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Sample records for nuclear standards development

  1. Nuclear standardization development study

    International Nuclear Information System (INIS)

    Pan Jianjun

    2010-01-01

    Nuclear industry is the important part of national security and national economic development is key area of national new energy supported by government. nuclear standardization is the important force for nuclear industry development, is the fundamental guarantee of nuclear safe production, is the valuable means of China's nuclear industry technology to the world market. Now nuclear standardization faces to the new development opportunity, nuclear standardization should implement strategy in standard system building, foreign standard research, company standard building, and talented people building to meet the requirement of nuclear industry development. (author)

  2. Standards development for the nuclear industry

    International Nuclear Information System (INIS)

    Domondon, D.B.

    The ushering of nuclear era in the Philippines with the construction of the PNPP-I (Philippine Nuclear Power Plant) necessitates the evolvement and use of nuclear standards as a tool for safety evaluation in the licensing process. The Department of Nuclear Regulation and Safeguards under the Philippine Atomic Energy Commission has as one of its responsibilities the establishment of regulatory standards to ensure safe operation of nuclear facilities. This article points out the needs for nuclear standards and the steps in standard development which involve an enormous amount of resources in terms of manpower, expertise and money. The staff of the Department of Nuclear Regulations and Safeguards (DNRS) does not intend to engage in the original development of standards; rather, it reviews standards in use elsewhere, specifically in the U.S. and adopts to local conditions. (author)

  3. ISO: international standards development for nuclear technology

    International Nuclear Information System (INIS)

    Becker, K.

    1981-01-01

    The importance of internationally recognized standards for nuclear technology and safety is rapidly increasing for technical as well as economical and political reasons such as public acceptance and nuclear technology transfer to developing countries. The need for such standards is also evident because of the large number of nuclear installations sited close to international borders, and the export of nuclear installations from relatively few supplier countries to a large number of user countries. It is the purpose of this report to describe briefly the history, organizational structures and procedures, goals, accomplishments, problems, and future needs of the relevant activities of the International Organization for Standardization (ISO). ISO is composed of the partly governmental, partly non-governmental national standards bodies of 86 countries including China. The work of its Technical Committee (TC) 85 'Nuclear Energy' is mostly concerned with industrial applications, contractual aspects and international communication, for the benefit of both developed and developing countries. It works in close liaison with IAEA, which develops Codes and Guides addressed mainly to the regulatory aspects of nuclear power plants in developing countries. ISO/TC 85 has four sub-committees dealing with: (a) Terminology, Definitions, Units and Symbols (Secretariat USA, four working groups (WGs)); (b) Radiation Protection (Secretariat France, ten WGs); (c) Power Reactor Technology (Secretariat Sweden, nine WGs); (d) Nuclear Fuel Technology (Secretariat F.R. Germany, seven WGs). (author)

  4. Accelerating nuclear power standards development and promoting sound nuclear power development in China

    International Nuclear Information System (INIS)

    Yang Changli

    2008-01-01

    The paper expounds the importance of quickening establishment and perfection of nuclear power standard system in China, analyzes achievements made and problems existed during the development of nuclear power standards, put forward proposals to actively promote the work in this regard, and indicates that CNNC will further strengthen the standardization work, enhance coordination with those trades related to nuclear power standards, and jointly promote the development of nuclear power standards. (authors)

  5. Development of nuclear power standards and relevant system in China

    International Nuclear Information System (INIS)

    Cao Shudong

    2008-01-01

    By analyzing the history of nuclear power development and the status of nuclear power codes and standards in China, the significance and necessity to quicken the development of nuclear power standards system in China are pointed out, and the guiding ideology, development thoughts, working doctrine and development objectives are put forward in this paper. (authors)

  6. Development of standard testing methods for nuclear-waste forms

    International Nuclear Information System (INIS)

    Mendel, J.E.; Nelson, R.D.

    1981-11-01

    Standard test methods for waste package component development and design, safety analyses, and licensing are being developed for the Nuclear Waste Materials Handbook. This paper describes mainly the testing methods for obtaining waste form materials data

  7. Personnel involved in nuclear standards development: 1980 directory

    International Nuclear Information System (INIS)

    Carr, S.J.

    1980-03-01

    The development of nuclear standards is an active and necessary endeavor that is concerned with the safe, orderly, and economic development of nuclear potential. There are almost 4100 people from the teachnical community who are presently involved either in writing nuclear standards, including codes, or in the management and processing roles necessary for their approval and promulgation. This document identifies the current participation of each individual as member, chairman, cochairman (vice-chairman), or secretary of about 700 standards development committees and groups. The standards committees and groups are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. This directory includes four major sections: personnel, employers, committees, and a Key-Word-in-Context (KWIC) Index of committee titles. It can also be used to identify the participation of employers as well as to recognize the contributions of individuals to the often interdisciplinary activity of standards development

  8. Personnel involved in nuclear standards development: 1980 directory

    Energy Technology Data Exchange (ETDEWEB)

    Carr, S.J. (ed.)

    1980-03-01

    The development of nuclear standards is an active and necessary endeavor that is concerned with the safe, orderly, and economic development of nuclear potential. There are almost 4100 people from the teachnical community who are presently involved either in writing nuclear standards, including codes, or in the management and processing roles necessary for their approval and promulgation. This document identifies the current participation of each individual as member, chairman, cochairman (vice-chairman), or secretary of about 700 standards development committees and groups. The standards committees and groups are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. This directory includes four major sections: personnel, employers, committees, and a Key-Word-in-Context (KWIC) Index of committee titles. It can also be used to identify the participation of employers as well as to recognize the contributions of individuals to the often interdisciplinary activity of standards development.

  9. Development of radiation shielding standards in the American Nuclear Society

    International Nuclear Information System (INIS)

    Trubey, D.K.

    1975-11-01

    The American Nuclear Society (ANS) is a standards-writing organization-member of the American National Standards Institute (ANSI). The ANS Standards Committee has a subcommittee denoted ANS-6, Shielding, whose charge is to establish standards in connection with radiation protection and shielding, to provide shielding information to other standards writing groups, and to prepare recommended sets of shielding data and test problems. This paper is a progress report of this subcommittee

  10. Trends in U.S. nuclear standards development

    International Nuclear Information System (INIS)

    Crowley, J.H.; Kaminski, R.S.

    1987-01-01

    Regulation of the U.S Nuclear Power industry has been extensive during the 1970's. Key to this situation has been the evolution in the 'interpretation' of the rules, regulations and consensus standards which have been incorporated into NRC guidance documents by reference or endorsement. The resulting increase in the number and complexity of LWR construction requirements has significantly increased the labor content of an LWR construction project. The authors believe that existing nuclear related consensus standards should be reviewed with the objective of modifying the standards to improve the efficiency and productivity of engineering, craft, and non-manual personnel. (author)

  11. Nuclear standards

    International Nuclear Information System (INIS)

    Fichtner, N.; Becker, K.; Bashir, M.

    1981-01-01

    This compilation of all nuclear standards available to the authors by mid 1980 represents the third, carefully revised edition of a catalogue which was first published in 1975 as EUR 5362. In this third edition several changes have been made. The title has been condensed. The information has again been carefully up-dated, covering all changes regarding status, withdrawal of old standards, new projects, amendments, revisions, splitting of standards into several parts, combination of several standards into one, etc., as available to the authors by mid 1980. The speed with which information travels varies and requires in many cases rather tedious and cumbersome inquiries. Also, the classification scheme has been revised with the goal of better adjustment to changing situations and priorities. Whenever it turned out to be difficult to attribute a standard to a single subject category, multiple listings in all relevant categories have been made. As in previous editions, within the subcategories the standards are arranged by organization (in Categorie 2.1 by country) alphabetically and in ascending numerical order. It covers all relevant areas of power reactors, the fuel cycle, radiation protection, etc., from the basic laws and governmental regulations, regulatory guides, etc., all the way to voluntary industrial standards and codes of pratice. (orig./HP)

  12. ASME Section XI trends in developing nuclear codes and standards

    International Nuclear Information System (INIS)

    Hedden, O.F.

    1995-01-01

    When the author began working on nuclear power many years ago, he knew that perfection was the only acceptable technical standard. Unfortunately, this became an obsession with perfection that has had unfavorable consequences in some of the non-technical areas of work in ASME nuclear power Codes and Standards. However, the economic problems of the nuclear power industry now demand a more pragmatic approach if the industry is to continue. Not only does each item considered for action need to be evaluated to criteria that may in some cases be less than perfection, but one needs to consider whether it contributes tangibly to either safety or to reduction in technical or administrative burden. These should be the governing, criteria. The introduction of risk-based inspection methodologies will certainly be an important element in doing this successfully. One needs to consider these criteria collectively, as one discusses each item at the committee level, and individually, as one votes on each item. In the past, the author has been concerned that the industry was not acting quickly enough in taking advantage of opportunities offered by the Code to increase safety or to reduce cost. While he still has some concern, he thinks communication channels have been greatly improved. Now he is becoming more concerned with both the collective and individual actions that delay beneficial changes. The second part of the author's talk has to do with the relevance of the code committees in the nuclear power industry regulatory process

  13. Development of nuclear standard filter elements for PWR plant

    International Nuclear Information System (INIS)

    Weng Minghui; Wu Jidong; Gu Xiuzhang; Zhang Jinghua

    1988-11-01

    Model FRX-5 and FRX-10 nuclear standard filter elements are used for the fluid clarification of the chemical and volume control system (CVCS), boron recycle system (BRS), spent fuel pit cooling system (SFPCS) and steam generator blowdown system (SGBS) in Qinshan Nuclear Power Plant. The radioactive contaminant, fragment of resin and impurity are collected by these filter elements, The core of filter elements consists of polypropylene frames and paper filter medium bonded by resin. A variety of filter papers are tested for optimization. The flow rate and comprehensive performance have been measured in the simulation condition. The results showed that the performance and lifetime have met the designing requirements. The advantages of the filter elements are simple in manufacturing, less expense and facilities for waste-disposal. At present, some of filter elements have been produced and put in operation

  14. Personnel involved in the development of nuclear standards in the United States, 1975

    International Nuclear Information System (INIS)

    Johnson, E.B.

    1976-05-01

    The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The Directory has four major sections: personnel, employers, committees, and a KWIC Index of committee titles. The Directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities

  15. Personnel involved in the development of nuclear standards in the United States, 1976

    International Nuclear Information System (INIS)

    Johnson, E.B.

    1977-03-01

    The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The directory has four major sections: personnel, employers, committees, and a KWIC index of committee titles. The directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities

  16. Personnel involved in the development of nuclear standards in the United States, 1976

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, E.B. (ed.)

    1977-03-01

    The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The directory has four major sections: personnel, employers, committees, and a KWIC index of committee titles. The directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities.

  17. Personnel involved in the development of nuclear standards in the United States, 1975

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, E.B. (ed.)

    1976-05-01

    The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The Directory has four major sections: personnel, employers, committees, and a KWIC Index of committee titles. The Directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities.

