-01

    During the next few years the Swedish Nuclear Fuel and Waste Management Co. (SKB) performs site investigations at two sites in Sweden for a future repository of spent nuclear fuel. Parallel an encapsulation plant is planned to encapsulate the spent fuel in copper canisters according to the KBS-3 method. The purpose of the SR-CAN safety assessment is to show the performance of the canister isolations at different sites for a repository at 500 meters depth in crystalline rock. Moreover, SR-CAN provides an example how the site specific safety assessment of a deep repository will be made in year 2006-2008. To be able to calculate dose and risk for humans and the environment, new assessment methods were developed for the biosphere. These methods were based on a system ecological approach and used knowledge from landscape ecology to provide an integrated approach with hydrology and geology considering the discharges in a watershed and calculating consequences in terrestrial and aquatic (freshwater and marine) ecosystems. A range of methods and tools were developed in GIS and Matlab/Simulink to be able to model and understand the important processes in the landscape today and during the next few thousands of years. In this paper, an overview of the program and the novel methods are presented, as well as some examples from performance calculations from a watershed in the Forsmark area considering effects on humans and ecosystems. (author)

  5. Simulating Experimental Investigation on the Safety of Nuclear Heating Reactor in Loss—of —Coolant Accidents

    Institute of Scientific and Technical Information of China (English)

    ZhanjieXu

    1996-01-01

    The 5MW low temperature nuclear heating reactor (NHR-5) is a new and advanced type of nuclear reactor developed by Institute of Nuclear Energy Technology(INET) of Tisinghuan University of CHina in 1989,Its main loop is a thermal-hydraulic system with natural circulation.This paper studies the safety of NHR under the condition of loss-of -coolant accidents(LOCAs) by means of simulant experiments.First,the Background and necessity of the experiments are presented.then the experimental system,including the thermal-hydraulic system and the data collection system,and similarity criteria are introduced.Up to now ,the discharge experiments with the residual heating power(20% rated heating power)have been carried out on the experimental system,The system prameters including circulation flow rate,system pressure,system temperature,void fraction,discharge mass and so on have been recorded and analyzed.Based on the results of the experiments,the conclusionas are shown as follos:on the whole,the reactor is safe under the condition of LOCAs,but the thermal vacillations resulting from the vibration of the circulation flow rate are disadvantageous to the internal parts of the reactor core.

  6. 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.

  7. 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.

  8. 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).

  9. 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.

  10. 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.

  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. 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...

  13. 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.)

  14. 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.

  15. 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

  16. Review report: safety and reliability issues on digital instrumentation and control systems in nuclear power plants and United States Nuclear Regulatory Commission`s dispositions

    Energy Technology Data Exchange (ETDEWEB)

    Watanabe, Norio; Suzudo, Tomoaki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-09-01

    Recently, digital instrumentation and control (I and C) systems have been applied to nuclear power plants (NPPs) in various countries. Introduction of digital I and C systems, however, raises special issues on design, implementation, safety and licensing. Since FY 1997, the Japan Atomic Energy Research Institute (JAERI) has been carrying out a project, Study on Reliability of Digital I and C Systems, which includes extensive reviews of design approaches, technical standards, regulatory processes, especially, in the United States. This report summarizes the results from the study of National Research Council (NRC) and the U.S. Nuclear Regulatory Commission`s (USNRC`s) responses to the recommendations made by the NRC`s study. That study identified six technical key issues (system aspects of digital I and C technology, software quality assurance, common-mode software failure potential, safety and reliability assessment methods, human factors and man-machine interface, dedication of commercial off-the-shelf hardware and software) and two strategic key issues (case-by-case licensing process, adequacy of technical infrastructure) that arise from the introduction of digital I and C technology and then, made recommendations to the USNRC for coping with digital I and C applications. The USNRC responded to each recommendation and showed their own dispositions in which the USNRC agreed with most of the recommendations. In Japan, it is expected that introduction of digital I and C technology is inevitable in NPPs because the vendors are gradually discontinuing support and stocking of analog components. To cope with such situations, there is a need to develop and update the standards and guidelines applicable to digital I and C technology. The key issues and the USNRC`s dispositions provided in this report is believed to be useful for developing and updating them. (J.P.N.)

  17. 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…

  18. 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.

  19. Draft Convention on the Exemption from Taxes of the European Organization for Nuclear Research, The Representatives of Member States on the Council of the Organization, the Director-General and the Members of the Staff of the European Organization for Nuclear Research

    CERN Document Server

    European Organization for Nuclear Research

    1955-01-01

    Draft Convention on the Exemption from Taxes of the European Organization for Nuclear Research, The Representatives of Member States on the Council of the Organization, the Director-General and the Members of the Staff of the European Organization for Nuclear Research

  20. 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

  1. 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

  2. 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.

  3. 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)

  4. 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

  5. 46{sup th} annual meeting on nuclear technology (AMNT 2015). Key topics / Outstanding know-how and sustainable innovations enhanced safety and operation excellence

    Energy Technology Data Exchange (ETDEWEB)

    Lamm, Matthias [AREVA GmbH, Erlangen (Germany). R and D; Hollands, Thorsten [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany). Reactor Safety Research Div.

    2016-01-15

    Summary report on the Technical Sessions ''Know-how, New Build and Innovations'' and ''Operation and Safety of Nuclear Installations, Fuel SA: WASA-BOSS + CESAM'' of the 46{sup th} Annual Conference on Nuclear Technology (AMNT 2015) held in Berlin, 5 to 7 May 2015. Other Sessions of AMNT 2015 have been covered in atw 7 to 12 (2015) and will be covered in further issues of atw.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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)

  11. 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)

  12. 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.

  13. 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.

  14. 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.

  15. Design characteristics for pressurized water small modular nuclear power reactors with focus on safety

    Energy Technology Data Exchange (ETDEWEB)

    Kani, Iraj Mahmoudzadeh [Tehran Univ. (Iran, Islamic Republic of). Civil Faculty; Zandieh, Mehdi [Tehran Univ. (Iran, Islamic Republic of). Civil Faculty; International Univ. of Imam Khomeini (Iran, Islamic Republic of). Architecture Faculty; Abadi, Saeed Kheirollahi Hossein [International Univ. of Imam Khomeini (Iran, Islamic Republic of). Architecture Faculty

    2016-05-15

    Small Modular Reactors (SMRs) are a technology, attracting attention. Light water SMR possess an upgraded design case and emphasize the significance of integral models. Beside of these advantages, SMRs has faced numerous challenges, e.g. licensing, cost/investment, safety and security observation, social and environmental issues in building new plants.

  16. 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.

  17. 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.

  18. 47{sup th} Annual conference on nuclear technology (AMNT 2016). Key topics / Outstanding know-how and sustainable innovations - enhanced safety and operation excellence

    Energy Technology Data Exchange (ETDEWEB)

    Raetzke, Christian [CONLAR - Consulting on Nuclear Law, Licensing and Regulation, Leipzig (Germany); Fischer, Erwin [PreussenElektra GmbH, Hannover (Germany). Management Board; Mohrbach, Ludger [VGB PowerTech e.V., Essen (Germany). Competence Center ' ' Nuclear Power Plants' '

    2016-08-15

    Summary report on the Key Topics ''Outstanding Know-How and Sustainable Innovations'' and ''Enhanced Safety and Operation Excellence'' of the 47{sup th} Annual Conference on Nuclear Technology (AMNT 2016) held in Hamburg, 10 to 12 May 2016. Other Sessions of AMNT 2016 will be covered in further issues of atw.

  19. 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.

  20. 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.

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. Final Technical Report on Quantifying Dependability Attributes of Software Based Safety Critical Instrumentation and Control Systems in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Smidts, Carol [The Ohio State Univ., Columbus, OH (United States); Huang, Funqun [The Ohio State Univ., Columbus, OH (United States); Li, Boyuan [The Ohio State Univ., Columbus, OH (United States); Li, Xiang [The Ohio State Univ., Columbus, OH (United States)

    2016-03-25

    elicitation for each of the software dependability attributes. The measures extracted are presented in this chapter. Stage 4 (Chapter 5): Assessment of the coverage of the causal maps via measures. Coverage was assessed to determine whether the measures obtained were sufficient to quantify software dependability, and what measures are further required. Stage 5 (Chapter 6): Identification of “missing” measures and measurement approaches for concepts not covered. New measures, for concepts that had not been covered sufficiently as determined in Stage 4, were identified using supplementary expert opinion elicitation as well as literature reviews. Stage 6 (Chapter 7): Building of a detailed quantification model based on the causal maps and measurements obtained. Ability to derive such a quantification model shows that the causal models and measurements derived from the previous stages (Stage 1 to Stage 5) can form the technical basis for developing dependability quantification models. Scope restrictions have led us to prioritize this demonstration effort. The demonstration was focused on a critical system, i.e. the reactor protection system. For this system, a ranking of the software dependability attributes by nuclear stakeholders was developed. As expected for this application, the stakeholder ranking identified safety as the most critical attribute to be quantified. A safety quantification model limited to the requirements phase of development was built. Two case studies were conducted for verification. A preliminary control gate for software safety for the requirements stage was proposed and applied to the first case study. The control gate allows a cost effective selection of the duration of the requirements phase.

  6. Research on the improvement of nuclear safety -Development of a nuclear power plant system analysis code TASS (Transient and setpoint simulation)

    Energy Technology Data Exchange (ETDEWEB)

    Shim, Suk Koo; Jang, Won Pyo; Kim, Heui Chul; Kim, Kyung Doo; Lee, Sung Jae; Hah, Kyooi Suk; Song, Soon Jah; Um, Kil Sub; Yoon, Han Yung; Kim, Doo Il; Yoo, Hyung Keun; Choi, Jae Don; Lee, Byung Il; Kim, Jung Jin [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-07-01

    During the third year of the project the development of TASS 1.0 code has been completed and validated its capability in applying for the licensing transient analyses of the Westinghouse and CE type operating reactors as well as the PWR reactors under construction in Korea. The validation of the TASS 1.0 code has been achieved through the comparison calculations of the YGN-3/4 FSAR transients, Kori-3 loss of AC power transient, plant data, Kori-4 load rejection and YGN-3 startup test data as well as the BETHSY loop steam generator tube rupture test data. TASS 1.0 calculation agrees well with the best estimate RELAP5/MOD 3.1 calculation for the YGN-3/4 FASR transients and shows its capability in simulating plant transient and startup data as well as the thermal hydraulic transient test data. Topical reports on TASS 1.0 code have been prepared and will be submitted to Korea Institute of Nuclear Safety for its licensing application to Westinghouse and CE type PWR transient analyses. The development of TASS 2.0 code has been head started in this year to timely utilize the TASS 2.0 code for the KNGR design certification. 65 figs, 30 tabs, 44 refs. (Author).

  7. Bill project authorizing the approval of the amendment to the Convention on the physical protection of nuclear materials; Projet de loi autorisant l'approbation de l'amendement a la convention sur la protection physique des matieres nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Juppe, Alain [Ministere des Affaires Etrangeres et Europeennes, 37 Quai d' Orsay, 75007 Paris (France); Fillon, Francois [Premier ministre, Hotel de Matignon, 57, rue de Varenne, 75700 Paris (France)

    2011-12-01

    This document deals with the amendment to the Convention on the Physical Protection of Nuclear Materials which has been adopted in July 2005. This amendment notably extended the Convention's scope, objectives, relation with other international instruments and content (regarding cooperation, sanctions, and so on). After the text of this amendment, this document contains the bill project which reports an impact study (estimated economic, financial, environmental, and legal consequences of the amendment implementation), comments the penal and criminal cooperation defined in the Convention. A table indicates the impact of the amendment's articles on the French law

  8. Final Technical Report on Quantifying Dependability Attributes of Software Based Safety Critical Instrumentation and Control Systems in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Smidts, Carol [The Ohio State Univ., Columbus, OH (United States); Huang, Funqun [The Ohio State Univ., Columbus, OH (United States); Li, Boyuan [The Ohio State Univ., Columbus, OH (United States); Li, Xiang [The Ohio State Univ., Columbus, OH (United States)

    2016-03-25

    With the current transition from analog to digital instrumentation and control systems in nuclear power plants, the number and variety of software-based systems have significantly increased. The sophisticated nature and increasing complexity of software raises trust in these systems as a significant challenge. The trust placed in a software system is typically termed software dependability. Software dependability analysis faces uncommon challenges since software systems’ characteristics differ from those of hardware systems. The lack of systematic science-based methods for quantifying the dependability attributes in software-based instrumentation as well as control systems in safety critical applications has proved itself to be a significant inhibitor to the expanded use of modern digital technology in the nuclear industry. Dependability refers to the ability of a system to deliver a service that can be trusted. Dependability is commonly considered as a general concept that encompasses different attributes, e.g., reliability, safety, security, availability and maintainability. Dependability research has progressed significantly over the last few decades. For example, various assessment models and/or design approaches have been proposed for software reliability, software availability and software maintainability. Advances have also been made to integrate multiple dependability attributes, e.g., integrating security with other dependability attributes, measuring availability and maintainability, modeling reliability and availability, quantifying reliability and security, exploring the dependencies between security and safety and developing integrated analysis models. However, there is still a lack of understanding of the dependencies between various dependability attributes as a whole and of how such dependencies are formed. To address the need for quantification and give a more objective basis to the review process -- therefore reducing regulatory uncertainty

  9. Operational readiness verification, phase 1: A study on safety during outage and restart of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hollnagel, E. [Linkoeping Univ. (Sweden). Dept. of Computer and Information Science; Gauthereau, V. [Linkoeping Univ. (Sweden). Dept. of Industrial Engineering