  18. Standard Reference Development of nuclear material for Tensile and Hardness Test Properties

    International Nuclear Information System (INIS)

    Choo, Y. S.; Kim, D. S.; Yoo, B. O.; Ahn, S. B.; Baik, S. J.; Chun, Y. B.; Kim, K. H.; Hong, K. P.; Ryu, W. S.

    2007-12-01

    Standard reference is a official approved data such a coefficient of physics, approved material properties, and etc., which should be analyzed and evaluated by scientific method to acquire official approval for accuracy and credibility of measured data and information. So it could be used broadly and continuously by various fields of nation and society. It is classified to effective standard reference, verified standard reference, and certified standard reference. There are sixteen fields in designated standard references such a physical chemistry field, material field, metal field, and the others. The standard reference of neutron irradiated nuclear structural material is classified to metal field. This report summarized the whole processes about data collection, data production, data evaluation and the suggestion of details evaluation technical standard for tensile and hardness properties, which were achieved by carry out the project 'nuclear material standard reference development' as a result

  19. Standard Reference Development of nuclear material for Tensile and Hardness Test Properties

    Energy Technology Data Exchange (ETDEWEB)

    Choo, Y. S.; Kim, D. S.; Yoo, B. O.; Ahn, S. B.; Baik, S. J.; Chun, Y. B.; Kim, K. H.; Hong, K. P.; Ryu, W. S

    2007-12-15

    Standard reference is a official approved data such a coefficient of physics, approved material properties, and etc., which should be analyzed and evaluated by scientific method to acquire official approval for accuracy and credibility of measured data and information. So it could be used broadly and continuously by various fields of nation and society. It is classified to effective standard reference, verified standard reference, and certified standard reference. There are sixteen fields in designated standard references such a physical chemistry field, material field, metal field, and the others. The standard reference of neutron irradiated nuclear structural material is classified to metal field. This report summarized the whole processes about data collection, data production, data evaluation and the suggestion of details evaluation technical standard for tensile and hardness properties, which were achieved by carry out the project 'nuclear material standard reference development' as a result.

  20. Development of a standard equipment management model for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Hee Seung; Ju, Tae Young; Kim, Jung Wun [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2012-10-15

    Most utilities that have achieved high performance have introduced a management model to improve performance and operate plants safely. The Nuclear Energy Institute has developed and updated its Standard Nuclear Performance Model (SNPM) in order to provide a summary of nuclear processes, cost definitions, and key business performance measures for business performance comparison and benchmarking. Over the past decade, Korea Hydro and Nuclear Power Co. (KHNP) has introduced and implemented many engineering processes such as Equipment Reliability (ER), Maintenance Rule (MR), Single Point Vulnerability (SPV), Corrective Action Program (CAP), and Self Assessment (SA) to improve plant performance and to sustain high performance. Some processes, however, are not well interfaced with other processes, because they were developed separately and were focused on the process itself. KHNP is developing a Standard Equipment Management Model (SEMM) to integrate these engineering processes and to improve the interrelation among the processes. In this paper, a draft model and attributes of the SEMM are discussed.

  1. Development of a standard equipment management model for nuclear power plants

    International Nuclear Information System (INIS)

    Chang, Hee Seung; Ju, Tae Young; Kim, Jung Wun

    2012-01-01

    Most utilities that have achieved high performance have introduced a management model to improve performance and operate plants safely. The Nuclear Energy Institute has developed and updated its Standard Nuclear Performance Model (SNPM) in order to provide a summary of nuclear processes, cost definitions, and key business performance measures for business performance comparison and benchmarking. Over the past decade, Korea Hydro and Nuclear Power Co. (KHNP) has introduced and implemented many engineering processes such as Equipment Reliability (ER), Maintenance Rule (MR), Single Point Vulnerability (SPV), Corrective Action Program (CAP), and Self Assessment (SA) to improve plant performance and to sustain high performance. Some processes, however, are not well interfaced with other processes, because they were developed separately and were focused on the process itself. KHNP is developing a Standard Equipment Management Model (SEMM) to integrate these engineering processes and to improve the interrelation among the processes. In this paper, a draft model and attributes of the SEMM are discussed

  2. Experience with nuclear safety standards development in non-governmental international organizations

    International Nuclear Information System (INIS)

    Becker, K.

    1985-01-01

    Besides the IAEA as a 'governmental' organization dealing with basic safety recommendations addressed primarily to the national regulatory bodies in developing countries, two closely related non-governmental international standards organizations have gained extensive experience in the field of nuclear standardization. Over more than 25 years since their formation, both (a) the International Organization for Standardization's (ISO) Technical Committee 85 'Nuclear Energy', in particular in its Sub-Committee 3 'Reactor Technology and Safety' and (b) the International Electrotechnical Commission's (IEC) Technical Committee 45 'Nuclear Instrumentation' have published numerous standards. A brief review is given of these, draft standards, and other documents planned to become international standards. Many of them deal with rather specialized topics typical for 'industrial' standards such as standardized procedures, instruments, methods, materials, test methods, terminology, and signs and symbols, but others are directly related to more basic safety issues. In some areas such as quality assurance, seismic aspects of siting and terminology, there has been in the past occasional overlap in the activities of the NUSS programme, IEC and ISO. Letters of Understanding have since 1981 contributed to clarifying the borderlines and to avoiding redundant efforts. Also, some experiences and problems are described arising, for example, from the harmonization of different national safety philosophies and traditions into universally accepted international standards, and the transfer of international standards into national standards systems. Finally, based on a recent comprehensive compilation of some 3300 nuclear standards and standards projects, an attempt is made to present a cost/benefit analysis and an outlook on future developments. (author)

  3. Co-operative development of nuclear safety regulations, guides and standards based on NUSS

    International Nuclear Information System (INIS)

    Pachner, J.; Boyd, F.C.; Yaremy, E.M.

    1985-01-01

    A major need of developing Member States building nuclear power plants (NPPs) of foreign origin is to acquire a capability to regulate such nuclear plants independently. Among other things, this requires the development of national nuclear safety regulations, guides and standards to govern the development and use of nuclear technology. Recognizing the importance and complexity of this task, it seems appropriate that the NPP-exporting Member States share their experience and assist the NPP-importing Member States in the development of their national regulations and guides. In 1983, the Atomic Energy Control Board and Atomic Energy of Canada Ltd. conducted a study of a possible joint programme involving Canada, an NPP-importing Member State and the IAEA for the development of the national nuclear safety regulations and guides based on NUSS documents. During the study, a work plan with manpower estimates for the development of design regulations, safety guides and a guide for regulatory evaluation of design was prepared as an investigatory exercise. The work plan suggests that a successful NUSS implementation in developing Member States will require availability of significant resources at the start of the programme. The study showed that such a joint programme could provide an effective mechanism for transfer of nuclear safety know-how to the developing Member States through NUSS implementation. (author)

  4. A basic study for development of environmental standard review plan of Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Chang Hyun; Cho, Jae Seon; You, Young Woo [Seoul Nationl Univ., Seoul (Korea, Republic of)] (and others)

    1999-12-15

    In this study is performed a basic study to be ready for the development and detail analysis of NUREG-1555 ESRP. As a fundamental research for literature survey and development of draft review plan, review and translation of NUREG-1555 published by NRC, and which is applied to licensing procedure of Nuclear Power Plants are included. These provided the basic information for the developments of the environmental standard review plan.

  5. Development of standard technical report on using and selecting wireless device in nuclear power plants

    International Nuclear Information System (INIS)

    Koo, I. S.; Hong, S. B.; Cho, J. W.

    2011-11-01

    1. Purpose · Development of IEC technical report on wireless device using in nuclear power plants 2. Contents · IEC technical reports of draft for circulation and final draft for next planary meeting · Case study on experiment of wireless devices 3. Implementation methods · Preparation of first draft with experts group, its circulation, discussions on the results of the circulation · Organizing three teams such as preparation, reviews and experiment 4. Results · Maintenance cost will be reduced with application of the wireless technologies in nuclear power plants · Commercial wireless devices will be developed before standard is issued

  6. Development of a standard communication protocol for an emergency situation management in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Man Cheol, E-mail: charleskim@kaeri.re.k [Integrated Risk Assessment Center, Korea Atomic Energy Research Institute, 150, Deokjin-dong, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Park, Jinkyun; Jung, Wondea [Integrated Risk Assessment Center, Korea Atomic Energy Research Institute, 150, Deokjin-dong, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Kim, Hanjeom; Kim, Yoon Joong [YGN Nuclear Power Division Training Center, Korea Hydro and Nuclear Power Company, 517 Kyemari, Hongnong-eup, Yeongkwang-gun, Chonnam 513-880 (Korea, Republic of)

    2010-06-15

    Correct communication between main control room (MCR) operators is an important factor in the management of emergency situations in nuclear power plants (NPPs). For this reason, a standard communication protocol for the management of emergency situations in NPPs has been developed, with the basic direction of enhancing the safety of NPPs and the standardization of communication protocols. To validate the newly developed standard communication protocol, validation experiments with 10 licensed NPP MCR operator teams was performed. From the validation experiments, it was found that the use of the standard communication protocol required more time, but it can contribute to the enhancement of the safety of NPPs by an operators' better grasp of the safety-related parameters and a more efficient and clearer communication between NPP operators, while imposing little additional workloads on the NPP MCR operators. The standard communication protocol is expected to be used to train existing NPP MCR operators without much aversion, as well as new operators.

  7. Development of a consensus standard for verification and validation of nuclear system thermal-fluids software

    International Nuclear Information System (INIS)

    Harvego, Edwin A.; Schultz, Richard R.; Crane, Ryan L.

    2011-01-01

    With the resurgence of nuclear power and increased interest in advanced nuclear reactors as an option to supply abundant energy without the associated greenhouse gas emissions of the more conventional fossil fuel energy sources, there is a need to establish internationally recognized standards for the verification and validation (V and V) of software used to calculate the thermal–hydraulic behavior of advanced reactor designs for both normal operation and hypothetical accident conditions. To address this need, ASME (American Society of Mechanical Engineers) Standards and Certification has established the V and V 30 Committee, under the jurisdiction of the V and V Standards Committee, to develop a consensus standard for verification and validation of software used for design and analysis of advanced reactor systems. The initial focus of this committee will be on the V and V of system analysis and computational fluid dynamics (CFD) software for nuclear applications. To limit the scope of the effort, the committee will further limit its focus to software to be used in the licensing of High-Temperature Gas-Cooled Reactors. Although software verification will be an important and necessary part of the standard, much of the initial effort of the committee will be focused on the validation of existing software and new models that could be used in the licensing process. In this framework, the Standard should conform to Nuclear Regulatory Commission (NRC) and other regulatory practices, procedures and methods for licensing of nuclear power plants as embodied in the United States (U.S.) Code of Federal Regulations and other pertinent documents such as Regulatory Guide 1.203, “Transient and Accident Analysis Methods” and NUREG-0800, “NRC Standard Review Plan”. In addition, the Standard should be consistent with applicable sections of ASME NQA-1-2008 “Quality Assurance Requirements for Nuclear Facility Applications (QA)”. This paper describes the general

  8. Development of the nuclear plant analyzer for Korean standard Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Shin Hwan; Kim, Hyeong Heon; Song, In Ho; Hong, Eon Yeong; Oh, Yeong Taek [Korea Power Engineering Company Inc., Yongin (Korea, Republic of)

    2000-12-15

    The purpose of this study is to develop an NPA for the Ulchin Nuclear Power Plant Unit 3 and 4, the first KSNP type plant. In this study, the process model simulating the overall plant systems, GUI and simulation executive which provide the functions of an engineering simulator were developed, and the NPA was completed by integrating them. The contents and the scope of this study are as follows : main feedwater system, auxiliary feedwater system, Chemical and Volume Control System(CVCS), Safety Injection System(SIS), Shutdown Cooling System(SCS), electric power supply system, Core Protection Calculator(CPC), various plant control system, development of the graphics screens for each system, real-time simulation, simulation control for the enhancement of functional capabilities, user friendly GUI, collection of the design and operating data, establishment of the NPA database, integration of the GUI and simulation control program with process model, collection of the data for the verification and validation of the developed NPA, collection of the plant test data, collection and review of the results of other computer codes, verification of the simulation accuracy by comparing the NPA results with the actual plant data, validation of the simulation capability of the NPA, comparison against available data from other analysis suing different computer codes.