    2001-06-01

    This report contains the findings from the first phase of a study on safety during outage and restart of nuclear power plants. Operational Readiness Verification (ORV) - in Swedish called Driftklarhetsverifiering (DKV) - refers to the test and verification activities that are necessary to ensure that plant systems are able to provide their required functions when needed - more concretely that all plant systems are in their correct functional state when the plant is restarted after an outage period. The concrete background for this work is that nine ORV related incidents were reported in Sweden between July 1995 and October 1998. The work reported here comprised a literature survey of research relevant for ORV issues, and an assessment of the present situation at Swedish NPPs with respect to ORV. The literature survey was primarily aimed at research related to NPPs, but also looked at domains where similar problems have occurred, such as maintenance in commercial aviation. The survey looked specifically for organisational and MTO aspects relevant to the present situation in Swedish NPPs. One finding was that ORV should be seen as an integral part of maintenance, rather than as a separate activity. Another, that there is a characteristic distribution of error modes for maintenance and ORV, with many sequence errors and omissions, rather than a set of unique error modes. An international study further showed that there are important differences in how procedures are used, and in the balance between decentralisation and centralisation. Several studies also suggested that ORV could usefully be described as a barrier system in relation to the flow of work, for instance using the following five stages: (1) preventive actions during maintenance/outage, (2) post-test after completion of work, (3) pre-test before start-up, (4) the start-up sequence itself, and (5) preventive actions during power operation - possibly including automatic safety systems. In the field survey

  10. Conventional and Unconventional Pairing and Condensates in Dilute Nuclear Matter

    CERN Document Server

    Clark, John W; Stein, Martin; Huang, Xu-Guang; Khodel, Victor A; Shaginyan, Vasily R; Zverev, Mikhail V

    2016-01-01

    This contribution will survey recent progress toward an understanding of diverse pairing phenomena in dilute nuclear matter at small and moderate isospin asymmetry, with results of potential relevance to supernova envelopes and proto-neutron stars. Application of {\\it ab initio} many-body techniques has revealed a rich array of temperature-density phase diagrams, indexed by isospin asymmetry, which feature both conventional and unconventional superfluid phases. At low density there exist a homogeneous translationally invariant BCS phase, a homogeneous LOFF phase violating translational invariance, and an inhomogeneous translationally invariant phase-separated BCS phase. The transition from the BCS to the BEC phases is characterized in terms of the evolution, from weak to strong coupling, of the pairing gap, condensate wave function, and quasiparticle occupation numbers and spectra. Additionally, a schematic formal analysis of pairing in neutron matter at low to moderate densities is presented that establishes...

  11. 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)

  12. 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)

  13. 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.

  14. 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.

  15. 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.

  16. 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)

  17. Perspectives on the Application of Order-Statistics in Best-Estimate Plus Uncertainty Nuclear Safety Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Robert P. Martin; William T. Nutt

    2011-01-01

    The application of order-statistics in best-estimate plus uncertainty nuclear safety analysis has received a considerable amount of attention from methodology practitioners, regulators, and academia. At the root of the debate are two questions: (1) what is an appropriate quantitative interpretation of “high level of probability” in regulatory language appearing in the LOCA rule, 10 CFR 50.46 and (2) how best to mathematically characterize the multi-variate case. An original derivation is offered to provide a quantitative basis for “high level of probability.” At root of the second question is whether one should recognize a probability statement based on the tolerance region method of Wald and Guba, et al., for multi-variate problems, one explicitly based on the regulatory limits, best articulated in the Wallis–Nutt “Testing Method”, or something else entirely. This paper reviews the origins of the different positions, key assumptions, limitations, and relationship to addressing acceptance criteria. It presents a mathematical interpretation of the regulatory language, including a complete derivation of uni-variate order-statistics (as credited in AREVA’s Realistic Large Break LOCA methodology) and extension to multi-variate situations. Lastly, it provides recommendations for LOCA applications, endorsing the “Testing Method” and addressing acceptance methods allowing for limited sample failures.

  18. A randomised, crossover study on an electronic vapour product, a nicotine inhalator and a conventional cigarette. Part B: Safety and subjective effects.

    Science.gov (United States)

    Walele, Tanvir; Sharma, Girish; Savioz, Rebecca; Martin, Claire; Williams, Josie

    2016-02-01

    An Electronic Vapour Product (EVP) has been evaluated for short-term safety parameters and subjective effects in a 2-part study, in smokers. Part 1 compared the EVP with unflavoured (UF) and flavoured (FL) e-liquid at 2.0% nicotine to a conventional cigarette (CC; JPS Silver King Size, 0.6 mg) and a licensed nicotine inhalator (Nicorette(®), 15 mg). Part 2 assessed the effect of increasing concentrations of nicotine in the e-liquid used with the EVP (0%, 0.4%, 0.9%, 2.0%). The study was designed as a randomised, controlled, crossover trial. Outcomes included adverse events (AEs), vital signs, exhaled carbon monoxide (CO), clinical laboratory parameters, smoking urges and withdrawal symptoms. In both study parts, only mild non-serious AEs were reported. No major differences were observed in AEs between the EVPs and Nicorette(®). Exhaled CO levels only increased for CC. All products appeared to decrease smoking urges and nicotine withdrawal symptom scores to a similar extent. The EVP had a similar short-term safety profile to Nicorette(®) and relieved smoking urges and nicotine withdrawal symptoms to a similar extent as Nicorette(®) and CC. Unlike nicotine replacement therapies, the EVP may offer an alternative for those finding it difficult to quit the behavioural and sensorial aspects of smoking.

  19. Proceedings of the 2nd NUCEF international symposium NUCEF`98. Safety research and development of base technology on nuclear fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    This volume contains 68 papers presented at the 2nd NUCEF International Symposium NUCEF`98 held on 16-17 November 1998, in Hitachinaka, Japan, following the 1st symposium NUCEF`95 (Proceeding: JAERI-Conf 96-003). The theme of this symposium was `Safety Research and Development of Base Technology on Nuclear Fuel Cycle`. The papers were presented in oral and poster sessions on following research fields: (1) Criticality Safety, (2) Reprocessing and Partitioning, (3) Radioactive Waste Management. The 68 papers are indexed individually. (J.P.N.)

  20. 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.

  1. 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

  2. Operational readiness verification, phase 1: A study on safety during outage and restart of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hollnagel, E. [Linkoeping Univ. (Sweden). Dept. of Computer and Information Science; Gauthereau, V. [Linkoeping Univ. (Sweden). Dept. of Industrial Engineering

    2001-06-01

    This report contains the findings from the first phase of a study on safety during outage and restart of nuclear power plants. Operational Readiness Verification (ORV) - in Swedish called Driftklarhetsverifiering (DKV) - refers to the test and verification activities that are necessary to ensure that plant systems are able to provide their required functions when needed - more concretely that all plant systems are in their correct functional state when the plant is restarted after an outage period. The concrete background for this work is that nine ORV related incidents were reported in Sweden between July 1995 and October 1998. The work reported here comprised a literature survey of research relevant for ORV issues, and an assessment of the present situation at Swedish NPPs with respect to ORV. The literature survey was primarily aimed at research related to NPPs, but also looked at domains where similar problems have occurred, such as maintenance in commercial aviation. The survey looked specifically for organisational and MTO aspects relevant to the present situation in Swedish NPPs. One finding was that ORV should be seen as an integral part of maintenance, rather than as a separate activity. Another, that there is a characteristic distribution of error modes for maintenance and ORV, with many sequence errors and omissions, rather than a set of unique error modes. An international study further showed that there are important differences in how procedures are used, and in the balance between decentralisation and centralisation. Several studies also suggested that ORV could usefully be described as a barrier system in relation to the flow of work, for instance using the following five stages: (1) preventive actions during maintenance/outage, (2) post-test after completion of work, (3) pre-test before start-up, (4) the start-up sequence itself, and (5) preventive actions during power operation - possibly including automatic safety systems. In the field survey

  3. 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

  4. Research advances on engineering structural seismic safety of nuclear power plant%核电厂工程结构抗震研究进展

    Institute of Scientific and Technical Information of China (English)

    孔宪京; 林皋

    2013-01-01

      当前以及今后相当长一段时期,核电都将是中国积极发展的能源形式之一,保障核电安全是确保核电工程建设顺利实施和安全运营的关键。然而,中国幅员广阔,地质条件差异大,海域自然条件复杂;同时,中国地震活动范围广、强度大、频度高,基于标准化设计的核电工程结构在建设过程中面临着诸多问题。尤其是2011年日本大地震导致的福岛核电事故的教训,对核电工程的抗震安全提出了新的问题。结合大连理工大学十几年来在解决我国核电工程结构抗震安全中的关键问题,以及在“地震作用下核电厂工程结构的功能失效机理及抗震安全评价”研究中所取得若干进展进行综述性介绍,主要包括核岛地基抗震适应性研究和核岛安全相关工程结构抗震防灾研究。%Nuclear power is one of energy resources that China will vigorously develop for a long term from now on. The issue of nuclear power security guarantee is a key to ensure the smooth implementation and the safe operation of the nuclear power plant construction. However,because of the vast territory of China,the great differences in geological conditions and the complex natural conditions of ocean,as well as a wide range of seis-mic activity,high strength and high frequency of earthquakes in China,nuclear power buildings based on cur-rent standardized design methods are facing problems. Moreover,the lessons of the 2011 Fukushima nuclear ac-cident due to destructive earthquake come out new problems to Chinese seismic safety of nuclear power engineer-ing. In this paper,by combining engineering practice in recent years of nuclear power engineering seismic safety evaluation of the Dalian University of Technology,the key issues and the research methods in the structural seis-mic safety of Chinese nuclear power projects and some progress made by the Dalian University of Technology in the study of

  5. 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

  6. 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.

  7. Effect of Thermal Cycling on the Strength and Texture of Concrete for Nuclear Safety Structures

    Directory of Open Access Journals (Sweden)

    Š. Hošková

    2001-01-01

    Full Text Available The effect of thermal cycling (freezing and thawing on the texture and strength of two types of concrete is studied: 1. Concrete used for a containment structure at NPP Temelín (Czech Republic - so-called TEMELÍN concrete.2. Highly resistant PENLY concrete, which was used as a standard because of its high quality, proved by the research carried out in a European Commission project. The results for the two samples of concrete are compared.

  8. 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.

  9. Research on the improvement of nuclear safety -The development of a severe accident analysis code-

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Heui Dong; Cho, Sung Won; Park, Jong Hwa; Hong, Sung Wan; Yoo, Dong Han; Hwang, Moon Kyoo; Noh, Kee Man; Song, Yong Man [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    For prevention and mitigation of the containment failure during severe accident, the study is focused on the severe accident phenomena, especially, the ones occurring inside the cavity and is intended to improve existing models and develop analytical tools for the assessment of severe accidents. A correlation equation of the flame velocity of pre mixture gas of H{sub 2}/air/steam has been suggested and combustion flame characteristic was analyzed using a developed computer code. For the analysis of the expansion phase of vapor explosion, the mechanical model has been developed. The development of a debris entrainment model in a reactor cavity with captured volume has been continued to review and examine the limitation and deficiencies of the existing models. Pre-test calculation was performed to support the severe accident experiment for molten corium concrete interaction study and the crust formation process and heat transfer characteristics of the crust have been carried out. A stress analysis code was developed using finite element method for the reactor vessel lower head failure analysis. Through international program of PHEBUS-FP and participation in the software development, the research on the core degradation process and fission products release and transportation are undergoing. CONTAIN and MELCOR codes were continuously updated under the cooperation with USNRC and French developed computer codes such as ICARE2, ESCADRE, SOPHAEROS were also installed into the SUN workstation. 204 figs, 61 tabs, 87 refs. (Author).

  10. 47{sup th} Annual meeting on nuclear technology (AMNT 2016). Key Topics / Enhanced safety and operation excellence and decommissioning experience and Waste management solutions

    Energy Technology Data Exchange (ETDEWEB)

    Salnikova, Tatiana [AREVA GmbH, Erlangen (Germany); Schaffrath, Andreas [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany)

    2016-10-15

    Summary report on the Key Topics ''Enhanced Safety and Operation Excellence'' and ''Decommissioning Experience and Waste Management Solutions'' of the 47{sup th} Annual Conference on Nuclear Technology (AMNT 2016) held in Hamburg, 10 to 12 May 2016. Other Sessions of AMNT 2016 have been and will be covered in further issues of atw.

  11. The Path to Deep Nuclear Reductions. Dealing with American Conventional Superiority

    Energy Technology Data Exchange (ETDEWEB)

    Gormley, D.M.

    2009-07-01

    The transformation of the U.S. conventional capabilities has begun to have a substantial and important impact on counter-force strike missions particularly as they affect counter-proliferation requirements. So too have improvements in ballistic missile defense programs, which are also critically central to U.S. counter-proliferation objectives. These improved conventional capabilities come at a time when thinking about the prospects of eventually achieving a nuclear disarmed world has never been so promising. Yet, the path toward achieving that goal, or making substantial progress towards it, is fraught with pitfalls, including domestic political, foreign, and military ones. Two of the most important impediments to deep reductions in U.S. and Russian nuclear arsenals - no less a nuclear disarmed world - are perceived U.S. advantages in conventional counter-force strike capabilities working in combination with even imperfect but growing missile defense systems. The Barack Obama administration has already toned down the George W. Bush administration's rhetoric surrounding many of these new capabilities. Nevertheless, it is likely to affirm that it is a worthy goal to pursue a more conventionally oriented denial strategy as America further weans itself from its reliance on nuclear weapons. The challenge is to do so in the context of a more multilateral or collective security environment in which transparency plays the role it once did during the Cold War as a necessary adjunct to arms control agreements. Considerable thought has already been devoted to assessing many of the challenges along the way to a nuclear-free world, including verifying arsenals when they reach very low levels, more effective management of the civilian nuclear programs that remain, enforcement procedures, and what, if anything, might be needed to deal with latent capacities to produce nuclear weapons.1 But far less thought has been expended on why Russia - whose cooperation is absolutely

  12. 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.