  9. Argentine nuclear energy standardization activities

    International Nuclear Information System (INIS)

    Boero, Norma; Corcuera, Roberto; Palacios, Tulio A.; Hey, Alfredo M.; Berte, G.; Trama, L.

    2004-01-01

    The International Organization for Standardization (ISO) has more than 200 Technical Committees that develop technical standards. During April 2004 took place in Buenos Aires the 14th Plenary of the ISO/TC 85 Nuclear Energy Committee. During this Plenary issues as Nuclear Terminology, Radiation Protection, Nuclear Fuels, Nuclear Reactors and Irradiation Dosimetry was dealt with. 105 International delegates and 45 National delegates (belonging to CNEA, ARN, NASA, INVAP, CONUAR, IONICS and other organizations) attended the meetings. During this meeting ISO/TC 85 changed its scope; the new scope of the Committee is 'Standardization in the fields of peaceful applications of nuclear energy and of the protection of individuals against all sources of ionizing radiations'. This work summarizes the most important advances and resolutions about the development of standards taken during this meeting as well as the main conclusions. (author) [es

  10. Fundamental challenging problems for developing new nuclear safety standard computer codes

    International Nuclear Information System (INIS)

    Wong, P.K.; Wong, A.E.; Wong, A.

    2005-01-01

    Based on the claims of the US Basic patents number 5,084,232; 5,848,377 and 6,430,516 that can be obtained from typing the Patent Numbers into the Box of the Web site http://164.195.100.11/netahtml/srchnum.htm and their associated published technical papers having been presented and published at International Conferences in the last three years and that all these had been sent into US-NRC by E-mail on March 26, 2003 at 2:46 PM., three fundamental challenging problems for developing new nuclear safety standard computer codes had been presented at the US-NRC RIC2003 Session W4. 2:15-3:15 PM. at the Washington D.C. Capital Hilton Hotel, Presidential Ballroom on April 16, 2003 in front of more than 800 nuclear professionals from many countries worldwide. The objective and scope of this paper is to invite all nuclear professionals to examine and evaluate all the current computer codes being used in their own countries by means of comparison of numerical data from these three specific openly challenging fundamental problems in order to set up a global safety standard for all nuclear power plants in the world. (authors)

  11. Nuclear radiation gauge standard

    International Nuclear Information System (INIS)

    Berry, R.L.

    1977-01-01

    A hydrophobic standard for calibrating nuclear radiation moisture gauges is described, comprising a body of superposed interleaved thin layers of a moderating material containing hydrogen in the molecular structure thereof and of a substantially non-moderating material

  12. Developing glovebox robotics to meet the national robot safety standard and nuclear safety criteria

    International Nuclear Information System (INIS)

    McMahon, T.T.; Sievers, R.H.

    1991-09-01

    Development of a glove box based robotic system by the Lawrence Livermore National Laboratory (LLNL) is reported. Safety issues addressed include planning to meet the special constraints of operations within a hazardous material glove box and with hostile environments, compliance with the current and draft national robotic system safety standards, and eventual satisfaction of nuclear material handling requirements. Special attention has been required for the revision to the robot and control system models which antedate adoption of the present national safety standard. A robotic test bed, using non-radioactive surrogates is being activated at the Lawrence Livermore National Laboratory to develop the material handling system and the process interfaces for future special nuclear material processing applications. Part of this effort is to define, test, and revise adequate safety controls to ensure success when the system is eventually deployed at a DOE site. The current system is primarily for demonstration and testing, but will evolve into the baseline configuration from which the production system is to be derived. This results in special hazards associated with research activities which may not be present on a production line. Nuclear safety is of paramount importance and has been successfully addressed for 50 years in the DOE weapons production complex. It carries its particular requirements for robot systems and manual operations, as summarized below: Criticality must be avoided (materials cannot consolidate or accumulate to approach a critical mass). Radioactive materials must be confined. The public and workers must be protected from accountable radiation exposure. Nuclear material must be readily retrievable. Nuclear safety must be conclusively demonstrated through hazards analysis. 7 refs

  13. The Canadian approach to nuclear codes and standards. A CSA forum for development of standards for CANDU: radioactive waste management and decommissioning

    International Nuclear Information System (INIS)

    Shin, T.; Azeez, S.; Dua, S.

    2006-01-01

    Together with the Canadian Standards Association (CSA), industry stakeholders, governments, and the public have developed a suite of standards for CANDU nuclear power plants that generate electricity in Canada and abroad. In this paper, we will describe: CSA's role in national and international nuclear standards development; the key issues and priority projects that the nuclear standards program has addressed; the new CSA nuclear committees and projects being established, particularly those related to waste management and decommissioning; the hierarchy of nuclear regulations, nuclear, and other standards in Canada, and how they are applied by AECL; the standards management activities; and the future trends and challenges for CSA and the nuclear community. CSA is an accredited Standards Development Organization (SDO) and part of the international standards system. CSA's Nuclear Strategic Steering Committee (NSSC) provides leadership, direction, and support for a standards committee hierarchy comprised of members from a balanced matrix of interests. The NSSC strategically focuses on industry challenges; a new nuclear regulatory system, deregulated energy markets, and industry restructuring. As the first phase of priority projects is nearing completion, the next phase of priorities is being identified. These priorities address radioactive waste management, environmental radiation management, decommissioning, structural, and seismic issues. As the CSA committees get established in the coming year, members and input will be solicited for the technical committees, subcommittees, and task forces for the following related subjects: Radioactive Waste Management; a) Dry Storage of Irradiated Fuel; b) Short-Term Radioactive Waste Management; c) Long-Term Storage and Disposal of Radioactive Waste. 2. Decommissioning Nuclear Power is highly regulated, and public scrutiny has focused Codes and Standards on public and worker safety. Licensing and regulation serves to control

  14. Standardization of nuclear power plants in the United States: recent regulatory developments

    International Nuclear Information System (INIS)

    Cowan, B.Z.; Tourtellotte, J.R.

    1992-01-01

    On April 18, 1989, the United States (U.S.) Nuclear Regulatory Commission (NRC) amended the regulations governing the process for licensing nuclear power plants in the United States to provide for issuance of early site permits, standard design certifications and combined construction permits and operating licenses for nuclear power reactors. The new regulations are designed to achieve early resolution of licensing issues and facilitate standardization of nuclear power plants in the United States. The program for design standardization is central to efforts mounted by the U.S. government and industry to ensure that there will be a next generation of nuclear power facilities in the U.S. The most significant changes are provisions for certification of standard designs and for issuance prior to start of construction of combined licenses which incorporate a construction permit and an operating license with conditions. Such certifications and combined licenses must contain tests, inspections and analyses, and acceptance criteria, which are necessary and sufficient to provide reasonable assurance that the facility has been constructed and will operate in accordance with the combined license. A number of significant implementation issues have arisen. In addition a major court case brought by several anti-nuclear groups is pending, challenging NRC authority to issue combined licenses. It is the goal of the U.S. nuclear industry to have the first of the next generation of standardized nuclear power plants ordered, licensed, constructed and on-line by the year 2000. (author)

  15. Development of alarm cause tracking system for Korea standard nuclear power plant

    International Nuclear Information System (INIS)

    Lee, Jung Woon; Kim, Jung Taek; Park, Jae Chang; Lee, Hyun Chul; Park, Joong Pal

    2004-05-01

    The proposed system, the ACTS(Alarm Cause Tracking System), in the 1st and 2nd development period(2001. 7 ∼ 2003. 6), tracks and displays the causes of alarms on-line from computerized logic diagrams. And the system highlights the specific procedures related the causes in the procedure of the alarm. In this period(2003. 7 ∼ 2004. 4), we developed the ACTS for Korea standard nuclear power plant. Also, we computerized control logic diagrams and alarm procedures for the ACTS. A long-term target is to apply the ACTS at the real power plant, and a short-term target is to connect the ACTS with the ITF(Intergrated Test Facility) in KAERI site to develop other applications

  16. Recent developments in the IAEA safety standards: design and operation of nuclear power plants

    International Nuclear Information System (INIS)

    Saito, Takehiko

    2004-01-01

    The IAEA has been publishing a wide variety of safety standards for nuclear and radiation related facilities and activities since 1978. In 1996, a more rigorously structured approach for the preparation and review of its safety standards was introduced. Currently, based on the approach, revision of most of the standards is in completion or near completion. The latest versions of the Safety Requirements for ''Design'' and ''Operation'' of nuclear power plants were respectively published in 2000. Currently, along with this revision of the Safety Requirements, many Safety Guides have been revised. In order to clarify the complicated revision procedure, an example of the entire revision process for a Safety Guide is provided. Through actual example of the revision process, enormous amount of work involved in the revision work is clearly indicated. The current status of all of the Safety Standards for Design and that for Operation of nuclear power plants are summarized. Summary of other IAEA safety standards currently revised and available related IAEA publications, together with information on the IAEA Web Site from where these documents can be downloaded, is also provided. The standards are reviewed to determine whether revision (or new issue) is necessary in five years following publication. The IAEA safety standards will continue to be updated through comprehensive and structured approach, collaboration of many experts of the world, and reflecting good practices of the world. The IAEA safety standards will serve to provide high level of safety assurance. (author)

  17. Application of objective provision tree to development of standard review plan for sodium-cooled fast reactor nuclear design

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Moo-Hoon; Suh, Namduk; Choi, Yongwon; Shin, Andong [Korea Institute of Nuclear Safety, Daejon (Korea, Republic of)

    2016-06-15

    A systematic methodology was developed for the standard review plan for sodium-cooled fast reactor nuclear design. The process is first to develop an objective provision tree of sodium-cooled fast reactor for the reactivity control safety function. The provision tree is generally developed by designer to confirm whether the design satisfies the defense-in-depth concept. Then applicability of the current standard review plan of nuclear design for light water reactor to sodium-cooled fast reactor was evaluated and complemented by the developed objective provision tree.

  18. Technical standards in nuclear area

    International Nuclear Information System (INIS)

    Grimberg, M.