  13. 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....

  14. 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.)

  15. 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...

  16. 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)

  17. 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.

  18. 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.

  19. 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...

  20. 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.

  1. 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....

  2. Europe's progress towards joint regulation of nuclear safety; Le cheminement de l'Europe vers une reglementation commune sur la surete nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Hennenhofer, G. [surete des installations nucleaires et la radioprotection, Ministere de l' Environnement, de la Protection de la nature et de la securite nucleaire (BMU) (Germany)

    2010-11-15

    Following the end of the Second World War, there was great hope for the use of nuclear energy for peaceful applications. In the beginning, the different approaches adopted by East and West led to the design of different types of reactors, with priority being given to rapid development of the reactor fleet. Cooperation between safety regulators only came about very gradually. The Chernobyl disaster was in this respect the trigger event, as it clearly showed that the effects of nuclear events do not stop at borders and that collaboration by the safety regulators in this field was essential. Texts such as the Convention on Nuclear Safety, requiring the creation of a regulatory body independent of economic interests, the other work done by IAEA on the issue of nuclear safety and, within the European context, the creation of WENRA, are all milestones along the path to close cooperation. The recently adopted European directive on the safety of nuclear installations is the natural successor to these achievements. The road to a common European vision of nuclear safety is now mapped out. Germany will be joining this movement and making its own contribution. (author)

  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. 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.

  7. 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…

  8. 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.

  9. 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.

  10. 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.)

  11. General safety considerations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-09-01

    This document presents the full filling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 4 of the document contains some details about the priority to safety, financial and human resources, human factors, quality assurance, safety assessment and verification, radiation protection and emergency preparedness.

  12. General safety considerations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This document presents the full filling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 4 of the document contains some details about the priority to safety, financial and human resources, human factors, quality assurance, safety assessment and verification, radiation protection and emergency preparedness.

  13. 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.

  14. Nuclear installations safety and protection: thirty years of researches on earthquakes at the IRSN; Surete et protection des installations nucleaires: trente ans de recherches a l'IRSN sur les seismes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-03-01

    Every years more than one hundred earthquakes occur in France. Taking into account this risk is essential for the safety of nuclear installations. In this context the IRSN develops research programs on earthquakes and realizes evolutions of safety procedures. This paper presents three sheets of researches realized by the IRSN on earthquakes risk assessment in the nuclear installations design and exploitation and the example of the Saint-Die earthquake. (A.L.B.)

  15. 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.)

  16. 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

  17. 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.

  18. 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.

  19. 46{sup th} Annual meeting on nuclear technology (AMNT 2015). Key topic / Enhanced safety and operation excellence / Sustainable reactor operation management - safe, efficient, valuable

    Energy Technology Data Exchange (ETDEWEB)

    Fischer, Erwin [E.ON Kernkraft GmbH, Global Unit Next Generation, Hannover (Germany)

    2015-08-15

    Summary report on the following Topical Session of the 46{sup th} Annual Conference on Nuclear Technology (AMNT 2015) held in Berlin, 5 to 7 May 2015: - Sustainable Reactor Operation Management - Safe, Efficient, Valuable (Erwin Fischer) The other Sessions of the Key Topics - ''Outstanding Know-How and Sustainable Innovations'', - ''Enhanced Safety and Operation Excellence'' and - ''Decommissioning Experience and Waste Management Solutions'' have been covered in atw 7 (2015) and will be covered in further issues of atw.

  20. Third national report of Brazil for the nuclear safety convention

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-09-15

    This document presents an activity report during the year of 2004, covering the following activities: corporate governance, sustainable development, internal control, controls and procedures for official financial information, evaluation of the controls and procedures by the internal audit, and financial statements.

  1. 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.

  2. 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.

  3. 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.

  4. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-05-15

    need to be carried out. Forsmarks Kraftgrupp AB (FKA) has applied for permission for power uprates at the Forsmark 1-3 reactors, OKG has applied for permission for power uprates at the Oskarshamn 3 reactor and RAB has applied for permission for power uprates at the Ringhals 1 and 3 reactors. SKI has reviewed the applications from OKG and RAB and has found that the necessary conditions exist for implementing the power uprates that have been requested. The Government has decided to grant permission for power uprates at Ringhals 1 and 3. SKI's regulations (SKIFS 2004:2) concerning the design and construction of nuclear reactors entered into force with certain transitional regulations on January 1, 2005. Through these regulations, SKI has developed and clarified the safety requirements for nuclear reactors. The transitional agreements mean that the licensees concerned must be given the necessary time to plan and implement the measures at the reactors that are necessary in order to comply with the regulations. The regulations mean that extensive measures need to be conducted at the reactors, especially the older reactors, in order to further improve safety to the modern level that the requirements entail. The safety improvement work will be conducted for a relatively long period of time. During the same period, power uprates are being planned at several reactors. During the year, SKI also decided on new regulations (SKIFS 2005:1) for the physical protection of nuclear facilities. These regulations will also have extensive consequences for the licensees, through more stringent regulations with respect to area protection, perimeter protection and access control. During the year, SKI continued to follow up and promote the further development of the licensees' internal audit functions, management systems and competence assurance processes. SKI notes that continued improvements have been implemented and that the independent audit functions have been reinforced among

  6. Heat treatments in a conventional steel to reproduce the microstructure of a nuclear grade steel; Tratamientos termicos en un acero convencional para reproducir la microestructura de un acero grado nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Rosalio G, M.

    2014-07-01

    The ferritic steels used in the manufacture of pressurized vessels of Boiling Water Reactors (BWR) suffer degradation in their mechanical properties due to damage caused by the neutron fluxes of high energy bigger to a Mega electron volt (E> 1 MeV) generated in the reactor core. The materials with which the pressurized vessels of nuclear reactors cooled by light water are built correspond to low alloy ferritic steels. The effect of neutron irradiation on these steels is manifested as an increase in hardness, mechanical strength, with the consequent decrease in ductility, fracture toughness and an increase in temperature of ductile-brittle transition. The life of a BWR is 40 years, its design must be considered sufficient margin of safety because pressure forces experienced during operation, maintenance and testing of postulated accident conditions. It is necessary that under these conditions the vessel to behave ductile and likely to propagate a fracture is minimized. The vessels of light water nuclear reactors have a bainite microstructure. Specifically, the reactor vessels of the nuclear power plant of Laguna Verde (Veracruz, Mexico) are made of a steel Astm A-533, Grade B Class 1. At present they are carrying out some welding tests for the construction of a model of a BWR, however, to use nuclear grade steel such as Astm A-533 to carry out some of the welding tests, is very expensive; perform these in a conventional material provides basic information. Although the microstructure present in the conventional material does not correspond exactly to the degree of nuclear material, it can take of reference. Therefore, it is proposed to conduct a pilot study to establish the thermal treatment that reproduces the microstructure of nuclear grade steel, in conventional steel. The resulting properties of the conventional steel samples will be compared to a JRQ steel, that is a steel Astm A-533, Grade B Class 1, provided by IAEA. (Author)

  7. The influence of individual and team cognitive ability on operators' task and safety performance: a multilevel field study in nuclear power plants.

    Science.gov (United States)

    Zhang, Jingyu; Li, Yongjuan; Wu, Changxu

    2013-01-01

    While much research has investigated the predictors of operators' performance such as personality, attitudes and motivation in high-risk industries, its cognitive antecedents and boundary conditions have not been fully investigated. Based on a multilevel investigation of 312 nuclear power plant main control room operators from 50 shift teams, the present study investigated how general mental ability (GMA) at both individual and team level can influence task and safety performance. At the individual level, operators' GMA was predictive of their task and safety performance and this trend became more significant as they accumulated more experience. At the team level, we found team GMA had positive influences on all three performance criteria. However, we also found a "big-fish-little-pond" effect insofar as team GMA had a relatively smaller effect and inhibited the contribution of individual GMA to workers' extra-role behaviors (safety participation) compared to its clear beneficial influence on in-role behaviors (task performance and safety compliance). The possible mechanisms related to learning and social comparison processes are discussed.

  8. The Influence of Individual and Team Cognitive Ability on Operators’ Task and Safety Performance: A Multilevel Field Study in Nuclear Power Plants

    Science.gov (United States)

    Zhang, Jingyu; Li, Yongjuan; Wu, Changxu

    2013-01-01

    While much research has investigated the predictors of operators’ performance such as personality, attitudes and motivation in high-risk industries, its cognitive antecedents and boundary conditions have not been fully investigated. Based on a multilevel investigation of 312 nuclear power plant main control room operators from 50 shift teams, the present study investigated how general mental ability (GMA) at both individual and team level can influence task and safety performance. At the individual level, operators’ GMA was predictive of their task and safety performance and this trend became more significant as they accumulated more experience. At the team level, we found team GMA had positive influences on all three performance criteria. However, we also found a “big-fish-little-pond” effect insofar as team GMA had a relatively smaller effect and inhibited the contribution of individual GMA to workers’ extra-role behaviors (safety participation) compared to its clear beneficial influence on in-role behaviors (task performance and safety compliance). The possible mechanisms related to learning and social comparison processes are discussed. PMID:24391964

  9. 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)

  10. The Impact of Organizational Factors on Safety. The Perspective of Experts from the Spanish Nuclear Sector; El Impacto de los Factores Organizativos en la Seguridad. La Vision de los Expertos del Sector Nuclear Espanol

    Energy Technology Data Exchange (ETDEWEB)

    German, S.; Silla, I.; Navajas, J.

    2014-07-01

    Previous research supports the importance of organizational factors on safety in high reliability organizations. This study aims to determine the impact of those factors in the Spanish nuclear sector. Particularly, this study focuses on examining the role of performance indicators, organizational culture, organizational factors, and organizational context. With that purpose, an electronic survey addressed to experts from the Spanish nuclear sector was carried out. Results showed that performance indicators are well-known among industry experts and are perceived as useful for improving performance. Behavioural norms that influence safety and some relevant factors that promote problem identification were identified. Additionally, findings suggested that organizational context must be taken into account to better understand the role of organizational culture. Moreover, industry experts pointed out organizational factors to be improved: organizational communication processes within the organization, positive reinforcement, and field supervisors practices. Finally, findings supported the influence of organizational context on safety. It is noteworthy the role of the social impact of international events (e.g., Chernobyl...), the relationship with the regulator and the legislative and governmental framework. (Author)

  11. 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.

  12. Combining Total Monte Carlo and Benchmarks for Nuclear Data Uncertainty Propagation on a Lead Fast Reactor's Safety Parameters

    Science.gov (United States)

    Alhassan, E.; Sjöstrand, H.; Duan, J.; Gustavsson, C.; Koning, A. J.; Pomp, S.; Rochman, D.; Österlund, M.

    2014-04-01

    Analyses are carried out to assess the impact of nuclear data uncertainties on keff for the European Lead Cooled Training Reactor (ELECTRA) using the Total Monte Carlo method. A large number of 239Pu random ENDF-formatted libraries generated using the TALYS based system were processed into ACE format with NJOY-99.336 code and used as input into the Serpent Monte Carlo neutron transport code to obtain distribution in keff. The mean of the keff distribution obtained was compared with the major nuclear data libraries, JEFF-3.1.1, ENDF/B-VII.1 and JENDL-4.0. A method is proposed for the selection of benchmarks for specific applications using the Total Monte Carlo approach. Finally, an accept/reject criterion was investigated based on χ2 values obtained using the 239Pu Jezebel criticality benchmark. It was observed that nuclear data uncertainties in keff were reduced considerably from 748 to 443 pcm by applying a more rigid acceptance criteria for accepting random files.

  13. 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)

  14. 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,...

  15. The Environmental Impact of Electrical Generation: Nuclear vs. Conventional.

    Science.gov (United States)

    McDermott, John J., Ed.

    This minicourse, partially supported by the Division of Nuclear Education and Training of the U.S. Atomic Energy Commission, is an effort to describe the benefit-to-risk ratio of various methods of generating electrical power. It attempts to present an unbiased, straightforward, and objective view of the advantages and disadvantages of nuclear…

  16. 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.

  17. 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

  18. 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

  19. 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.

  20. 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.

  1. 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.

  2. PERFORMANCE OF CONVENTIONAL PCRs BASED ON PRIMERS DIRECTED TO NUCLEAR AND MITOCHONDRIAL GENES FOR THE DETECTION AND IDENTIFICATION OF Leishmania spp.

    Science.gov (United States)

    LOPES, Estela Gallucci; GERALDO, Carlos Alberto; MARCILI, Arlei; SILVA, Ricardo Duarte; KEID, Lara Borges; OLIVEIRA, Trícia Maria Ferreira da Silva; SOARES, Rodrigo Martins

    2016-01-01

    In visceral leishmaniasis, the detection of the agent is of paramount importance to identify reservoirs of infection. Here, we evaluated the diagnostic attributes of PCRs based on primers directed to cytochrome-B (cytB), cytochrome-oxidase-subunit II (coxII), cytochrome-C (cytC), and the minicircle-kDNA. Although PCRs directed to cytB, coxII, cytC were able to detect different species of Leishmania, and the nucleotide sequence of their amplicons allowed the unequivocal differentiation of species, the analytical and diagnostic sensitivity of these PCRs were much lower than the analytical and diagnostic sensitivity of the kDNA-PCR. Among the 73 seropositive animals, the asymptomatic dogs had spleen and bone marrow samples collected and tested; only two animals were positive by PCRs based on cytB, coxII, and cytC, whereas 18 were positive by the kDNA-PCR. Considering the kDNA-PCR results, six dogs had positive spleen and bone marrow samples, eight dogs had positive bone marrow results but negative results in spleen samples and, in four dogs, the reverse situation occurred. We concluded that PCRs based on cytB, coxII, and cytC can be useful tools to identify Leishmania species when used in combination with automated sequencing. The discordance between the results of the kDNA-PCR in bone marrow and spleen samples may indicate that conventional PCR lacks sensitivity for the detection of infected dogs. Thus, primers based on the kDNA should be preferred for the screening of infected dogs. PMID:27253743

  3. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, January--March 1977

    Energy Technology Data Exchange (ETDEWEB)

    Card, D. H. [ed.

    1977-06-01

    A test series to evaluate the effectiveness of different emergency core coolant injection arrangements was completed. A LOFT test series was initiated to investigate the effect of break nozzle geometry on break flow and system response during a 200 percent double-ended cold leg break test. Two analyses of results of LOFT nonnuclear experiments were made. The intact loop flow resistance on LOFT system responses during loss-of-coolant experiments was evaluated. The second in a series of five tests to evaluate the effects of fuel density, initial gap width, and fill gas composition on gap conductance was performed with four BWR-type rods tested simultaneously. A test was conducted to provide steady state, power ramp, and film boiling operation behavior data on the fuel rods constructed from irradiated and unirradiated cladding and to investigate the influence of simulated fission products on cladding integrity and performance. Cladding ballooning phenomena were also investigated. Results of preliminary postirradiation examinations of irradiation effects, power-cooling mismatch, and gap conductance tests performed previously are reported. A review of FLECHT and Semiscale forced feed and gravity feed reflood heat transfer experiments was performed. A study to predict and compare surface temperature response of Semiscale electrically heated rods with LOFT nuclear rods during a Semiscale blowdown was completed. SPERT and NSRR data were analyzed to evaluate fuel failure modes and the effect of energy deposition for cold-startup conditions.

  4. Quarterly report on Defense Nuclear Facilities Safety Board Recommendation 90-7 for the period ending June 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Cash, R.J.; Dukelow, G.T.; Forbes, C.J.; Meacham, J.E.

    1993-10-01

    This is the ninth quarterly report on the progress of activities that address safety issues associated with Hanford Site high-level radioactive waste tanks containing ferrocyanide compounds. Milestones completed this quarter include (1) a report on the credibility of hot spots and a recommendation on infrared scans; (2) a document discussing the strength and limitations of proposed moisture monitoring technologies; (3) limited calibration of the neutron probe in simulant-filled drums; (4) a report interpreting data from auger surface samples of ferrocyanide tank 241-BY-104; (5) a document on the effect of possible catalyst, initiator, and diluents on ferrocyanide reactivity; (6) a report on small scale sensitivity tests of ferrocyanide flowsheet simulants; and (7) preparation and shipment of T Plant simulants for calorimetric and dryout tests.

  5. Spinal radiosurgery - efficacy and safety after prior conventional radiotherapy

    Directory of Open Access Journals (Sweden)

    Nikolajek Katharina

    2011-12-01

    Full Text Available Abstract Background Conventional external beam radiotherapy is a standard procedure for treatment of spinal metastases. In case of progression spinal cord tolerance limits further radiotherapy in pre-irradiated areas. Spinal stereotactic radiotherapy is a non-invasive option to re-treat pre-irradiated patients. Nevertheless, spinal radiosurgery results in relevant dose deposition within the myelon with potential toxicity. Aim of the study was to retrospectively analyse the efficacy and feasibility for salvage radiosurgery of spinal metastases. Methods During a period of 4 years (2005-2009 70 lesions in 54 patients were treated in 60 radiosurgery sessions and retrospectively analysed. Clinical (pain, sensory and motor deficit and radiological (CT/MRI follow-up data were collected prospectively after radiosurgery. Pain - as main symptom - was classified by the Visual Analogue Scale (VAS score. Every patient received single session radiosurgery after having been treated first-line with conventionally fractionated radiotherapy. Kaplan-Meier method and life tables were used to analyse freedom from local failure and overall survival. Results At a median follow-up of 14.5 months the actuarial rates of freedom from local failure at 6/12/18 months were 93%, 88% and 85%, respectively. The median radiosurgery dose was 1 × 18 Gy (range 10-28 Gy to the median 70% isodose. The VAS score of patients with pain (median 6 dropped significantly (median 4, p = 0.002. In 6 out of 7 patients worse sensory or motor deficit after SRS was caused by local or distant failures (diagnosed by CT/MRI. One patient with metastatic renal cell carcinoma developed a progressive complete paraparesis one year after the last treatment at lumbar level L3. Due to multiple surgery and radiosurgery treatments at the lumbar region and further local progression, the exact reason remained unclear. Apart from that, no CTC grade III or higher toxicity has been observed. Conclusions By

  6. 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.

  7. 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

  8. Safety studies on Korean fusion DEMO plant using integrated safety assessment methodology

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Kyemin; Kang, Myoung-suk [Kyung Hee University, Youngin-si, Gyeonggi-do 446-701 (Korea, Republic of); Heo, Gyunyoung, E-mail: gheo@khu.ac.kr [Kyung Hee University, Youngin-si, Gyeonggi-do 446-701 (Korea, Republic of); Kim, Hyoung-chan [National Fusion Research Institute, Daejeon-si 305-333 (Korea, Republic of)

    2014-10-15

    Highlights: •The purpose of this paper is to suggest methodology that can investigate safety issues and provides a case study for Korean fusion DEMO plant. •The concepts of integrated safety assessment methodology (ISAM) that can be applied in addressing regulatory requirements and recognizing safety issues for K-DEMO were emphasized. •Phenomena identification and ranking table (PIRT) was proposed. It can recognize vulnerabilities of systems and identify the gaps in technical areas requiring additional researches. •This work is expected to contribute on the conceptual design of safety features for K-DEMO to design engineers and the guidance for regulatory requirements to licensers. -- Abstract: The purpose of this paper is to suggest methodology that can investigate safety issues and provides a case study for Korean fusion DEMO plant (K-DEMO) as a part of R and D program through the National Fusion Research Institute of Korea. Even though nuclear regulation and licensing framework is well setup due to the operating and design experience of Pressurized Water Reactors (PWRs) since 1970s, the regulatory authority of South Korea has concerns on the challenge of facing new nuclear facilities including K-DEMO due to the differences in systems, materials, and inherent safety feature from conventional PWRs. Even though the follow-up of the ITER license process facilitates to deal with significant safety issues of fusion facilities, a licensee as well as a licenser should identify the gaps between ITER and DEMO in terms of safety issues. First we reviewed the methods of conducting safety analysis for unprecedented nuclear facilities such as Generation IV reactors, particularly very high temperature reactor (VHTR), which is called as integrated safety assessment methodology (ISAM). Second, the analysis for the conceptual design of K-DEMO on the basis of ISAM was conducted. The ISAM consists of five analytical tools to develop the safety requirements from licensee

  9. 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.

  10. Experimental and numerical investigations on the direct contact condensation phenomenon in horizontal flow channels and its implications in nuclear safety

    Energy Technology Data Exchange (ETDEWEB)

    Ceuca, Sabin Cristian [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany); Laurinavicius, Darius [Lithuanian Energy Institute, Kaunas (Lithuania)

    2016-11-15

    The complex direct contact condensation phenomenon is investigated in horizontal flow channels both experimentally and numerically with special emphasis on its implications on safety assessment studies. Under certain conditions direct contact condensation can act as the driving force for the water hammer phenomenon with potentially local devastating results, thus posing a threat to the integrity of the affected NPP components. New experimental results of in-depth analysis of the direct contact condensation phenomena obtained in Kaunas at the Lithuanian Energy Institute will be presented. The German system code ATHLET employing for the calculation of the heat transfer coefficient a mechanistic model accounting for two different eddy length scales, combined with the interfacial area transport equation will be assessed against condensation induced water hammer experimental data from the integral thermal-hydraulic experimental facility PMK-2, located at the KFKI Atomic Energy Research Institute in Budapest Hungary.

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  15. Transactions of the fifth symposium on space nuclear power systems

    Energy Technology Data Exchange (ETDEWEB)

    El-Genk, M.S.; Hoover, M.D. (eds.)

    1988-01-01

    This paper contains the presented papers at the fourth symposium on space nuclear power systems. Topics of these paper include: space nuclear missions and applications, reactors and shielding, nuclear electric and nuclear propulsion, high-temperature materials, instrumentation and control, energy conversion and storage, space nuclear fuels, thermal management, nuclear safety, simulation and modeling, and multimegawatt system concepts. (LSP)

  16. Transactions of the fourth symposium on space nuclear power systems

    Energy Technology Data Exchange (ETDEWEB)

    El-Genk, M.S.; Hoover, M.D. (eds.)

    1987-01-01

    This paper contains the presented papers at the fourth symposium on space nuclear power systems. Topics of these papers include: space nuclear missions and applications, reactors and shielding, nuclear electric and nuclear propulsion, refractory alloys and high-temperature materials, instrumentation and control, energy conversion and storage, space nuclear fuels, thermal management, nuclear safety, simulation and modeling, and multimegawatt system concepts. (LSP)

  17. 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.

  18. 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.)

  19. 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.

  20. 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.

  1. 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....

  2. 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.

  3. 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)

  4. 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)

  5. 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.

  6. 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.

  7. 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.

  8. 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)

  9. 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.

  10. 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。

  11. 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.)

  12. 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.

  13. 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

  14. 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.

  15. 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

  16. 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.

  17. 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)

  18. 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.

  19. 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.

  20. 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.).

  1. 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.

  2. 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.

  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. 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

  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. 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.

  7. Risk Analysis on Safety Injection Test of PWR Nuclear Power Plant%压水堆核电厂安注试验风险研究

    Institute of Scientific and Technical Information of China (English)

    徐永华

    2012-01-01

    During the safety injection (SI) test in the PWR nuclear power plant, full water in pressurizer and high-high level, low-low level in SG may take place. This paper analyzes the risks and response measures in the SI test. Focusing on the full scale problem of pressurizer thermal calibration level gauge in the SI test of nuclear power plant, the test process is analyzed and the problems that should be noted in the SI test are summed up.%在压水堆核电厂安注试验期间,可能出现稳压器满水及主蒸汽发生器(SG)高高、低低液位等问题.本文分析了安注试验的风险及应对措施;针对某核电厂进行安注试验时稳压器热态标定液位计满量程问题,对试验过程进行分析,并总结出安注试验中应注意的问题.

  8. Russia’s Conventional Military Weakness and Substrategic Nuclear Policy

    Science.gov (United States)

    2011-01-01

    February 8, 2011, Lithuanian Defense Minister Rasa Jukneviciene alleged that Russia had moved SSNW into Kaliningrad , bordering both Poland and... Kaliningrad . And to our east as well,” Jukneviciene told Lithuanian public radio. Moscow had dismissed similar allegations in November 2010. She made...the absence of 27. any clarity on the possible Russian response Kaliningrad effectively being cut off were the scenario to be implemented. Citing an

  9. 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

  10. 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.

  11. Research on Fuzzy Comprehensive Assessment Method of Nuclear Power Plant Safety Culture%核电厂安全文化的模糊综合评价方法研究

    Institute of Scientific and Technical Information of China (English)

    项媛媛; 陈徐坤; 许荣斌

    2012-01-01

    Considering the traits of safety culture in nuclear plant, 38 safety culture assessment inde-xes are established from 4 aspects such as safety values, safety institution, safety behavior and safety sub-stances. Based on it, a comprehensive assessment method for nuclear power plant safety culture is con-structed by using AHP (Analytic Hierarchy Process) approach and fuzzy mathematics. The comprehensive assessment method has the quality of high precision and high operability, which can support the decision making of safety culture development.%根据核电厂的特点,从安全文化四个形态层面——安全观念、安全制度、安全行为与安全物态出发,建立了38项安全文化评价指标,并应用层次分析法(AHP)和模糊数学理论,提出核电厂安全文化的模糊综合评价方法。该方法能较为准确地评价核电厂的安全文化水平,为核电厂营运单位确定安全文化建设战略目标提供有力依据。

  12. 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)

  13. 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.

  14. 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.

  15. Auditory localisation of conventional and electric cars : laboratory results and implications for cycling safety

    NARCIS (Netherlands)

    Stelling-Konczak, A. Hagenzieker, M.P. Commandeur, J.J.F. Agterberg, M.J.H. & Wee, B. van

    2016-01-01

    When driven at low speeds, cars operating in electric mode have been found to be quieter than conventional cars. As a result, the auditory cues which pedestrians and cyclists use to assess the presence, proximity and location oncoming traffic may be reduced, posing a safety hazard. This laboratory s

  16. Auditory localisation of conventional and electric cars : laboratory results and implications for cycling safety.

    NARCIS (Netherlands)

    Stelling-Konczak, A. Hagenzieker, M.P. Commandeur, J.J.F. Agterberg, M.J.H. & Wee, B. van

    2016-01-01

    When driven at low speeds, cars operating in electric mode have been found to be quieter than conventional cars. As a result, the auditory cues which pedestrians and cyclists use to assess the presence, proximity and location oncoming traffic may be reduced, posing a safety hazard. This laboratory s

  17. Auditory localisation of conventional and electric cars : laboratory results and implications for cycling safety.

    NARCIS (Netherlands)

    Stelling-Konczak, A. Hagenzieker, M.P. Commandeur, J.J.F. Agterberg, M.J.H. & Wee, B. van

    2016-01-01

    When driven at low speeds, cars operating in electric mode have been found to be quieter than conventional cars. As a result, the auditory cues which pedestrians and cyclists use to assess the presence, proximity and location oncoming traffic may be reduced, posing a safety hazard. This laboratory

  18. 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.