    1978-01-01

    The technical standardization in nuclear area is discussed. Also, the competence of CNEN in standardization pursuit is analysed. Moreover, the process of working up of technical standards is explained; in addition, some kinds of technical standards are discussed. (author) [pt

  19. Management plan for the Nuclear Standards Program

    International Nuclear Information System (INIS)

    1979-11-01

    This Management Plan was prepared to describe the manner in which Oak Ridge National Laboratory will provide technical management of the Nuclear Standards Program. The organizational structure that has been established within ORNL for this function is the Nuclear Standards Management Center, which includes the Nuclear Standards Office (NSO) already in existence at ORNL. This plan is intended to support the policies and practices for the development and application of technical standards in ETN projects, programs, and technology developments as set forth in a standards policy memorandum from the DOE Program Director for Nuclear Energy

  20. Cooperative development of nuclear safety regulations, guides and standards based on NUSS

    International Nuclear Information System (INIS)

    Pachner, J.; Boyd, F.C.; Yaremy, E.M.

    1984-10-01

    In 1983, the Atomic Energy Control Board and Atomic Energy of Canada Limited conducted a study of a possible joint program involving Canada, a nuclear power plant importing Member State and the IAEA for the development of the national nuclear safety regulations and guides based on NUSS documents. During the study, a work plan with manpower estimates for the development of design was prepared as an investigatory exercise. The work plan suggests that a successful NUSS implementation in developing Member States will require availability of significant resources at the start of the program. The study showed that such a joint program could provide an effective mechanism for transfer of nuclear safety know-how to the developing Member States through NUSS implementation

  1. Nuclear standards: current issues and future trends

    International Nuclear Information System (INIS)

    Landis, J.W.

    1985-01-01

    A summary of the important issues that currently face the nuclear standards field is presented and a discussion of how each of these issues is being resolved is given. The economic benefits that properly developed standards produce are listed

  2. Development of A Standard Method for Human Reliability Analysis (HRA) of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kang, Dae Il; Jung, Won Dea; Kim, Jae Whan

    2005-12-01

    According as the demand of risk-informed regulation and applications increase, the quality and reliability of a probabilistic safety assessment (PSA) has been more important. KAERI started a study to standardize the process and the rules of HRA (Human Reliability Analysis) which was known as a major contributor to the uncertainty of PSA. The study made progress as follows; assessing the level of quality of the HRAs in Korea and identifying the weaknesses of the HRAs, determining the requirements for developing a standard HRA method, developing the process and rules for quantifying human error probability. Since the risk-informed applications use the ASME and ANS PSA standard to ensure PSA quality, the standard HRA method was developed to meet the ASME and ANS HRA requirements with level of category II. The standard method was based on THERP and ASEP HRA that are widely used for conventional HRA. However, the method focuses on standardizing and specifying the analysis process, quantification rules and criteria to minimize the deviation of the analysis results caused by different analysts. Several HRA experts from different organizations in Korea participated in developing the standard method. Several case studies were interactively undertaken to verify the usability and applicability of the standard method

  3. Development of A Standard Method for Human Reliability Analysis of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Jung, Won Dea; Kang, Dae Il; Kim, Jae Whan

    2005-12-01

    According as the demand of risk-informed regulation and applications increase, the quality and reliability of a probabilistic safety assessment (PSA) has been more important. KAERI started a study to standardize the process and the rules of HRA (Human Reliability Analysis) which was known as a major contributor to the uncertainty of PSA. The study made progress as follows; assessing the level of quality of the HRAs in Korea and identifying the weaknesses of the HRAs, determining the requirements for developing a standard HRA method, developing the process and rules for quantifying human error probability. Since the risk-informed applications use the ASME PSA standard to ensure PSA quality, the standard HRA method was developed to meet the ASME HRA requirements with level of category II. The standard method was based on THERP and ASEP HRA that are widely used for conventional HRA. However, the method focuses on standardizing and specifying the analysis process, quantification rules and criteria to minimize the deviation of the analysis results caused by different analysts. Several HRA experts from different organizations in Korea participated in developing the standard method. Several case studies were interactively undertaken to verify the usability and applicability of the standard method

  4. Development of A Standard Method for Human Reliability Analysis of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Won Dea; Kang, Dae Il; Kim, Jae Whan

    2005-12-15

    According as the demand of risk-informed regulation and applications increase, the quality and reliability of a probabilistic safety assessment (PSA) has been more important. KAERI started a study to standardize the process and the rules of HRA (Human Reliability Analysis) which was known as a major contributor to the uncertainty of PSA. The study made progress as follows; assessing the level of quality of the HRAs in Korea and identifying the weaknesses of the HRAs, determining the requirements for developing a standard HRA method, developing the process and rules for quantifying human error probability. Since the risk-informed applications use the ASME PSA standard to ensure PSA quality, the standard HRA method was developed to meet the ASME HRA requirements with level of category II. The standard method was based on THERP and ASEP HRA that are widely used for conventional HRA. However, the method focuses on standardizing and specifying the analysis process, quantification rules and criteria to minimize the deviation of the analysis results caused by different analysts. Several HRA experts from different organizations in Korea participated in developing the standard method. Several case studies were interactively undertaken to verify the usability and applicability of the standard method.

  5. Development of A Standard Method for Human Reliability Analysis (HRA) of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Dae Il; Jung, Won Dea; Kim, Jae Whan

    2005-12-15

    According as the demand of risk-informed regulation and applications increase, the quality and reliability of a probabilistic safety assessment (PSA) has been more important. KAERI started a study to standardize the process and the rules of HRA (Human Reliability Analysis) which was known as a major contributor to the uncertainty of PSA. The study made progress as follows; assessing the level of quality of the HRAs in Korea and identifying the weaknesses of the HRAs, determining the requirements for developing a standard HRA method, developing the process and rules for quantifying human error probability. Since the risk-informed applications use the ASME and ANS PSA standard to ensure PSA quality, the standard HRA method was developed to meet the ASME and ANS HRA requirements with level of category II. The standard method was based on THERP and ASEP HRA that are widely used for conventional HRA. However, the method focuses on standardizing and specifying the analysis process, quantification rules and criteria to minimize the deviation of the analysis results caused by different analysts. Several HRA experts from different organizations in Korea participated in developing the standard method. Several case studies were interactively undertaken to verify the usability and applicability of the standard method.

  6. Nuclear security standard: Argentina approach

    International Nuclear Information System (INIS)

    Bonet Duran, Stella M.; Rodriguez, Carlos E.; Menossi, Sergio A.; Serdeiro, Nelida H.

    2007-01-01

    Argentina has a comprehensive regulatory system designed to assure the security and safety of radioactive sources, which has been in place for more than fifty years. In 1989 the Radiation Protection and Nuclear Safety branch of the National Atomic Energy Commission created the 'Council of Physical Protection of Nuclear Materials and Installations' (CAPFMIN). This Council published in 1992 a Physical Protection Standard based on a deep and careful analysis of INFCIRC 225/Rev.2 including topics like 'sabotage scenario'. Since then, the world's scenario has changed, and some concepts like 'design basis threat', 'detection, delay and response', 'performance approach and prescriptive approach', have been applied to the design of physical protection systems in facilities other than nuclear installations. In Argentina, radioactive sources are widely used in medical and industrial applications with more than 1,600 facilities controlled by the Nuclear Regulatory Authority (in spanish ARN). During 2005, measures like 'access control', 'timely detection of intruder', 'background checks', and 'security plan', were required by ARN for implementation in facilities with radioactive sources. To 'close the cycle' the next step is to produce a regulatory standard based on the operational experience acquired during 2005. ARN has developed a set of criteria for including them in a new standard on security of radioactive materials. Besides, a specific Regulatory Guide is being prepared to help licensees of facilities in design a security system and to fulfill the 'Design of Security System Questionnaire'. The present paper describes the proposed Standard on Security of Radioactive Sources and the draft of the Nuclear Security Regulatory Guidance, based on our regulatory experience and the latest international recommendations. (author)

  7. World Nuclear Association (WNA) internationally standardized reporting (checklist) on the sustainable development performance of uranium mining and processing sites

    International Nuclear Information System (INIS)

    Harris, F.

    2014-01-01

    The World Nuclear Association (WNA) has developed internationally standardized reporting (‘Checklist’) for uranium mining and processing sites. This reporting is to achieve widespread utilities/miners agreement on a list of topics/indicators for common use in demonstrating miners’ adherence to strong sustainable development performance. Nuclear utilities are often required to evaluate the sustainable development performance of their suppliers as part of a utility operational management system. In the present case, nuclear utilities are buyers of uranium supplies from uranium miners and such purchases are often achieved through the utility uranium or fuel supply management function. This Checklist is an evaluation tool which has been created to collect information from uranium miners’ available annual reports, data series, and measurable indicators on a wide range of sustainable development topics to verify that best practices in this field are implemented throughout uranium mining and processing sites. The Checklist has been developed to align with the WNA’s policy document Sustaining Global Best Practices in Uranium Mining and Processing: Principles for Managing Radiation, Health and Safety, and Waste and the Environment which encompasses all applicable aspects of sustainable development to uranium mining and processing. The eleven sections of the Checklist are: 1. Adherence to Sustainable Development; 2. Health, Safety and Environmental Protection; 3. Compliance; 4. Social Responsibility and Stakeholder Engagement; 5. Management of Hazardous Materials; 6. Quality Management Systems; 7. Accidents and Emergencies; 8. Transport of Hazardous Materials; 9. Systematic Approach to Training; 10. Security of Sealed Radioactive Sources and Nuclear Substances; 11. Decommissioning and Site Closure. The Checklist benefits from many years of nuclear utility experience in verifying the sustainable development performance of uranium mining and processing sites. This

  8. Development of a standard methodology for optimizing remote visual display for nuclear maintenance tasks

    Science.gov (United States)

    Clarke, M. M.; Garin, J.; Prestonanderson, A.

    A fuel recycle facility being designed at Oak Ridge National Laboratory involves the Remotex concept: advanced servo-controlled master/slave manipulators, with remote television viewing, will totally replace direct human contact with the radioactive environment. The design of optimal viewing conditions is a critical component of the overall man/machine system. A methodology was developed for optimizing remote visual displays for nuclear maintenance tasks. The usefulness of this approach was demonstrated by preliminary specification of optimal closed circuit TV systems for such tasks.

  9. Development of a standard methodology for optimizing remote visual display for nuclear-maintenance tasks

    International Nuclear Information System (INIS)

    Clarke, M.M.; Garin, J.; Preston-Anderson, A.

    1981-01-01

    The aim of the present study is to develop a methodology for optimizing remote viewing systems for a fuel recycle facility (HEF) being designed at Oak Ridge National Laboratory (ORNL). An important feature of this design involves the Remotex concept: advanced servo-controlled master/slave manipulators, with remote television viewing, will totally replace direct human contact with the radioactive environment. Therefore, the design of optimal viewing conditions is a critical component of the overall man/machine system. A methodology has been developed for optimizing remote visual displays for nuclear maintenance tasks. The usefulness of this approach has been demonstrated by preliminary specification of optimal closed circuit TV systems for such tasks

  10. Development of departmental standard for traceability of measured activity for 131I therapy capsules used in nuclear medicine

    International Nuclear Information System (INIS)

    Ravichandran, Ramamoorthy; Binukumar, J.P.