  19. 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.

  20. 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.

  1. 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...

  2. 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)

  3. Development of a methodology for safety classification on a non-reactor nuclear facility illustrated using an specific example; Entwicklung einer Methodik zur Sicherheitsklassifizierung fuer eine kerntechnische Anlage ohne Reaktor an einem spezifischen Beispiel

    Energy Technology Data Exchange (ETDEWEB)

    Scheuermann, F.; Lehradt, O.; Traichel, A. [NUKEM Technologies Engineering Services GmbH, Alzenau (Germany)

    2015-07-01

    To realize the safety of personnel and environment systems and components of nuclear facilities are classified according to their potential danger into safety classes. Based on this classification different demands on the manufacturing quality result. The objective of this work is to present the standardized method developed by NUKEM Technologies Engineering Services for the categorization into the safety classes restricted to Non-reactor nuclear facilities (NRNF). Exemplary the methodology is used on the complex Russian normative system (four safety classes). For NRNF only the lower two safety classes are relevant. The classification into the lowest safety class 4 is accordingly if the maximum resulting dose following from clean-up actions in case of incidents/accidents remains below 20 mSv and the volume activity restrictions of set in NRB-99/2009 are met. The methodology is illustrated using an example. In short the methodology consists of: - Determination of the working time to remove consequences of incidents, - Calculation of the dose resulting from direct radiation and due to inhalation during these works. The application of this methodology avoids over-conservative approaches. As a result some previously higher classified equipment can be classified into the lower safety class.

  4. Risk-informed regulation and safety management of nuclear power plants--on the prevention of severe accidents.

    Science.gov (United States)

    Himanen, Risto; Julin, Ari; Jänkälä, Kalle; Holmberg, Jan-Erik; Virolainen, Reino

    2012-11-01

    There are four operating nuclear power plant (NPP) units in Finland. The Teollisuuden Voima (TVO) power company has two 840 MWe BWR units supplied by Asea-Atom at the Olkiluoto site. The Fortum corporation (formerly IVO) has two 500 MWe VVER 440/213 units at the Loviisa site. In addition, a 1600 MWe European Pressurized Water Reactor supplied by AREVA NP (formerly the Framatome ANP--Siemens AG Consortium) is under construction at the Olkiluoto site. Recently, the Finnish Parliament ratified the government Decision in Principle that the utilities' applications to build two new NPP units are in line with the total good of the society. The Finnish utilities, Fenno power company, and TVO company are in progress of qualifying the type of the new nuclear builds. In Finland, risk-informed applications are formally integrated in the regulatory process of NPPs that are already in the early design phase and these are to run through the construction and operation phases all through the entire plant service time. A plant-specific full-scope probabilistic risk assessment (PRA) is required for each NPP. PRAs shall cover internal events, area events (fires, floods), and external events such as harsh weather conditions and seismic events in all operating modes. Special attention is devoted to the use of various risk-informed PRA applications in the licensing of Olkiluoto 3 NPP.

  5. 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.

  6. 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.

  7. 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

  8. The European ASAMPSA_E project : towards guidance to model the impact of high amplitude natural hazards in the probabilistic safety assessment of nuclear power plants. Information on the project progress and needs from the geosciences.

    Science.gov (United States)

    Raimond, Emmanuel; Decker, Kurt; Guigueno, Yves; Klug, Joakim; Loeffler, Horst

    2015-04-01

    The Fukushima nuclear accident in Japan resulted from the combination of two correlated extreme external events (earthquake and tsunami). The consequences, in particular flooding, went beyond what was considered in the initial engineering design design of nuclear power plants (NPPs). Such situations can in theory be identified using probabilistic safety assessment (PSA) methodology. PSA results may then lead industry (system suppliers and utilities) or Safety Authorities to take appropriate decisions to reinforce the defence-in-depth of the NPP for low probability event but high amplitude consequences. In reality, the development of such PSA remains a challenging task. Definitions of the design basis of NPPs, for example, require data on events with occurrence probabilities not higher than 10-4 per year. Today, even lower probabilities, down to 10-8, are expected and typically used for probabilistic safety analyses (PSA) of NPPs and the examination of so-called design extension conditions. Modelling the combinations of natural or man-made hazards that can affect a NPP and affecting some meaningful probability of occurrence seems to be difficult. The European project ASAMPSAE (www.asampsa.eu) gathers more than 30 organizations (industry, research, safety control) from Europe, US and Japan and aims at identifying some meaningful practices to extend the scope and the quality of the existing probabilistic safety analysis developed for nuclear power plants. It offers a framework to discuss, at a technical level, how "extended PSA" can be developed efficiently and be used to verify if the robustness of Nuclear Power Plants (NPPs) in their environment is sufficient. The paper will present the objectives of this project, some first lessons and introduce which type of guidance is being developed. It will explain the need of expertise from geosciences to support the nuclear safety assessment in the different area (seismotectonic, hydrological, meteorological and biological

  9. 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

  10. 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.

  11. 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...

  12. 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

  13. Regulatory analysis for the resolution of Generic Safety Issue 29: Bolting degradation or failure in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Chang, T.Y.

    1991-09-01

    Generic Safety Issue (GSI)-29 deals with staff concerns about public risk due to degradation or failure of safety-related bolting in nuclear power plants. The issue was initiated in November 1982. Value-impact studies of a mandatory program on safety-related bolting for operating plants were inconclusive: therefore, additional regulatory requirements for operating plants could not be justified in accordance with provisions of 10 CFR 50.109. In addition, based on operating experience with bolting in both nuclear and conventional power plants, the actions already taken through bulletins, generic letters, and information notices, and the industry-proposed actions, the staff concluded that a sufficient technical basis exists for the resolution of GSI-29. The staff further concluded that leakage of bolted pressure joints is possible but catastrophic failure of a reactor coolant pressure boundary joint that will lead to significant accident sequences is highly unlikely. For future plants, it was concluded that a new Standard Review Plant section should be developed to codify existing bolting requirements and industry-developed initiatives. 9 refs., 1 tab.

  14. 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

  15. 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.

  16. 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.

  17. 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...

  18. 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,...

  19. 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. ...

  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. Recent trends in ILO conventions related to occupational safety and health.

    Science.gov (United States)

    Wilson, Donald J; Takahashi, Ken; Smith, Derek R; Yoshino, Masako; Tanaka, Chieko; Takala, Jukka

    2006-01-01

    The present study was conducted to analyze the ratification status of International Labour Organization (ILO) conventions related to occupational safety and health (OSH) by ILO member states in terms of national indicators (length of ILO membership and national income status) and regional affiliation. 17 conventions designated as OSH-related by the 2003 International Labour Conference were examined. In general, countries with longer ILO membership ratified higher numbers of conventions related to OSH. With some variation, long-membership countries had the largest number of ratifications, followed by middle- and short-membership countries in all regions. There were also incremental increases in the number of ratifications for OSH-related conventions according to the national income status. Common regional characteristics that could not be explained by the factors studied also existed. Future efforts to increase ratification at an international level will need to consider the factors influencing ratification practice among the member states.

  2. Comparison of Obstetric Efficacy and Safety of the Kiwi OmniCup with Conventional Vacuum Extraction.

    Science.gov (United States)

    Siggelkow, W; Schwarz, N; Beckmann, M W; Kehl, S; Faschingbauer, F; Schild, R L

    2014-02-01

    Purpose: The aim of the present study was to compare the safety and efficacy of the Kiwi OmniCup system with conventional vacuum delivery. Methods: A retrospective study of operative vaginal deliveries was done for 4682 births. The procedures included 217 operative vaginal deliveries (4.6 %), 79 of which were done using conventional vacuum extraction (37 %) and 138 using the Kiwi system (63 %). Results: Use of the Kiwi system was associated with a significant reduction in episiotomies (61 vs. 76 % in the control group; p Kiwi system and 99 % with conventional vacuum delivery). Cup detachment occurred significantly more often in the Kiwi group (p Kiwi system is an acceptable alternative to the conventional vacuum cup. The advantages of the Kiwi system are its significantly lower episiotomy rate and its ease and rapidity of use.

  3. One safety critical indicators model for regulatory actions on nuclear power plants based on a level 1 PSA; Um modelo de indicadores criticos de seguranca para acoes regulatorias em usinas nucleares baseado em uma APS nivel 1

    Energy Technology Data Exchange (ETDEWEB)

    Araujo, Jefferson Borges

    2006-03-15

    This study presents a general methodology to the establishment, selection and use of safety indicators for a two loop PWR plant, as Angra 1. The study performed identifies areas considered critical for the plant operational safety. For each of these areas, strategic sub-areas are defined. For each strategic sub-area, specific safety indicators are defined. These proposed Safety Indicators are based on the contribution to risk considering a quantitative risk analysis. For each safety indicator, a goal, a bounded interval and proper bases are developed, to allow for a clear and comprehensive individual behavior evaluation. Additionally, an integrated evaluation of the indicators, using expert systems, was done to obtain an overview of the plant general safety. This methodology can be used for identifying situations where the plant safety is challenged, by giving a general overview of the plant operational condition. Additionally, this study can also identify eventual room for improvements by generating suggestions and recommendations, as a complement for regulatory actions and inspections, focusing resources on eventual existing weaknesses, in order to increase or maintain a high pattern of operational safety. (author)

  4. 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.

  5. M310核电站非能动安全改进措施研究%Study on Passive Safety Improvement of M310 Nuclear Power Station

    Institute of Scientific and Technical Information of China (English)

    邹象; 郎明刚

    2015-01-01

    A severe accident model of typical M310 nuclear power station with MELCOR 1.8.5 code was constructed in this paper .Based on the model ,several passive safety measures were designed ,and their benefits of mitigating the accident caused by station blackout (SBO) were simulated .The calculating results show that the core makeup tank system , external reactor vessel cooling system and passive residual heat removal system can operate successfully in SBO , postpone the progression of the accident markedly , stabilize the M310 nuclear power station in a safe state and gain more time for manual intervention .%本文利用MELCOR1.8.5程序建立了典型的M310核电站的严重事故模型,基于该模型设计了多种非能动的缓解措施,针对由全厂断电诱发的严重事故,模拟研究了这些非能动安全措施的缓解效果。研究结果表明:在全厂断电事故下,堆芯补水箱系统、堆腔注水系统、非能动余热排出系统均能有效地投入使用,并显著地延缓事故的发展,将核电站稳定在一个安全的状态,为人工干预赢得更多时间。

  6. 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.

  7. 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.

  8. 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.

  9. General digitalized system on nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Akagi, Katsumi; Kadohara, Hozumi; Taniguchi, Manabu [Mitsubishi Electric Corp., Tokyo (Japan)

    2000-08-01

    Hitherto, instrumentation control system in a PWR nuclear power plant has stepwisely adopted digital technology such as application of digital instrumentation control device to ordinary use (primary/secondary system control device, and so on), application of CRT display system to monitoring function, and so forth, to realize load reduction of an operator due to expansion of operation automation range, upgrading of reliability and maintenance due to self-diagnosis function, reduction of mass in cables due to multiple transfer, and upgrading of visual recognition due to information integration. In next term PWR plant instrumentation control system, under consideration of application practice of conventional digital technology, application of general digitalisation system to adopt digitalisation of overall instrumentation control system containing safety protection system, and central instrumentation system (new type of instrumentation system) and to intend to further upgrade economics, maintenance, operability/monitoring under security of reliability/safety is planned. And, together with embodiment of construction program of the next-term plant, verification at the general digitalisation proto-system aiming at establishment of basic technology on the system is carried out. Then, here was described on abstract of the general digitalisation system and characteristics of a digital type safety protection apparatus to be adopted in the next-term plant. (G.K.)

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  16. 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.

  17. Nuclear law bulletin supplement to no. 72

    CERN Document Server

    2003-01-01

    When the Joint Convention on the Safety of Spent Fuel Management and on the Safety ofRadioactive Waste Management1 came into force in June 2002, following by almost five years theentry into force of the Convention on Nuclear Safety (CNS),2 the major elements3 of the InternationalAtomic Energy Agency's long-planned international legal regime on nuclear safety4 appeared to befinally in place. This fact might have been expected to be a cause for general satisfaction, if not

  18. 46 CFR 109.103 - Requirements of the International Convention for Safety of Life at Sea, 1974.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Requirements of the International Convention for Safety of Life at Sea, 1974. 109.103 Section 109.103 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY... Convention for Safety of Life at Sea, 1974. No self-propelled unit of more than 500 gross tons may embark...

  19. 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.

  20. 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).

  1. 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.

  2. 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.

  3. Preferences for food safety and animal welare - a choice experiment study comparing organic and conventional consumers

    DEFF Research Database (Denmark)

    Christensen, Tove; Mørkbak, Morten; Denver, Sigrid;

    Food quality attributes such as food safety and animal welfare are increasingly influencing consumers' choices of food products. These attributes are not readily traded in the markets. Hence, stated preference methods have proven to be valuable tools for eliciting preferences for such non...... that organic consumers have a higher willingness to pay for animal welfare than other consumers, but they are not willing to pay more than conventional consumers when it comes to their willingness to pay for avoiding campylobacter....

  4. Information report made on the behalf of the European Affairs Commission on European policy for nuclear safety; Rapport d'information fait au nom de la commission des affaires europeennes (1) sur la politique europeenne de surete nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Bizet, J.; Sutour, S.

    2011-05-15

    This report aims at defining some perspectives for the evolution of the European general legal framework for nuclear safety. The authors first outline the difficulty for a European policy to emerge. They explain this statement by the importance of the current policy of national states, of their operators and of their national regulation authorities. They evoke the few elements of this legal framework (EURATOM Treaty, jurisprudence) but outline the strong cooperation between national authorities. Then, they discuss some progresses which have been noticed during the past two years (the 'safety' directive, a proposition for a directive on the management of used fuel and radioactive wastes, and the recent works by WENRA), and discuss the consequences of the accident in Fukushima. Propositions are made, notably concerning the support to the 'waste' directive, the perpetuation of strength tests, the rewriting of the 'safety' directive of June 2009

  5. 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。

  6. 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

  7. 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.

  8. 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.

  9. 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/.

  10. Cognitive Targeting: A Coercive Air Power Theory for Conventional Escalation Control Against Nuclear Armed Adversaries

    Science.gov (United States)

    2016-06-01

    COGNITIVE TARGETING: A COERCIVE AIR POWER THEORY FOR CONVENTIONAL ESCALATION CONTROL AGAINST NUCLEAR- ARMED ADVERSARIES BY PAUL A. GOOSSEN, MAJ...process with both critical analysis and with encouragement. Most importantly, I want to express my most sincere appreciation to my family. Their love...regional powers such as North Korea, the post-Cold War geo-political environment characterized by U.S. hegemony is fading away. In the emerging

  11. 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)

  12. 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.

  13. 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.

  14. Study on Safety of Sub-critical Nuclear Power Reactor%次临界能源堆安全性研究

    Institute of Scientific and Technical Information of China (English)

    周喆; 汪俊; 张慧敏

    2015-01-01

    The sub‐critical nuclear power reactor is composed by the Tokamak device in the center and the fission blanket surrounding it .A design layout of the fuel and coolant channel of the fission blanket was offered in the paper ,in which the safety analysis was done .The CFD code was used for the thermal‐hydraulic design and safety analysis of coolant channel blocked accident . The RELAP code was used to simulate the fission blanket of the sub‐critical nuclear power reactor , and the inherent safety of it was researched .By the analysis ,some safety weak points were found and related sugges‐tions were provided for the future safety improvement of the sub‐critical nuclear power reactor .%次临界能源堆由中心的托卡马克装置和围绕其的裂变包层组成。本文根据物理和热工专业分析计算得出的一种针对其裂变包层的燃料和冷却剂通道布置方式,分析设计的包层结构安全性和工程应用中的安全性。包层结构安全性分析使用C FD方法,计算了正常运行工况和冷却剂通道堵管的情况,得到堵管发生后包层的局部状况。通过RELAP程序模拟了裂变包层参与核电厂发电运行过程中,其本身所具有的固有安全性。本文通过计算发现了其安全上的薄弱环节,并提出了改进措施,为以后改进次临界能源堆安全性提供参考。

  15. Investigations on boron carbide oxidation for nuclear reactors safety-General modelling for ICARE/CATHARE code applications

    Energy Technology Data Exchange (ETDEWEB)

    Seiler, N. [Institut de Radioprotection et de Surete Nucleaire (IRSN), Cadarache, BP 3, 13 115 Saint Paul lez Durance Cedex (France)], E-mail: nathalie.seiler@irsn.fr; Bertrand, F.; Marchand, O.; Repetto, G. [Institut de Radioprotection et de Surete Nucleaire (IRSN), Cadarache, BP 3, 13 115 Saint Paul lez Durance Cedex (France); Ederli, S. [ENEA, Ente per le Nuove Tecnologie l' Energia et l' Ambiente (Italy)

    2008-04-15

    The present paper deals with the problem of boron carbide pellet oxidation which might occur during a severe accident. A basic correlation, involving global variables, has been developed for the simulation of boron carbide oxidation with the ICARE/CATHARE code. This modelling has been based on available experimental data, including the VERDI separate effects experiments performed by IRSN at low pressures and high temperatures. According to the agreement between the measured and the calculated bundle temperatures as well as hydrogen release and oxidized B{sub 4}C, the ICARE/CATHARE code simulates rather well QUENCH experiments involving B{sub 4}C control rod degradation, Zircaloy oxidation under starvation and cooling with steam. Based on simulations results, it has been noticed that the B{sub 4}C degradation has a slight direct effect on global bundle degradation but a non-negligible influence on Zircaloy oxidation through power release, material melting and flowing down.

  16. Discussion on safety management of nuclear power engineering in general contracting mode%总承包模式下核电工程安全管理相关问题探讨

    Institute of Scientific and Technical Information of China (English)

    赵显; 刘勃

    2014-01-01

    The characteristics of safety management on nuclear power engineering in general contracting mode, which were different from the common construction projects, were analyzed.Then the main problems in current safety management of nuclear power engineering construction were put forward, such as lagging of relevant laws and regulations, the contradiction between expansion of nuclear power construction project and lack of human resources, the labor subcontracting system and safety problems brought by its working personnel, and passive regulation of safety production costs etc.These problems would directly impact the existing work safety defense line, and bring unprecedented challenge to safety management work of general contractor.So the suggestions and countermeasures were put forward, including that the relevant government departments should publish the relevant laws and regula-tions about general contracting of project as soon as possible, the general contractor should fully integrate on-site safety management resources, strengthen the safety management on subcontractors, strengthen safety training of the labor service personnel, and explore the management mode of work safety costs.%首先分析了总承包模式下核电工程建设不同于一般建设工程安全管理的特点,提出目前工作中存在的主要问题,包括相关法律法规的滞后、核电建设工程扩张与人力资源不足之间的矛盾、劳务分包体制及其作业人员引起的相关问题以及安全生产费用监管被动等,这些都直接冲击现有的安全生产防线,并给总承包单位安全管理工作带来前所未有的挑战。为此,提出以下建议和对策措施:有关部门尽快出台总承包工程相关法律法规;总承包单位应充分整合现场安全管理资源,加大对分包单位安全管理力度,加强劳务作业人员安全培训,探索安全生产费用管理模式等。

  17. 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.

  18. Reports on research work in the field of the safety of nuclear facilities financed by the Federal Minister of the Interior. Period under report: 1st October - 31th December 1980 (17th quarterly report on SR-projects)

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    The BMI (Home Office) finances the performance of studies, expert's reports and other investigations in the field of the safety of nuclear facilities. The results of these studies (CSR-projects) are meant to contribute to the elucidation of still open questions concerning the atomic licensing procedure. The GRS, who are charged by the BMI, give regular information on the state-of-affairs of such investigations. This is done quarterly resp., annually by editing progrss reports within the report series GRS-F. These reports serve to inform the authorities of the Bund and Laender afflicted as well as the reactor safety commission. Each progress report presents a compilation of individual reports arranged according to subject fields. These are written by the contractors themselves in a standardized form as a documentation of the progress of their work and edited by the supervisory board of the GRS (GRS-FB) within the framework of the general information on progress within the investigations on the safety of nuclear facilities. The individual reports are marked in the order of their arrangement with successive numbers. Each report contains, among other things, data on the objective targets, the work performed, the results gained and the continuation of work planned.

  19. 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.

  20. 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.

  1. Perspectives on reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States)

    1994-03-01

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

  2. 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

  3. Comparison of the Microbiological Quality and Safety between Conventional and Organic Vegetables Sold in Malaysia

    Science.gov (United States)

    Kuan, Chee-Hao; Rukayadi, Yaya; Ahmad, Siti H.; Wan Mohamed Radzi, Che W. J.; Thung, Tze-Young; Premarathne, Jayasekara M. K. J. K.; Chang, Wei-San; Loo, Yuet-Ying; Tan, Chia-Wanq; Ramzi, Othman B.; Mohd Fadzil, Siti N.; Kuan, Chee-Sian; Yeo, Siok-Koon; Nishibuchi, Mitsuaki; Radu, Son

    2017-01-01

    Given the remarkable increase of public interest in organic food products, it is indeed critical to evaluate the microbiological risk associated with consumption of fresh organic produce. Organic farming practices including the use of animal manures may increase the risk of microbiological contamination as manure can act as a vehicle for transmission of foodborne pathogens. This study aimed to determine and compare the microbiological status between organic and conventional fresh produce at the retail level in Malaysia. A total of 152 organic and conventional vegetables were purchased at retail markets in Malaysia. Samples were analyzed for mesophilic aerobic bacteria, yeasts and molds, and total coliforms using conventional microbiological methods. Combination methods of most probable number-multiplex polymerase chain reaction (MPN-mPCR) were used to detect and quantify foodborne pathogens, including Escherichia coli O157:H7, Shiga toxin-producing E. coli (STEC), Listeria monocytogenes, Salmonella Typhimurium, and Salmonella Enteritidis. Results indicated that most types of organic and conventional vegetables possessed similar microbial count (P > 0.05) of mesophilic aerobic bacteria, yeasts and molds, and total coliforms. E. coli O157:H7 and S. Typhimurium were not detected in any sample analyzed in this study. Among the 152 samples tested, only the conventional lettuce and organic carrot were tested positive for STEC and S. Enteritidis, respectively. L. monocytogenes were more frequently detected in both organic (9.1%) and conventional vegetables (2.7%) as compared to E. coli O157:H7, S. Typhimurium, and S. Enteritidis. Overall, no trend was shown that either organically or conventionally grown vegetables have posed greater microbiological risks. These findings indicated that one particular type of farming practices would not affect the microbiological profiles of fresh produce. Therefore, regardless of farming methods, all vegetables should be subjected to

  4. Comparison of the Microbiological Quality and Safety between Conventional and Organic Vegetables Sold in Malaysia

    Directory of Open Access Journals (Sweden)

    Chee-Hao Kuan

    2017-07-01

    Full Text Available Given the remarkable increase of public interest in organic food products, it is indeed critical to evaluate the microbiological risk associated with consumption of fresh organic produce. Organic farming practices including the use of animal manures may increase the risk of microbiological contamination as manure can act as a vehicle for transmission of foodborne pathogens. This study aimed to determine and compare the microbiological status between organic and conventional fresh produce at the retail level in Malaysia. A total of 152 organic and conventional vegetables were purchased at retail markets in Malaysia. Samples were analyzed for mesophilic aerobic bacteria, yeasts and molds, and total coliforms using conventional microbiological methods. Combination methods of most probable number-multiplex polymerase chain reaction (MPN-mPCR were used to detect and quantify foodborne pathogens, including Escherichia coli O157:H7, Shiga toxin-producing E. coli (STEC, Listeria monocytogenes, Salmonella Typhimurium, and Salmonella Enteritidis. Results indicated that most types of organic and conventional vegetables possessed similar microbial count (P > 0.05 of mesophilic aerobic bacteria, yeasts and molds, and total coliforms. E. coli O157:H7 and S. Typhimurium were not detected in any sample analyzed in this study. Among the 152 samples tested, only the conventional lettuce and organic carrot were tested positive for STEC and S. Enteritidis, respectively. L. monocytogenes were more frequently detected in both organic (9.1% and conventional vegetables (2.7% as compared to E. coli O157:H7, S. Typhimurium, and S. Enteritidis. Overall, no trend was shown that either organically or conventionally grown vegetables have posed greater microbiological risks. These findings indicated that one particular type of farming practices would not affect the microbiological profiles of fresh produce. Therefore, regardless of farming methods, all vegetables should be

  5. 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.