    2011-01-01

    International Basic Safety Standards (International Atomic Energy Agency, IAEA) provide guidance levels for diagnostic procedures in nuclear medicine indicating the maximum usual activity for various diagnostic tests in terms of activities of injected radioactive formulations. An accuracy of ± 10% in the activities of administered radio-pharmaceuticals is being recommended, for expected outcome in diagnostic and therapeutic nuclear medicine procedures. It is recommended that the long-term stability of isotope calibrators used in nuclear medicine is to be checked periodically for their performance using a long-lived check source, such as 137 Cs, of suitable activity. In view of the un-availability of such a radioactive source, we tried to develop methods to maintain traceability of these instruments, for certifying measured activities for human use. Two re-entrant chambers ((HDR 1000 and Selectron Source Dosimetry System (SSDS)) with 125 I and 192 Ir calibration factors in the Department of Radiotherapy were used to measure Iodine-131 ( 131 I) therapy capsules to establish traceability to Mark V isotope calibrator of the Department of Nuclear Medicine. Special nylon jigs were fabricated to keep 131 I capsule holder in position. Measured activities in all the chambers showed good agreement. The accuracy of SSDS chamber in measuring 192 Ir activities in the last 5 years was within 0.5%, validating its role as departmental standard for measuring activity. The above method is adopted because mean energies of 131 I and 192 Ir are comparable. (author)

  11. Department of Energy Nuclear Energy Standards Program

    International Nuclear Information System (INIS)

    Silver, E.G.

    1980-01-01

    The policy with respect to the development and use of standards in the Department of Energy (DOE) programs concerned with maintaining and developing the nuclear option for the civilian sector (both in the form of the currently used light water reactors and for advanced concepts including the Liquid Metal Fast Breeder Reactor), is embodied in a Nuclear Standards Policy, issued in 1978, whose perspectives and philosophy are discussed

  12. Development in France of nuclear safety technical regulations and standards used in the licensing procedure

    International Nuclear Information System (INIS)

    Lebouleux, P.

    1983-04-01

    Initially, the Commissariat a l'Energie Atomique was the overall structure which encompassed all nuclear activities in France, including those connected with radiological protection and nuclear safety. As other partners appeared, the Authorities have laid down national regulations relative to nuclear installations since 1963. These regulations more particularly provide for the addition of prescriptions with which the applicant must comply to obtain the necessary licenses and the establishment of General Technical Regulations pertaining to nuclear safety. The technical regulation related to nuclear safety in France is made of a set of regulation texts, of a different nature, that define the requirements for the construction, commissioning and operation of nuclear facilities. Simultaneously, the safety authorities (Service Central de Surete des Installations Nucleaires: SCSIN) issue recommendations or guides which are not strictly speaking regulations in the juridical sense; they are called ''Regles Fondamentales de Surete'' (RFS). The RFS set up and detail the conditions, the respect of which is deemed to be complying with the French regulation practice, for the subject to which they relate. Their purpose is to make known rules judged acceptable by safety authorities, thus making the safety review easier. A RFS, or a letter, can also give the result of the examination of the constructor and operator codes (RCC) by safety authorities

  13. Standardization of the WPS and Development of the Welding Process Management System for Nuclear Power Plants

    International Nuclear Information System (INIS)

    Cho, Hong Seok; Lee, Jang Wook; Cho, Ki Hyun; Choi, Sang Hoon

    2010-01-01

    The purpose of this study is to integrate existing WPS(welding procedure specification) and PQR(procedure qualification records) which are kept by every branch office respectively and to develop a specialized program that will assist in the creation of WPS and PQR in accordance with the ASME Sec. IX, III, B31.1, etc. These research results make possible not only to ensure structural integrity by applying WPS and PQR correctly but also to cut down on expenses by managing the welding process efficiently. Moreover, as the specialized program will be linked with ERP system between KHNP and KPS, an administration action of welding process will be dealt with on-line. The backgrounds of this study are as follows; · Need to apply WPS correctly and promptly · Need to cut down on expenses due to overlapping development WPS · Need to manage welding resources efficiently · Need to standardize welding QA(quality assurance) documents · Need to improve efficiency of administrative welding process

  14. Development of adequate meteorological monitoring standards for safety analysis of nuclear facilities

    International Nuclear Information System (INIS)

    Alp, E.; Lewis, P.J.

    1985-09-01

    The aim of this report is to identify what constitutes adequate meteorological information for airborne dispersion calculations in case of releases from nuclear facilities during 'normal operation', 'design postulated accidents', and 'emergency situations'. The models used for estimating downwind dispersion are reviewed, including short-range simple terrain, short-range complex terrain and medium to long range models with emphasis on Lagrangian models. The meteorogolical input parameters required for running these models are identified. The methods by which these parameters may be obtained from raw meteorological data are then considered. Emphasis is placed on well-tried and recommended methods rather than those which are currently being developed and lack long-term field tests. The meteorological data required to calculate the parameters that are in turn input to dispersion calculation methods can be obtained mainly from tower measurements. Recommended tower height is 50 m, with two levels of instruments (10 and 50 m) for wind speed, wind direction and temperature. Data for precipitation and solar radiation, that may be required under certain conditions and for special calculations, may be estimated from nearby representative weather stations (if available). For simple terrain, a single tower is sufficient. For complex terrain, such as coastal regions, two towers are desirable for accurate characterization of the turbulence regime in the vicinity of a release site. The report provides the necessary accuracy specifications for instruments required for the meteorological measurements. Data monitoring and recording, maintenance, quality control and assurance are also discussed. Error propagation analyses are recommended to determine the full implications of instrument accuracies on the accuracy of dispersion model predictions. 82 refs

  15. ISO standardization in nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Brabec, D [Ustav pro Vyzkum, Vyrobu a Vyuziti Radioisotopu, Prague (Czechoslovakia); Cermak, O [Urad pro Normalizaci a Mereni, Prague (Czechoslovakia)

    1984-10-01

    The activity is described of the technical commission ISO/TC 85 which is currently divided into 4 subcommissions (SC) and 24 working groups. SC 1 ''Terminology, definitions, units, abbreviations'' has one working group. The most important document of this SC is ISO 921-1972 (Dictionary of nuclear technology). SC 2 ''Radiation protection'' has 9 working groups and has processed standards in dosimetry. SC 3 ''Technology of power reactors'' has 6 working groups and its work is related to IAEA activities within the NUSS program. SC 4 ''Technology of nuclear fuels'' has 8 working groups. SC 4 has compiled the basic standards for sealed sources and methods of testing their tightness. The results of the work of this group have been reflected into the standardization work of CMEA. A list is given of published international standards within TC 85.

  16. Development of nuclear energy

    Energy Technology Data Exchange (ETDEWEB)

    Wakeham, John [Secretary of State for Energy, London (UK)

    1991-06-01

    The Government's views on the development of nuclear energy are outlined. In this country, we continue to see some important advantages in maintaining nuclear power generation. It increases diversity, and so helps to maintain security of energy supply. It does not produce greenhouse gases or contribute to acid rain. But it is equally clear that nuclear costs must be brought under control whilst at the same time maintaining the high standards of safety and environmental protection which we have come to expect in the UK. The three main elements which the nuclear industry must address in the future are summarized. First the costs of nuclear generation must be reduced. Secondly, once the feasibility and costings of PWRs have been established consideration must be given to the choices for the future energy policy and thirdly new reactor designs should be standardized so the benefits of replication can be realised. (author).

  17. Nuclear Data Verification and Standardization

    Energy Technology Data Exchange (ETDEWEB)

    Karam, Lisa R.; Arif, Muhammad; Thompson, Alan K.

    2011-10-01

    The objective of this interagency program is to provide accurate neutron interaction verification and standardization data for the U.S. Department of Energy Division of Nuclear Physics programs which include astrophysics, radioactive beam studies, and heavy-ion reactions. The measurements made in this program are also useful to other programs that indirectly use the unique properties of the neutron for diagnostic and analytical purposes. These include homeland security, personnel health and safety, nuclear waste disposal, treaty verification, national defense, and nuclear based energy production. The work includes the verification of reference standard cross sections and related neutron data employing the unique facilities and capabilities at NIST and other laboratories as required; leadership and participation in international intercomparisons and collaborations; and the preservation of standard reference deposits. An essential element of the program is critical evaluation of neutron interaction data standards including international coordinations. Data testing of critical data for important applications is included. The program is jointly supported by the Department of Energy and the National Institute of Standards and Technology.

  18. Development of a standard data base for FBR core nuclear design. 9. Analysis of FCA XVII-1 experiments

    International Nuclear Information System (INIS)

    Yokoyama, Kenji; Ishikawa, Makoto; Oigawa, Hiroyuki; Iijima, Susumu

    1998-10-01

    Pnc had developed the adjusted nuclear cross-section library in which the results of the Jupiter experiments were reflected. Using this adjusted library, the distinct improvement of the accuracy in nuclear design of Fbr cores had been achieved. As a recent research, JNC develops a database of other integral data in addition to the JUPITER experiments, aiming at further improvement for accuracy and reliability. In this report, the authors describe the evaluation of the C/E values and the sensitivity analysis for FCA XVII-1 assembly. FCA XVII-1 is a representative mock-up of a MOX fuel sodium cooling FBR core. The criticality, reaction rate ratio, sodium void reactivity worth and 238 U Doppler reactivity worth of FCA XVII-1 were analyzed. The results of C/E values calculated by the standard analytical method for JUPITER experiments are similar to those calculated by the method of JAERI, except for the sodium void reactivity. So, further investigation for sodium void reactivity is necessary. Furthermore, sensitivity analysis shows the characteristics of FCA XVII-1 in comparison with ZPPR-9. (author)

  19. Development of new NSSS thermal-hydraulic model for Korean standard nuclear power plant(UCN-3/4) simulator

    International Nuclear Information System (INIS)

    Kim, Kyung Doo; Jeong, Jae Jun

    2001-09-01

    The NSSS thermal-hydraulic programs installed in the domestic full-scope power plant simulators were provided in early 1980s by foreign vendors. Because of limited computational capability at that time, they usually adopt very simplified physical models for a real-time simulation of NSSS thermal-hydraulic phenomena, which entails inaccurate results and the possibility of so-called 'negative training', especially for complicated two-phase flows in the reactor coolant system. To resolve the problem, we developed a realistic NSSS T/H program (named 'ARTS-UCN' code) for the improvement of the Korean Standard Nuclear Power Plant full-scope simulator. ARTS Code, developed as an NSSS T/H model for the KNPEC no. 2 simulator using the RETRAN03 code, was selected as a reference code for ARTS-UCN code development. For the development of ARTS, the followings have been performed: - Improvement of the robustness of RETRAN - Improvement of the real-time simulation capability of RETRAN - Optimum input data generation for the NSSS simulation - New model development that cannot be efficiently modeled by RETRAN - Assessment of the ARTS code. The systematic assessment of ARTS has been conducted in both personal computers (Windows 98, Visual fortran) and the simulator development environment (Windows NT, GSE simulator development tool). The results were resonable in terms of accuracy, real-time simulation and robustness

  20. The nuclear safety standards of IAEA (NUSS)

    International Nuclear Information System (INIS)

    Andres, H.