  6. 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

  7. Three-dimensional all-speed CFD code for safety analysis of nuclear reactor containment: Status of GASFLOW parallelization, model development, validation and application

    Energy Technology Data Exchange (ETDEWEB)

    Xiao, Jianjun, E-mail: jianjun.xiao@kit.edu [Institute of Nuclear and Energy Technologies, Karlsruhe Institute of Technology, P.O. Box 3640, 76021 Karlsruhe (Germany); Travis, John R., E-mail: jack_travis@comcast.com [Engineering and Scientific Software Inc., 3010 Old Pecos Trail, Santa Fe, NM 87505 (United States); Royl, Peter, E-mail: peter.royl@partner.kit.edu [Institute of Nuclear and Energy Technologies, Karlsruhe Institute of Technology, P.O. Box 3640, 76021 Karlsruhe (Germany); Necker, Gottfried, E-mail: gottfried.necker@partner.kit.edu [Institute of Nuclear and Energy Technologies, Karlsruhe Institute of Technology, P.O. Box 3640, 76021 Karlsruhe (Germany); Svishchev, Anatoly, E-mail: anatoly.svishchev@kit.edu [Institute of Nuclear and Energy Technologies, Karlsruhe Institute of Technology, P.O. Box 3640, 76021 Karlsruhe (Germany); Jordan, Thomas, E-mail: thomas.jordan@kit.edu [Institute of Nuclear and Energy Technologies, Karlsruhe Institute of Technology, P.O. Box 3640, 76021 Karlsruhe (Germany)

    2016-05-15

    Highlights: • 3-D scalable semi-implicit pressure-based CFD code for containment safety analysis. • Robust solution algorithm valid for all-speed flows. • Well validated and widely used CFD code for hydrogen safety analysis. • Code applied in various types of nuclear reactor containments. • Parallelization enables high-fidelity models in large scale containment simulations. - Abstract: GASFLOW is a three dimensional semi-implicit all-speed CFD code which can be used to predict fluid dynamics, chemical kinetics, heat and mass transfer, aerosol transportation and other related phenomena involved in postulated accidents in nuclear reactor containments. The main purpose of the paper is to give a brief review on recent GASFLOW code development, validations and applications in the field of nuclear safety. GASFLOW code has been well validated by international experimental benchmarks, and has been widely applied to hydrogen safety analysis in various types of nuclear power plants in European and Asian countries, which have been summarized in this paper. Furthermore, four benchmark tests of a lid-driven cavity flow, low Mach number jet flow, 1-D shock tube and supersonic flow over a forward-facing step are presented in order to demonstrate the accuracy and wide-ranging capability of ICE’d ALE solution algorithm for all-speed flows. GASFLOW has been successfully parallelized using the paradigms of Message Passing Interface (MPI) and domain decomposition. The parallel version, GASFLOW-MPI, adds great value to large scale containment simulations by enabling high-fidelity models, including more geometric details and more complex physics. It will be helpful for the nuclear safety engineers to better understand the hydrogen safety related physical phenomena during the severe accident, to optimize the design of the hydrogen risk mitigation systems and to fulfill the licensing requirements by the nuclear regulatory authorities. GASFLOW-MPI is targeting a high

  8. Conventional and Nuclear Medicine Imaging in Ectopic Cushing's Syndrome: A Systematic Review

    Science.gov (United States)

    Isidori, Andrea M.; Sbardella, Emilia; Zatelli, Maria Chiara; Boschetti, Mara; Vitale, Giovanni; Colao, Annamaria

    2015-01-01

    Context: Ectopic Cushing's Syndrome (ECS) can be a diagnostic challenge with the hormonal source difficult to find. This study analyzes the accuracy of imaging studies in ECS localization. Evidence Acquisition: Systematic review of medical literature for ECS case series providing individual patient data on at least one conventional imaging technique (computed tomography [CT]/magnetic resonance imaging) and one of the following: 111In-pentetreotide (OCT), 131I/123I-metaiodobenzylguanidine, 18F-fluoro-2-deoxyglucose-positron emission tomography (FDG-PET), 18F-fluorodopa-PET (F-DOPA-PET), 68Ga-DOTATATE-PET/CT or 68Ga-DOTATOC-PET/CT scan (68Gallium-SSTR-PET/CT). Evidence Summary: The analysis comprised 231 patients (females, 50.2%; age, 42.6 ± 17 y). Overall, 52.4% (121/231) had “overt” ECS, 18.6% had “occult” ECS, and 29% had “covert” ECS. Tumors were located in the lung (55.3%), mediastinum-thymus (7.9%), pancreas (8.5%), adrenal glands (6.4%), gastrointestinal tract (5.4%), thyroid (3.7%), and other sites (12.8%), and primary tumors were mostly bronchial neuroendocrine tumors (NETs) (54.8%), pancreatic NETs (8%), mediastinum-thymus NETs (6.9%), gastrointestinal NETs (5.3%), pheochromocytoma (6.4%), neuroblastoma (3.2%), and medullary thyroid carcinoma (3.2%). Tumors were localized by CT in 66.2% (137/207), magnetic resonance imaging in 51.5% (53/103), OCT in 48.9% (84/172), FDG-PET in 51.7% (46/89), F-DOPA-PET in 57.1% (12/21), 131/123I-metaiodobenzylguanidine in 30.8% (4/13), and 68Gallium-SSTR-PET/CT in 81.8% (18/22) of cases. Molecular imaging discovered 79.1% (53/67) of tumors unidentified by conventional radiology, with OCT the most commonly used, revealing the tumor in 64%, followed by FDG-PET in 59.4%. F-DOPA-PET was used in only seven covert cases (sensitivity, 85.7%). Notably, 68Gallium-SSTR-PET/CT had 100% sensitivity among covert cases. Conclusions: Nuclear medicine improves the sensitivity of conventional radiology when tumor site

  9. 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.

  10. 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.

  11. 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)

  12. 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

  13. 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.

  14. 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.).

  15. 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

  16. Nuclear characteristics of the endometrial cytology: liquid-based versus conventional preparation.

    Science.gov (United States)

    Norimatsu, Yoshiaki; Shigematsu, Yumie; Sakamoto, Shingo; Ohsaki, Hiroyuki; Yanoh, Kenji; Kawanishi, Namiki; Kobayashi, Tadao K

    2013-02-01

    The aim of this study was to assess the utility of liquid-based cytologic preparation (LP) compared with conventional preparation (CP) for the assessment of nuclear findings in endometrial glandular and stromal breakdown (EGBD) which may be misdiagnosed as carcinoma in EGBD cases. The material consists of cytologic smears including 20 cases of proliferative endometrium (PE), 20 cases of EGBD, and 20 cases of endometrioid adenocarcinoma grade1 (G1) for which histopathological diagnosis was obtained by endometrial curettage at the JA Suzuka General Hospital. Nuclear findings were examined in PE cells, EGBD-stromal cells, EGBD-metaplastic cells, and G1 cells, respectively. It was examined about the following items; (1) nuclear shape; (2) A long/minor axis ratio in cell nuclei; (3) an area of cell nuclei; (4) overlapping nuclei. Results are as follows: (1) nuclear shape; as for the reniform shape of EGBD-stromal cells and spindle shape of EGBD-metaplastic cells, the ratio of the LP method was a higher value than the CP method. (2) The long axis and area of cell nuclei; LP in all groups was a recognizable tendency for nuclear shrinkage. (3) The long/minor axis ratio in cell nuclei; only EGBD-metaplastic cells recognize a significant difference between CP and LP. (4) Overlapping nuclei; LP was a higher value in comparison with CP in the other groups except PE cells, and the degree of overlapping nuclei was enhanced about three times. Therefore, although a cell of LP has a shrinking tendency, (1) it is excellent that LP preserves a characteristic of nuclear shape than CP; (2) a cellular characteristic becomes clearer, because three-dimensional architecture of LP is preserved of than CP. As for the standard preparation method for endometrial cytology samples, we considered that a concrete introduction of the LP method poses no problems.

  17. 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).

  18. 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)

  19. The ratification status of ILO conventions related to occupational safety and health and its relationship with reported occupational fatality rates.

    Science.gov (United States)

    Wilson, Donald J; Takahashi, Ken; Sakuragi, Sonoko; Yoshino, Masako; Hoshuyama, Tsutomu; Imai, Teppei; Takala, Jukka

    2007-01-01

    The aim of this study was to assess the relationship between the ratification status of occupational safety and health (OSH)-related ILO conventions and reported occupational fatality rates of ILO member countries, while controlling for possible confounding factors. ILO member states were divided into 4 levels of income status, based on the gross national income per capita. Seventeen conventions designated as OSH-related were examined. Reported country occupational fatality rates were compared according to the ratification status of these 17 conventions and multiple regression analyses were conducted to assess the relationship between the fatality rates, ratification status, income level and length of ILO membership. Fatality rates were inversely and significantly related to income levels. In general, non-ratifying countries had higher work-related fatality rates than ratifying countries. A statistical model for identifying predictors of fatal injury rates showed that a larger number of conventions ratified was significantly associated with lower fatality rates. The fact that non-ratifying countries generally have higher fatality rates than ratifying ones supports the notion that all countries should promote ratification of ILO conventions aimed at improving OSH conditions.

  20. 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).

  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. A study on the human reliability analysis in probabilistic safety assessment during low power/shutdown operation of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kang, D. I.; Sung, T. Y.; Jung, W. D.; Yang, J. E.; Park, J. H.; Lee, Y. H.; Hwang, M. J.; Kim, K. Y.; Jin, Y. H

    1997-02-01

    This report describes the review results of human reliability analysis (HRA) in the probabilistic safety assessment (PSA) during low power/shutdown operation of nuclear power plants (NPPs). We select four NPP PSA reports to review. These are System 80+ using THERP, Surry using SLIM, Grand Gulf using ASEP, Electric de France using simulator experiments. This report also describe the method, the procedure, the quantification example, the critical review and the insights of HRA which were used in the process of PSA of NPPs mentioned above. It is expected that this study results will be effectively used in HRA of domestic PSA during low power/shutdown operation of NPPs. (author). 18 refs., 1 tab.

  3. 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.

  4. 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 ...

  5. Bonus systems and their effects on safety: an interview-based pilot study at the Swedish nuclear power plants; Bonussystem och dess inverkan paa saekerheten: en intervjubaserad pilotstudie vid de svenska kaernkraftverken

    Energy Technology Data Exchange (ETDEWEB)

    Torbioern, Ingemar; Mattson, Malin (Inst. of Psychology, Stockholm Univ., Stockholm (Sweden))

    2009-03-15

    The aim of this pilot study has been to describe and analyse potential effects on safety-related behaviour and risks associated with the bonus systems currently used at Swedish nuclear plants. To this end and in order to establish a frame of reference several theories on motivation were consulted regarding the relevance of monetary rewards. In addition empirical evidence on effects upon behaviours in general and safety behaviours in particular was taken into consideration, as well as a systems and a rationalist perspective on organisations. The resulting frame of reference was used for a descriptive mapping of the bonus systems and for the formulation of a semi-structured interview schedule intended to capture the experiences of those concerned by the systems. A total of 15 interviews were performed with staff of different functions and organisational positions. Results of the study do not indicate any negative effects on safety-related behaviours. Rather they indicate that safety-behaviours may be promoted insofar as bonus rewards are linked to performance goals concerning safety. All of the bonus-systems may be characterised as low in incentive intensity, i.e. produce small effects on motivation and performance. Still, as the systems differ in design and in the way they are perceived, they also represent different challenges in order to function more efficiently as parameters

  6. Numerical Analysis on Key Structure of Super High Pressure Hydraulic Bolt Stretcher for Conventional Island of Nuclear Power%核电常规岛用超高液压螺栓拉伸器关键结构的数值分析

    Institute of Scientific and Technical Information of China (English)

    张澄东; 浦琪琦; 张江涛; 李萍

    2014-01-01

    针对核电常规岛用螺栓拉伸器具有超高压、超小空间作业工况的特性,提出一种基于数值分析与实验相接合的设计方法,运用ANSYS软件对螺栓拉伸器关键结构---缸体与螺帽进行有限元校核,并与测定的应变实验数据进行对比;同时分析参数Rm、D对螺帽结构的优化特性。研究结果表明:初设的缸体强度和刚度满足材料的要求,但螺帽在“L型”截面拐点处出现“负”安全系数;优化螺帽结构尺寸,当Rm =8 mm,D=60 mm时与初设参数相比应力减小了121.2%,应变减小了58%,安全系数得到极大提高,这为该设备的可靠性和安全性提供了设计依据。%Aiming at the characteristics that the bolt stretcher for conventional island of nuclear power has the ultra high pres-sure,ultra small space operation conditions,a design method based on numerical analysis and experiment was presented,the ANSYS software was used to check the cylinder block and blind nut,and the analysis results were compared with the experimental strain data. The optimization characteristices of the parameters Rm ,D on the blind nut were analyzed. The results show that:the strength and stiff-ness of first set of cylinder block can meet the material requirements,but the blind nut has“negative”safety factor in the inflection point of“L”section;optimizing the blind nut structure size,when Rm and D are equal to 8 mm and 60 mm respectively,the stress de-creases by 121.2% and the strain decreases by 58% comparing with initial parameters,the safety coefficient is heightened,which pro-vides design basis for the reliability and safety of the equipment.

  7. 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)

  8. 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.

  9. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    2008-07-01

    The safety level of the plants is maintained at an acceptable level. SKI has in its regulatory supervision not found any known deficiencies in the barriers which could result in release of radioactive substances in excess of the permitted levels. SKI considers that improvements have been implemented during the year in the management, control and following up of safety work at the plants. In some cases, SKI has imposed requirements that improvements be made. Extensive measures are under way at the nuclear power plants to comply with the safety requirements in SKI's regulations, SKIFS 2004:2 concerning the design and construction of nuclear power reactors, and the stricter requirements regarding physical protection. Concurrently preparations are underway at eight of the ten units for thermal power increases. At the Forsmark plant considerable efforts have been during the year to correct the deficiencies in the safety culture and quality assurance system that became apparent in 2006. A programme to improve the execution of activities has been established in accordance with SKI's decision. SKI considers that the plant has developed in a positive direction but that there are further possibilities for improvement with regard to internal control. This is amongst other things concerns the areas internal auditing, independent safety review function, and working methods. SKI has had special supervision of the plant since 28 September, 2006. At the Oskarshamn plant work has been carried out to improve the organisation and routines in several areas. The plant has established routines which provide the basis to ensure that decisions are taken in a stringent manner. The quality assurance system has a clearer structure and there is a better defined division of work. Some measures remain to be dealt with in 2008. The Ringhals plant has also worked with attitudes to routines and internal control. SKI considers that the measures have good prerequisites to provide a

  11. 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.

  12. Evaluation of conventional power systems. [emphasizing fossil fuels and nuclear energy

    Science.gov (United States)

    Smith, K. R.; Weyant, J.; Holdren, J. P.

    1975-01-01

    The technical, economic, and environmental characteristics of (thermal, nonsolar) electric power plants are reviewed. The fuel cycle, from extraction of new fuel to final waste management, is included. Emphasis is placed on the fossil fuel and nuclear technologies.

  13. Rolls-Royce successful modernization of safety-critical Instrumentation and Control (I and C) equipment at the Dukovany VVER 440/213 Nuclear Power Plant, based on SPINLINE 3 platform

    Energy Technology Data Exchange (ETDEWEB)

    Rebreyend, P.; Burel, J.P. [Rolls-Royce Civil Nuclear SAS (France); Spoc, J. [Skoda JS (Czech republic); Karasek, A. [CEZ a.s.(Czech republic)

    2010-07-01

    Rolls-Royce has provided on-time delivery of a substantial safety-critical I and C overhaul for four Nuclear reactors operated by Czech Republic utility, CEZ a.s. This nine-year project is considered to be one of the largest I and C modernization projects in the world. The Dukovany VVER 440 I and C modernization project and its key success factors are profiled in this paper. The project is in the final stages with the last unit to be completed in 2009. Beginning in September 2000, the project is in compliance with the initial schedule. Rolls-Royce has been designing and manufacturing I and C solutions dedicated to the implementation of safety and safety-related functions in nuclear power plants (NPPs) for more than 30 years. Though the early solutions were non-software-based, since 1984 software-based solutions for safety I and C functions have been deployed in operating NPPs across France and 15 other countries. The Rolls-Royce platform is suitable for implementation of safety I and C functions in new NPPs, as well as in the modernization of safety equipment in existing plants. CEZ a.s. is a major electricity supplier for the national grid. At Dukovany, CEZ a.s. operates four units of VVER-440/213-type reactors producing one quarter of CEZ a.s. electricity production. The first of these units was connected to the grid in 1985. Since the year 2000, the nine-year modernization program has been underway at Dukovany, at a cost of more than 200 million Euros. The equipment replacement was implemented during regular, planned outages of the original equipment and systems. After an international bidding phase, CEZ a.s. awarded a contract to Skoda JS for general engineering and project management. Individual subcontracts were then signed between Skoda JS and a consortium between Rolls-Royce and Areva for modernization of the safety systems, including the Reactor Protection System (RPS), the Reactor Control System (RCS), and the Post-Accident Monitoring System (PAMS). Two

  14. 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)

  15. From Risk Analysis to the Safety Case. Values in Risk Assessments. A Report Based on Interviews with Experts in the Nuclear Waste Programs in Sweden and Finland. A Report from the RISCOM II Project

    Energy Technology Data Exchange (ETDEWEB)

    Drottz Sjoeberg, Britt-Marie [Norwegian Univ. of Science and Technology, Trondheim (Norway). Dept. of Psychology

    2004-06-01

    The report focuses on values in risk assessment, and is based on interviews with safety assessment experts and persons working at the national authorities in Sweden and Finland working in the area of nuclear waste management. The interviews contained questions related to definitions of risk and safety, standards, constraints and degrees of freedom in the work, data collections, reliability and validity of systems and the safety assessments, as well as communication between experts, and experts and non-experts. The results pointed to an increased amount of data and relevant factors considered in the analyses over time, changing the work content and process from one of risk analysis to a multifaceted teamwork towards the assessment of 'the safety case'. The multifaceted systems approach highlighted the increased importance of investigating assumptions underlying e.g. integration of diverse systems, and simplification procedures. It also highlighted the increased reliance on consensus building processes within the extended expert group, the importance of adequate communication abilities within the extended expert group, as well as the importance of transparency and communication relative the larger society. The results are discussed with reference to e.g. Janis 'groupthink' theory and Kuhns ideas of paradigmatic developments in science. It is concluded that it is well advised, in addition to the ordinary challenges of the work, to investigate also the implicit assumptions involved in the work processes to further enhance the understanding of safety assessments.

  16. 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

  17. 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.

  18. 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)

  19. Progress on nuclear modifications of structure functions

    CERN Document Server

    Kumano, S

    2016-01-01

    We report progress on nuclear structure functions, especially on their nuclear modifications and a new tensor structure function for the deuteron. To understand nuclear structure functions is an important step toward describing nuclei and QCD matters from low to high densities and from low to high energies in terms of fundamental quark and gluon degrees of freedom beyond conventional hadron and nuclear physics. It is also practically important for understanding new phenomena in high-energy heavy-ion collisions at RHIC and LHC. Furthermore, since systematic errors of current neutrino-oscillation experiments are dominated by uncertainties of neutrino-nucleus interactions, such studies are valuable for finding new physics beyond current framework. Next, a new tensor-polarized structure function $b_1$ is discussed for the deuteron. There was a measurement by HERMES; however, its data are inconsistent with the conventional convolution estimate based on the standard deuteron model with D-state admixture. This fact ...

  20. 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.)

  1. 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

  2. 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

  3. 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

  4. 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,...

  5. 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)

  6. 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.)

  7. 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.

  8. 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.

  9. Study on nuclear power introduction into Vietnam

    Energy Technology Data Exchange (ETDEWEB)

    Vuong Huu Tan [Vietnam Atomic Energy Commission, 59 Ly Thuong Kiet, Hanoi (Viet Nam)

    2000-03-01

    The report presents main results of the study on nuclear power introduction into Vietnam which have been carried out at Vietnam Atomic Energy Commission in collaboration with Ministry of Industry of Vietnam and other countries like Japan, Canada and Korea. The study covers all topics related to the nuclear power introduction into Vietnam such as electricity demands and supply, economics, finance, technology, safety, manpower, site selection etc. (author)

  10. 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.

  11. 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...

  12. Safety Management. An Introduction to a Frame of Reference Exemplified with Case Studies from Non-Nuclear Contexts

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-11-15

    A systems perspective on safety management is introduced followed by two briefly presented case studies of safety management in non-nuclear contexts. The first study concerns a car manufacturer and the second study a road traffic tunnel system. The risks of a car accident in the first case study are evident. The great exposure generates many incidents and accidents. In the second study, the rather low traffic intensity through the tunnel produces few incidents and accidents and only a few fatal accidents over the years. Yet, the risk of the individual traveler is much greater in the tunnel than on the average road. The case studies are presented in a systems perspective with emphasis on information feedback about the risks of the systems. The first case study illustrates high quality safety management, while the second case study shows many weaknesses of the safety management in the tunnel system. Some differences in safety management between the case studies are noted. The last part of the study presents an organizational perspective on safety management and offers alternative theoretical perspectives on the concept of safety management. The report shows that further studies are needed both (1) to develop a frame of reference for describing safety management across industries and activities and (2) to collect data illustrating of good and poor safety management. Then, the results can be used to strengthen and/or improving safety management in the nuclear power industry and its regulators

  13. 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.

  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. Vulnerability, safety and response of nuclear power plants to the hydroclimatic hazards

    Science.gov (United States)

    János Katona, Tamás; Vilimi, András

    2016-04-01

    practice demonstrated that the NPPs could safely withstand the meteorological extremes (Katrina hurricane, 2005). However the floods at some sites cause significant safety issues. Design of NPPs and their response to extreme hydroclimatic events depends on the features of particular hazards, e.g., predictability, possibility and time available for the protective actions, potential for causing cliff-edge effects and the possible combinations of events. The uncertainty of the prediction of extreme values for the design and safety assessment is a fundamental issue. In the paper the consequences of hydroclimatic extremes are analysed for nuclear power plants. The possibility of operational response to extremes is presented. The safety margins are assessed with respect to the effects caused by hydroclimatic extremes. The direct actions (e.g. wind) and the indirect consequences (e.g. changing of ground water level) are also considered. Methods for accounting the uncertainties of the characterisation of low probability hazards are also considered. The preparedness to severe hydroclimatic conditions / events and actions for mitigation and management are presented and discussed. The considerations in the paper are illustrated by the case of the Paks Nuclear Power Plant, Hungary.

  16. Fessenheim plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident; Fessenheim - Rapport d'evaluation complementaire de la surete des installations nucleaires au regard de l'accident de Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-09-15

    This CSA (Complementary Safety Assessment) analyses the robustness of the Fessenheim plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)

  17. The German atomic law on trial. The requirements of the EURATOM Nuclear Safety Directive; Deutsches Atomrecht auf dem Pruefstand. Die Anforderungen aus der EURATOM-Richtlinie zur nuklearen Sicherheit

    Energy Technology Data Exchange (ETDEWEB)

    Mueller-Dehn, Christian [E.ON Kernkraft GmbH, Hannover (Germany). Nuclear Regulation and Policy

    2016-05-15

    The EURATOM Directive on Nuclear Safety, dated 8 July 2014, is to be transposed into national law, not later than 15 August 2017. This raises the question of whether and to what extent by then the German atomic energy act is adapted to the respective requirements. On national level requirements have to be implemented now, that are already not effective. This includes the introduction of thematic peer reviews and, if necessary, regulations for the independence and effectiveness of the regulatory authorities. Here - but only here - is a need for implementation.

  18. Annual report to Congress. Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, calendar year 2000

    Energy Technology Data Exchange (ETDEWEB)

    None

    2001-03-01

    This Annual Report to the Congress describes the Department of Energy's activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board. During 2000, the Department completed its implementation and proposed closure of one Board recommendation and completed all implementation plan milestones associated with two additional Board recommendations. Also in 2000, the Department formally accepted two new Board recommendations and developed implementation plans in response to those recommendations. The Department also made significant progress with a number of broad-based safety initiatives. These include initial implementation of integrated safety management at field sites and within headquarters program offices, issuance of a nuclear safety rule, and continued progress on stabilizing excess nuclear materials to achieve significant risk reduction.

  19. Annual report to Congress. Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, calendar year 2000

    Energy Technology Data Exchange (ETDEWEB)

    None

    2001-03-01

    This Annual Report to the Congress describes the Department of Energy's activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board. During 2000, the Department completed its implementation and proposed closure of one Board recommendation and completed all implementation plan milestones associated with two additional Board recommendations. Also in 2000, the Department formally accepted two new Board recommendations and developed implementation plans in response to those recommendations. The Department also made significant progress with a number of broad-based safety initiatives. These include initial implementation of integrated safety management at field sites and within headquarters program offices, issuance of a nuclear safety rule, and continued progress on stabilizing excess nuclear materials to achieve significant risk reduction.

  20. Multicentre safety of adding Focal Impulse and Rotor Modulation (FIRM) to conventional ablation for atrial fibrillation.

    Science.gov (United States)

    Krummen, David E; Baykaner, Tina; Schricker, Amir A; Kowalewski, Christopher A B; Swarup, Vijay; Miller, John M; Tomassoni, Gery F; Park, Shirley; Viswanathan, Mohan N; Wang, Paul J; Narayan, Sanjiv M

    2017-05-01

    Focal Impulse and Rotor Modulation (FIRM) uses 64-electrode basket catheters to identify atrial fibrillation (AF)-sustaining sites for ablation, with promising results in many studies. Accordingly, new basket designs are being tested by several groups. We set out to determine the procedural safety of adding basket mapping and map-guided ablation to conventional pulmonary vein isolation (PVI). We collected 30 day procedural safety data in five US centres for consecutive patients undergoing FIRM plus PVI (FIRM-PVI) compared with contemporaneous controls undergoing PVI without FIRM. A total of 625 cases were included in this analysis: 325 FIRM-PVI and 300 PVI-controls. FIRM-PVI patients were more likely than PVI-controls to be male (83% vs. 66%, P PVI (62 ± 22 min) vs. PVI-controls (52 ± 18 min, P = 0.03). The complication rate for FIRM-PVI procedures (4.3%) was similar to controls (4.0%, P = 1) for both major and minor complications; no deaths were reported. The rate of complications potentially attributable to the basket catheter was small and did not differ between basket types (Constellation 2.8% vs. FIRMap 1.8%, P = 0.7) or between cases in which basket catheters were and were not used (P = 0.5). Complication rates did not differ between centres (P = 0.6). Procedural complications from the use of the basket catheters for AF mapping are low, and thus procedural safety appears similar between FIRM-PVI and PVI-controls in a large multicentre cohort. Future studies are required to determine the optimal approach to maximize the efficacy of FIRM-guided ablation.

  1. The role of the Nuclear Safety Council in relation to the Fukushima accident; El papel del Consejo de Seguridad Nuclear en relacion con el accidente de Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    Garcia Casado, B.

    2011-07-01

    On March 11th last, in the wake of the earthquake and subsequent tsunami that devastated the East coast of Japan, damage was sustained by the reactors of the Fukushima nuclear power plant. During this process, the CSN, as the organisation solely responsible for nuclear safety and radiological protection in Spain, has played a key role in managing communications, with a view to providing society with reliable and accurate information on the accident. (Author)

  2. 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.

  3. 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

  4. 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...

  5. 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.

  6. 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

  7. Physical aspects of quality assurance in nuclear medicine and radiotherapy, regulatory approach of the National Nuclear Safety Center; Aspectos fisicos de garantia de calidad en medicina nuclear y radioterapia. Enfoque regulatorio del centro Nacional de Seguridad Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez C, D.; Fuente P, A. de la; Quevedo G, J.R.; Lopez F, Y. [CNSN, Calle 28 No. 504 e/5 y 7, Ave. Miramar, La Habana (Cuba); Varela C, C. [CCEEM, Calle 4 No. 455 e/19 y 21, Ave. Vedado, La Habana (Cuba)]. e-mail: cruz@orasen.co.cu

    2006-07-01

    The physical aspects of the quality guarantee in Nuclear Medicine and Radiotherapy its are of cardinal importance to guarantee the quality of the diagnoses and treatments that are carried out to the patients in this type of services. The OIEA, the OMS and other scientific and professional organizations have contributed significantly to the elaboration of recommendations, Protocols, etc. applicable in the quality control programs and safety of the Nuclear Medicine and Radi