    1980-01-01

    The lecture will give an overview of the Agency's Safety Standards for Nuclear Power Plants: its range and its current state of development. The general contents of the documents will be presented, and the procedures used for their development will be briefly described. (orig.)

  1. ISO standardization in nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Brabec, D. (Ustav pro Vyzkum, Vyrobu a Vyuziti Radioisotopu, Prague (Czechoslovakia)); Cermak, O. (Urad pro Normalizaci a Mereni, Prague (Czechoslovakia))

    1984-10-01

    The activity is described of the technical commission ISO/TC 85 which is currently divided into 4 subcommissions (SC) and 24 working groups. SC 1 ''Terminology, definitions, units, abbreviations'' has one working group. The most important document of this SC is ISO 921-1972 (Dictionary of nuclear technology). SC 2 ''Radiation protection'' has 9 working groups and has processed standards in dosimetry. SC 3 ''Technology of power reactors'' has 6 working groups and its work is related to IAEA activities within the NUSS program. SC 4 ''Technology of nuclear fuels'' has 8 working groups. SC 4 has compiled the basic standards for sealed sources and methods of testing their tightness. The results of the work of this group have been reflected into the standardization work of CMEA. A list is given of published international standards within TC 85.

  2. Selecting safety standards for nuclear power plants

    International Nuclear Information System (INIS)

    1981-01-01

    Today, many thousands of documents are available describing the requirements, guidelines, and industrial standards which can be used as bases for a nuclear power plant programme. Many of these documents relate to nuclear safety which is currently the focus of world-wide attention. The multitude of documents available on the subject, and their varying status and emphasis, make the processes of selection and implementation very important. Because nuclear power plants are technically intricate and advanced, particularly in relation to the technological status of many developing countries, these processes are also complicated. These matters were the subject of a seminar held at the Agency's headquarters in Vienna last December. The IAEA Nuclear Safety Standards (NUSS) programme was outlined and explained at the Seminar. The five areas of the NUSS programme for nuclear power plants cover, governmental organization, siting, design; operation; quality assurance. In each area the Agency has issued Codes of Practice and is developing Safety Guides. These provide regulatory agencies with a framework for safety. The Seminar recognized that the NUSS programme should enable developing countries to identify priorities in their work, particularly the implementation of safety standards. The ISO activities in the nuclear field are carried out in the framework of its Technical Committee 85 (ISO/TC85). The work is distributed in sub-committees. Seminar on selection and implementation of safety standards for nuclear power plants, jointly organized by the IAEA and the International Organization for Standardization (ISO), and held in Vienna from 15 to 18 December 1980 concerned with: terminology, definitions, units and symbols (SC-1), radiation protection (SC-2), power reactor technology (SC-3), nuclear fuel technology (SC-5). There was general agreement that the ISO standards are complementary to the NUSS codes and guides. ISO has had close relations with the IAEA for several years

  3. Standardization of Nuclear Instrumentation Applied in the NPP and in other nuclear installations

    International Nuclear Information System (INIS)

    Kusnowo, Arlinah; Darmawati, Suzie

    2002-01-01

    Nuclear power plant (NPP) and other nuclear installations have been recognized as applications needing very sophisticated technologies. One of technologies used in this all nuclear facilities is nuclear instrumentation. In order that NPP and other nuclear installations be operated safely, nuclear instrumentation requires standardization from design to its operation. Internationally, standardizations of nuclear instrumentation have been issued by IEC (International Electrotechnical Commission). Formulation of standard in nuclear instrumentation in IEC is carried out by Technical Committee (TC) 45. This paper describes briefly the standardization of nuclear instrumentation applied in Indonesia as Indonesian National Standard (SNI, Standard National Indonesia), standardization of nuclear instrumentation developed by TC 45, SC 45A, and SC 45B, as well as the possibility to adopt and apply those IEC standard in Indonesia

  4. Analytical Evaluation of Preliminary Drop Tests Performed to Develop a Robust Design for the Standardized DOE Spent Nuclear Fuel Canister

    International Nuclear Information System (INIS)

    Ware, A.G.; Morton, D.K.; Smith, N.L.; Snow, S.D.; Rahl, T.E.

    1999-01-01

    The Department of Energy (DOE) has developed a design concept for a set of standard canisters for the handling, interim storage, transportation, and disposal in the national repository, of DOE spent nuclear fuel (SNF). The standardized DOE SNF canister has to be capable of handling virtually all of the DOE SNF in a variety of potential storage and transportation systems. It must also be acceptable to the repository, based on current and anticipated future requirements. This expected usage mandates a robust design. The canister design has four unique geometries, with lengths of approximately 10 feet or 15 feet, and an outside nominal diameter of 18 inches or 24 inches. The canister has been developed to withstand a drop from 30 feet onto a rigid (flat) surface, sustaining only minor damage - but no rupture - to the pressure (containment) boundary. The majority of the end drop-induced damage is confined to the skirt and lifting/stiffening ring components, which can be removed if de sired after an accidental drop. A canister, with its skirt and stiffening ring removed after an accidental drop, can continue to be used in service with appropriate operational steps being taken. Features of the design concept have been proven through drop testing and finite element analyses of smaller test specimens. Finite element analyses also validated the canister design for drops onto a rigid (flat) surface for a variety of canister orientations at impact, from vertical to 45 degrees off vertical. Actual 30-foot drop testing has also been performed to verify the final design, though limited to just two full-scale test canister drops. In each case, the analytical models accurately predicted the canister response

  5. Harmonized technical standards in the nuclear field

    International Nuclear Information System (INIS)

    Carbone, Ferdinando

    1976-01-01

    The need was felt of harmonizing and gradually standardizing technical norms, from the well-known Anglo-Saxon type codes of practice to the equally well-known recommendations of the International Commission on Radiological Protection (ICRP). The latter provide the basis for the Euratom Directives (basic standards), which, following their adoption, were embodied in the national laws of community Member countries. ISO (International Standardization Organization) is active in the nuclear technical regulations field, in particular through its Committee ISO/TC 85 ''Nuclear Energy'' at international level and, in Italy, through the National Italian Unification Agency (UNI) and its Nuclear Unification Commission (UNICEN). At its XI plenary meeting this body, on the proposal of the Secretary-General, set up a Study Group to promote revision of the regulation in force and coordination between legislation and development of UNICEN standards, considered as a set of integrative industrial technical standards. CISDEN, the Italian Nuclear Energy Forum (FIEN) and other interested organizations have been invited to collaborate in this work. (N.E.A.)

  6. Nuclear Manpower Development

    International Nuclear Information System (INIS)

    Hwang, I. A.; Lee, K. B.; Shin, B. C.

    2010-12-01

    The industry-university-research collaborative education is aiming at developing national nuclear human resources to satisfy with the increasing needs from the industry. For this efforts are being made to develop curricula customized to respective industry needs by improving existing ones. As the demand for training programs for the university students and domestic nuclear personnel was increasing owing to revitalization of nuclear industry, Nuclear Training Center (NTC) improved previous education programs to meet the needs. NTC has operated 2 education programs on research reactor experiments for the university students, and 18 programs on nuclear technology related experiment courses in 2010. Furthermore, the NTC developed new education programs related to 'standardized research reactor system design'. Also the request from universities for internship programs was increased by about three times in 2010 compared to those of the previous year, and this required to develop relevant curricula. In 2005, NTC developed KAERI-ACE, as a unique competency-based staff education system of Korea Atomic Energy Research Institute (KAERI). Based on the system, the NTC has performed 'systematic education'. In 2008, NTC was awarded Best HRD(Human Resource Development) in Public sector for the first time as a government-supported research institute. In 2009, the system was improved to become KAERI-ACE 2.0, based on which, in 2010, NTC improved and diversified education programs including various cyber training programs

  7. Standardization's role in revitalizing the nuclear option

    International Nuclear Information System (INIS)

    Ward, J.E.

    1986-01-01

    Considering the moribund status of the nuclear industry, something has to be done in the near-term to reverse the decaying economics of nuclear power. Standardization can turn around nuclear economics in the short term and in the longer term can foster a significant return to nuclear power. In the short term the industry needs to take advantage of those current designs that have proved their worth by excellent operating records. These designs can be replicated taking advantage of the complete status of the design and the construction techniques already in place. In the longer term it needs to develop preapproved designs and sites. Further, it must develop a discipline within the system of regulation as well as within the utility management to accept a power design as is. They cannot afford customized regulation nor customized design. Traditional institutional structures may also be up for grabs as utilities struggle to be more cost-effective. Generating companies may plan a significant role in the future of electric utilities. This kind of emphasis will also provide an impetus for the use of cost-effective, standardized designs that can be the catalyst for nuclear power's resurgence

  8. Brief overview of American Nuclear Society's research reactor standards

    International Nuclear Information System (INIS)

    Richards, Wade J.

    1984-01-01

    The American Nuclear Society (ANS) established the research reactor standards group in 1968. The standards group, known as ANS-15, was established for the purpose of developing, preparing, and maintaining standards for the design, construction, operation, maintenance, and decommissioning of nuclear reactors intended for research and training

  9. Nuclear performance standards: Promoting efficient generation

    International Nuclear Information System (INIS)

    Nagelhout, M.

    1990-01-01

    Nuclear plant performance standards are designed to share the risks of operation associated with nuclear generation. Such standards often shift risks from ratepayers to utility shareholders, even without a finding of imprudence or mismanagement. The rationale underlying nuclear performance standards is that ratepayers should not be responsible for excessive replacement power costs incurred as a result of unreasonable decisions by utility management, especially because the high fixed costs of nuclear plants are already included in base rates. In addition, performance standards can be designed to provide incentives to reward utilities that achieve superior nuclear performance, for the benefit of both ratepayers and shareholders

  10. Standards and Professional Development

    Science.gov (United States)

    Zengler, Cynthia J.

    2017-01-01

    The purpose of this paper is to describe the professional development that has taken place in conjunction with Ohio adopting the College and Career Readiness (CCR) Standards. The professional development (PD) has changed over time to include not only training on the new standards and lesson plans but training on the concepts defined in the…

  11. Nuclear radiation moisture gauge calibration standard

    International Nuclear Information System (INIS)

    1977-01-01

    A hydrophobic standard for calibrating nuclear radiation moisture gauges is described. Each standard has physical characteristics and dimensions effective for representing to a nuclear gauge undergoing calibration, an infinite mass of homogeneous hydrogen content. Calibration standards are discussed which are suitable for use with surface gauges and with depth gauges. (C.F.)

  12. National standards for the nuclear industry

    International Nuclear Information System (INIS)

    Laing, W.R.; Corbin, L.T.

    1981-01-01

    Standards needs for the nuclear industry are being met by a number of voluntary organizations, such as ANS, ASTM, AWS, ASME, and IEEE. The American National Standards Institute (ANSI) coordinates these activities and approves completed standards as American National Standards. ASTM has two all-nuclear committees, E-10 and C-26. A C-26 subcommittee, Test Methods, has been active in writing analytical chemistry standards for twelve years. Thirteen have been approved as ANSI standards and others are ready for ballot. Work is continuing in all areas of the nuclear fuel cycle

  13. The international dimensions of nuclear safety standards

    International Nuclear Information System (INIS)

    Reed, J.M.

    1992-01-01

    The paper reviews the activities of the major international organisations in the field of nuclear safety standards; the International Atomic Energy Agency (IAEA), the OECD's Nuclear Energy Agency (NEA) and the Commission of the European Communities. Each organisation encourages the concept of international nuclear safety standards. After Chernobyl, there were calls for some form of binding international nuclear safety standards. Many Member States of IAEA accepted these Codes as a suitable basis for formulating their national safety standards, but the prevailing view was that voluntary compliance with the Codes was the preferred path. With few reactor vendors in a limited international market, the time may be approaching when an internationally licensable nuclear reactor is needed. Commonly accepted safety standards would be a prerequisite. The paper discusses the issues involved and the complexities of standards making in the international arena. (author)

  14. Recent activities on nuclear codes and standards

    International Nuclear Information System (INIS)

    Minematsu, Akiyoshi; Ishimoto, Shozaburo; Honjin, Masao

    2000-01-01

    The technical codes and standards relating to the nuclear power stations in Japan are prepared by shapes of laws (ministerial ordinances and bulletins) issued by the government and obliged to comply with by 'the Law concerning the Regulations of Nuclear Material Substances, Nuclear Fuel Substances and Nuclear Reactors' and 'the Electricity Business Act' and of guides defined by the Nuclear Safety Commission, and further some private standards have been issued at a shape of complement of these laws and guides by receiving national recommendation. On the other hand, in the fields of electricity and heat facilities except atomic energy, simplification and feature stipulation of the national technical codes and standards was recently carried out, by which a system usable for the private standards in and out of Japan were prepared through approval of the private Japan Electrotechnical Standards and Codes Committee (JESC). As the nuclear field was now excepted from simultaneous transfer to the private standard and the standard application system, it is expected in future to realize similar transfer if possible and preparation of the private standards is now being advanced. Here were introduced on present state on technical codes and standards relating to the nuclear power generation facilities and recent trends on their private standardization. (G.K.)

  15. Development and evaluation of Standard Operating Procedures (SOPs) for quality control tests and radiological protection activities in a Nuclear Medicine Service

    Energy Technology Data Exchange (ETDEWEB)

    Krempser, Alexandre R., E-mail: krempser@peb.ufrj.br [Universidade Federal do Rio de Janeiro (PEB/COPPE/UFRJ), RJ (Brazil). Programa de Engenharia Biomedica; Soares, Alexandre B. [Universidade Federal do Rio de Janeiro (IF/UFRJ), Rio de Janeiro, RJ (Brazil). Inst. de Fisica; Corbo, Rossana [Universidade Federal do Rio de Janeiro (FM/UFRJ), Rio de Janeiro, RJ (Brazil). Dept. de Radiologia

    2011-07-01

    The quality management in Nuclear Medicine Services is a requirement of national and international standards. The Brazilian regulatory agency in health surveillance, the Agencia Nacional de Vigilancia Sanitaria (ANVISA), in its Resolucao de Diretoria Colegiada (Collegiate Directory Resolution) no. 38, requires the elaboration of documents describing the technical and clinical routine activities. This study aimed to elaborate, implement and evaluate Standard Operating Procedures (SOPs) for quality control tests and radiological protection activities in the Nuclear Medicine Service of a university hospital. Eighteen SOPs were developed, involving tasks related to dose calibrator, gamma camera, Geiger-Muller detectors and radiological protection activities. The performance of its application was evaluated for a period of six months. It was observed a reduction in 75% of reported operational errors and 42% of the number of reported incidents with contamination by radioactive material. The SOPs were adequate and successful in its application. New procedures involving clinical activities will also be developed and evaluated. (author)

  16. Proprietary, standard, and government-supported nuclear data bases

    International Nuclear Information System (INIS)

    Poncelet, C.G.; Ozer, O.; Harris, D.R.

    1975-07-01

    This study presents an assessment of the complex situation surrounding nuclear data bases for nuclear power technology. Requirements for nuclear data bases are identified as regards engineering functions and system applications for the many and various user groups that rely on nuclear data bases. Current practices in the development and generation of nuclear data sets are described, and the competitive aspect of design nuclear data set development is noted. The past and current role of the federal government in nuclear data base development is reviewed, and the relative merits of continued government involvement are explored. National policies of the United States and other industrial countries regarding the availability of nationally supported nuclear data information are reviewed. Current proprietary policies of reactor vendors regarding design library data sets are discussed along with the basis for such proprietary policies. The legal aspects of protective policies are explored as are their impacts on the nuclear power industry as a whole. The effect of the regulatory process on the availability and documentation of nuclear data bases is examined. Current nuclear data standard developments are reviewed, including a discussion of the standard preparation process. Standards currently proposed or in preparation that directly relate to nuclear data bases are discussed in some detail. (auth)

  17. Instant standard concept for data standards development

    NARCIS (Netherlands)

    Folmer, Erwin Johan Albert; Kulcsor, Istvan Zsolt; Roes, Jasper

    2013-01-01

    This paper presents the current results of an ongoing research about a new data standards development concept. The concept is called Instant Standard referring to the pressure that is generated by shrinking the length of the standardization process. Based on this concept it is estimated that the

  18. Nuclear medicine in developing nations

    International Nuclear Information System (INIS)

    Nofal, M.M.

    1985-01-01

    Agency activities in nuclear medicine are directed towards effectively applying techniques to the diagnosis and management of patients attending nuclear medicine units in about 60 developing countries. A corollary purpose is to use these techniques in investigations related to control of parasitic diseases distinctive to some of these countries. Through such efforts, the aim is to improve health standards through better diagnosis, and to achieve a better understanding of disease processes as well as their prevention and management. Among general trends observed for the region: Clinical nuclear medicine; Radiopharmaceuticals; Monoclonal antibodies; Radioimmunoassay (RIA); Nuclear imaging

  19. Working out the standards for nuclear power aging management implementation (PLM Standards)

    International Nuclear Information System (INIS)

    Miyano, Hiroshi

    2008-01-01

    Background of preparation of standards, preparation of standards for development of nuclear power aging management technologies, revision of PLM (Product Lifecycle Management) standards, and problems of PLM standards are stated. The placement of social needs, scheme, the standards system, preparation of rules and standards, and practical use of them by road map are illustrated and explained. Relation between the safety regulations and examination standards, and development and preparation of standards system are outlined. The nuclear power plant aging management and the maintenance control are provided by many rules and standards. PLM standards defines the aging phenomena and extracts the measurements and reflects them on the usual maintenance flow under the long term maintenance program. New examination system constructs the usual maintenance and the maintenance based on the aging management and long term maintenance program. Outline and construction of PLM standards are explained with notes and additional books. (S.Y.)

  20. Progress in standards for nuclear air and gas treatment

    International Nuclear Information System (INIS)

    Burchsted, C.A.

    1978-01-01

    Standardization in nuclear air and gas treatment spans a period of more than 25 years, starting with military specifications for HEPA filters and filter media, and now progressing to the development of a formal code analogous to the ASME Boiler and Pressure Vessel Code. Whereas the current standard for components and installation of nuclear air cleaning systems is limited to safety related facilities for nuclear power plants, the proposed code will cover all types of critical ventilation and air and gas treatment installations for all types of nuclear facilities

  1. ASME nuclear codes and standards risk management strategic plan

    International Nuclear Information System (INIS)

    Balkey, Kenneth R.

    2003-01-01

    Over the past 15 years, several risk-informed initiatives have been completed or are under development within the ASME Nuclear Codes and Standards organization. In order to better manage the numerous initiatives in the future, the ASME Board on Nuclear Codes and Standards has recently developed and approved a Risk Management Strategic Plan. This paper presents the latest approved version of the plan beginning with a background of applications completed to date, including the recent issuance of the ASME Standard for Probabilistic Risk Assessment (PRA) for Nuclear Power Plant Applications. The paper discusses potential applications within ASME Nuclear Codes and Standards that may require expansion of the PRA Standard, such as for new generation reactors, or the development of new PRA Standards. A long-term vision for the potential development and evolution to a nuclear systems code that adopts a risk-informed approach across a facility life-cycle (design, construction, operation, maintenance, and closure) is summarized. Finally, near term and long term actions are defined across the ASME Nuclear Codes and Standards organizations related to risk management, and related U.S. regulatory activities are also summarized. (author)

  2. Nonreactor nuclear facilities: standards and criteria guide

    International Nuclear Information System (INIS)

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

    1981-09-01

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

  3. Nonreactor nuclear facilities: Standards and criteria guide

    International Nuclear Information System (INIS)

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

    1986-09-01

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

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

    International Nuclear Information System (INIS)

    Gonzalez, Abel J.

    1997-01-01

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

  5. Nuclear radiation moisture gauge calibration standard

    International Nuclear Information System (INIS)

    Berry, R.L.

    1981-01-01

    A hydrophobic standard for calibrating radiation moisture gauges is described. This standard has little or no affinity for water and accordingly will not take up or give off water under ambient conditions of fluctuating humidity in such a manner as to change the hydrogen content presented to a nuclear gauge undergoing calibration. (O.T.)

  6. Romanian nuclear fuel cycle development

    International Nuclear Information System (INIS)

    Rapeanu, S.N.; Comsa, Olivia

    1998-01-01

    Romanian decision to introduce nuclear power was based on the evaluation of electricity demand and supply as well as a domestic resources assessment. The option was the introduction of CANDU-PHWR through a license agreement with AECL Canada. The major factors in this choice have been the need of diversifying the energy resources, the improvement the national industry and the independence of foreign suppliers. Romanian Nuclear Power Program envisaged a large national participation in Cernavoda NPP completion, in the development of nuclear fuel cycle facilities and horizontal industry, in R and D and human resources. As consequence, important support was being given to development of industries involved in Nuclear Fuel Cycle and manufacturing of equipment and nuclear materials based on technology transfer, implementation of advanced design execution standards, QA procedures and current nuclear safety requirements at international level. Unit 1 of the first Romanian nuclear power plant, Cernavoda NPP with a final profile 5x700 Mw e, is now in operation and its production represents 10% of all national electricity production. There were also developed all stages of FRONT END of Nuclear Fuel Cycle as well as programs for spent fuel and waste management. Industrial facilities for uranian production, U 3 O 8 concentrate, UO 2 powder and CANDU fuel bundles, as well as heavy water plant, supply the required fuel and heavy water for Cernavoda NPP. The paper presents the Romanian activities in Nuclear Fuel Cycle and waste management fields. (authors)

  7. Nuclear buildings and sustainable development

    International Nuclear Information System (INIS)

    Gomah, A.M.H

    2009-01-01

    The main proposal of this thesis based on some practical notes and the theoretical readings, the mathematical equations which led to existing a shared relationship between the nuclear institutions and the economical development with preserving the environment and its recourses which achieves the concept of the sustainable development. The thesis aims also at recognizing the most important characteristics of the nuclear institutions , as the study interests in understanding how the nuclear energy can be distinguished from the other energy resources. Furthermore, the study in its intellectual framework interests in comparing a number of the nuclear institutions that the study finds them related to the research topic and assists in achieving the study goals, which represent in the environmental evaluation of the nuclear institutions inside its biological surroundings. The study consists of four main chapters in addition to the introduction and the conclusion as follows: The first chapter: Recognizing the nuclear institutions and their effect on the environment. The second chapter: Recognizing planning and generalizing the nuclear institutions. The third chapter: Recognizing the limits and standards of the planning and the designing of a nuclear institution. The fourth chapter: The nuclear institutions inside the suburban places.

  8. Development of nuclear power

    International Nuclear Information System (INIS)

    1960-01-01

    The discussion on the development of nuclear power took place on 28 September 1960 in Vienna. In his opening remarks, Director General Cole referred to the widespread opinion that 'the prospect of cheap electricity derived from nuclear energy offers the most exciting prospect for improving the lot of mankind of all of the opportunities for uses of atomic energy'. He then introduced the four speakers and the moderator of the discussion, Mr. H. de Laboulaye, IAEA Deputy Director General for Technical Operations. n the first part of the discussion the experts addressed themselves in turn to four topics put forward by the moderator. These were: the present technical status of nuclear power, the present costs of nuclear power, prospects for future reductions in the cost of nuclear power, and applications of nuclear power in less-developed areas

  9. Nuclear power development

    International Nuclear Information System (INIS)

    Povolny, M.

    1980-01-01

    The development and uses of nuclear power in Czechoslovakia and other countries are briefly outlined. In the first stage, the Czechoslovak nuclear programme was oriented to the WWER 440 type reactor while the second stage of the nuclear power plant construction is oriented to the WWER 10O0 type reactor. It is envisaged that 12 WWER 440 type reactors and four to five WWER 1000 type reactors will be commissioned till 1990. (J.P.)

  10. JPRS Report, Nuclear Developments

    Science.gov (United States)

    1990-12-06

    ban on that flail away at each other in maneuvers designed to nuclear tests (sic), even for peaceful purposes, across build up influence . Whatever...uranium and develop reactors for nuclear can help Mr. Collor nudge (away from the nuclear submarines. program) his fractious military along by suspending...two and a half years to behaviour to qualify for a certificate. WASHINGTON permit the second six-year aid package for 1988-93, was POST has meanwhile

  11. ASME nuclear codes and standards risk management strategic planning

    International Nuclear Information System (INIS)

    Hill, Ralph S. III; Balkey, Kenneth R.; Erler, Bryan A.; Wesley Rowley, C.

    2007-01-01

    This paper is prepared in honor and in memory of the late Professor Emeritus Yasuhide Asada to recognize his contributions to ASME Nuclear Codes and Standards initiatives, particularly those related to risk-informed technology and System Based Code developments. For nearly two decades, numerous risk-informed initiatives have been completed or are under development within the ASME Nuclear Codes and Standards organization. In order to properly manage the numerous initiatives currently underway or planned for the future, the ASME Board on Nuclear Codes and Standards (BNCS) has an established Risk Management Strategic Plan (Plan) that is maintained and updated by the ASME BNCS Risk Management Task Group. This paper presents the latest approved version of the plan beginning with a background of applications completed to date, including the recent probabilistic risk assessment (PRA) standards developments for nuclear power plant applications. The paper discusses planned applications within ASME Nuclear Codes and Standards that will require expansion of the ASME PRA Standard to support new advanced light water reactor and next generation reactor developments, such as for high temperature gas-cooled reactors. Emerging regulatory developments related to risk-informed, performance- based approaches are summarized. A long-term vision for the potential development and evolution to a nuclear systems code that adopts a risk-informed approach across a facility life-cycle (design, construction, operation, maintenance, and closure) is also summarized. Finally, near term and long term actions are defined across the ASME Nuclear Codes and Standards organizations related to risk management, including related U.S. regulatory activities. (author)

  12. Nuclear power development

    International Nuclear Information System (INIS)

    Nealey, S.

    1990-01-01

    The objective of this study is to examine factors and prospects for a resumption in growth of nuclear power in the United States over the next decade. The focus of analysis on the likelihood that current efforts in the United States to develop improved and safer nuclear power reactors will provide a sound technical basis for improved acceptance of nuclear power, and contribute to a social/political climate more conducive to a resumption of nuclear power growth. The acceptability of nuclear power and advanced reactors to five social/political sectors in the U.S. is examined. Three sectors highly relevant to the prospects for a restart of nuclear power plant construction are the financial sector involved in financing nuclear power plant construction, the federal nuclear regulatory sector, and the national political sector. For this analysis, the general public are divided into two groups: those who are knowledgeable about and involved in nuclear power issues, the involved public, and the much larger body of the general public that is relatively uninvolved in the controversy over nuclear power

  13. Nuclear development in Korea

    International Nuclear Information System (INIS)

    Lee Byong Whi

    1993-10-01

    The Korean research and development project ''evelopment of Next Generation Reactor Technology'' aimed at the 21st century is briefly outlined. Activities directed to improvement of public acceptance of nuclear energy, the public information and education on the advanced nuclear reactor and fuel cycle technology are described

  14. Nuclear data development work in support of the National Bureau of Standards ISNF Project. Status report, February 1976-July 1980

    International Nuclear Information System (INIS)

    LaBauve, R.J.; George, D.C.; Muir, D.W.; Soran, P.D.; Eisenhauer, C.M.

    1980-12-01

    Work in several areas was completed by the Los Alamos Scientific Laboratory for the National Bureau of Standards in connection with the Intermediate-Energy Standard Neutron Field (ISNF) project during this reporting period. These areas include supplying multigroup cross section sets from ENDF/B-IV appropriate for ISNF calculations; determining the effects of small changes in calculational parameters, including cross section changes, in LSNF results; providing additional selected multigroup cross section sets from both ENDF/B-IV and ENDF/B-V; and performing comparison ISNF calculations using discrete ordinates and Monte Carlo codes. Plans for future work are briefly mentioned. 12 figures, 5 tables

  15. Future direction of ASME nuclear codes and standards

    International Nuclear Information System (INIS)

    Ennis, Kevin; Sheehan, Mark E.

    2003-01-01

    While the nuclear power industry in the US is in a period of stasis, there continues to be a great deal of activity in the ASME nuclear standards development arena. As plants age, the need for new approaches in standardization changes with the changing needs of the industry. New tools are becoming available in the form of risk analysis, and this is finding its way into more and more of ASME's standards activities. This paper will take a look at the direction that ASME nuclear Codes and Standards are heading in this and other areas, as well as taking a look at some advance reactor concepts and plans for standards to address new technologies

  16. JPRS Report, Nuclear Developments

    National Research Council Canada - National Science Library

    1991-01-01

    Partial Contents: Medium Range Missiles, Rocket Engine, Nuclear Submarine, Nuclear Reactor, Nuclear Inspection, Nuclear Weapons, Transfer Technology, Scud, Safety, Nuclear Power, Chernobyl Trial, ,CHemical Weapons...

  17. Nuclear manpower development

    International Nuclear Information System (INIS)

    Hwang, I. A.; Lee, K. B.; Shin, B. C.

    2011-12-01

    The nuclear manpower development project has concentrated on the systemisation and specialization of education and training programs and has actively carried out diverse activities to create new nuclear courses based on the experience of the Nuclear Training and Education Center (NTC) accumulated over the past years. As the demand of education program for training nuclear manpower is increasing due to the remarkable growth of nuclear industry, NTC developed customized education programs making the most use of nuclear experiment equipment and providing practical exercise with research reactor. For improving organizational performance and the development of skilled manpower, KAERI-ACE 2.0 system offered diverse programs addressing the type of occupation and position based on individual competency. Also education on IT was carried out to improve public relations on nuclear and field trips were arranged to encourage local residents' better understanding of the nuclear industry. As a continuous effort, In 2011, NTC specially conducted a survey of employees who are attached to small and medium sized business, and analyzed the present business situations and education requirements for the development of a Pre/under job education program. Prior to this, a briefing session took place for mutual exchange of opinions of industry and academia, based on which a test operation on 'Basic Radiation Education' was carried out. This program has a significance that it was first step toward connection between the nuclear industry and academia as well as an opportunity to educate the employee involved in nuclear engineering field. In 2012, this program is planned to be expanded. With reference to the in-house training, NTC established an 'e-HRD system' providing available resources concerned with education program for cultivating talented personnel. All the education programs are based on individual competency. The e-HRD system will be test operated in 2012 and applied to the

  18. Standards: An international framework for nuclear safety

    International Nuclear Information System (INIS)

    Versteeg, J.

    2000-01-01

    The IAEA, uniquely among international organizations concerned with the use of radiation, radioactive materials and nuclear energy, has statutory functions to establish safety standards and to provide for their application in Member States. The IAEA also contributes towards another major element of the 'global safety culture', namely the establishment of legally binding international agreements on safety related issues. (author)

  19. Walk the Line: The Development of Route Selection Standards for Spent Nuclear Fuel and High-level Radioactive Waste in the United States - 13519

    Energy Technology Data Exchange (ETDEWEB)

    Dilger, Fred [Black Mountain Research, Henderson, NV 81012 (United States); Halstead, Robert J. [State of Nevada Agency for Nuclear Projects, Carson City, NV 80906 (United States); Ballard, James D. [Department of Sociology, California State University, Northridge, CA 91330 (United States)

    2013-07-01

    Although storage facilities for spent nuclear fuel (SNF) and high-level radioactive waste (HLRW) are widely dispersed throughout the United States, these materials are also relatively concentrated in terms of geographic area. That is, the impacts of storage occur in a very small geographic space. Once shipments begin to a national repository or centralized interim storage facility, the impacts of SNF and HLRW will become more geographically distributed, more publicly visible, and almost certainly more contentious. The selection of shipping routes will likely be a major source of controversy. This paper describes the development of procedures, regulations, and standards for the selection of routes used to ship spent nuclear fuel and high-level radioactive waste in the United States. The paper begins by reviewing the circumstances around the development of HM-164 routing guidelines. The paper discusses the significance of New York City versus the Department of Transportation and application of HM-164. The paper describes the methods used to implement those regulations. The paper will also describe the current HM-164 designated routes and will provide a summary data analysis of their characteristics. This analysis will reveal the relatively small spatial scale of the effects of HM 164. The paper will then describe subsequent developments that have affected route selection for these materials. These developments include the use of 'representative routes' found in the Department of Energy (DOE) 2008 Supplemental Environmental Impact Statement for the formerly proposed Yucca Mountain geologic repository. The paper will describe recommendations related to route selection found in the National Academy of Sciences 2006 report Going the Distance, as well as recommendations found in the 2012 Final Report of the Blue Ribbon Commission on America's Nuclear Future. The paper will examine recently promulgated federal regulations (HM-232) for selection of rail

  20. Low Impact Development Standards

    Energy Technology Data Exchange (ETDEWEB)

    Loftin, Samuel R. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-10-02

    The goal of the LID Standards is to provide guidance on the planning, design, construction and maintenance of green infrastructure (GI) features at Los Alamos National Laboratory. The success of LID at LANL is dependent on maintaining a consistent approach to achieve effective application, operation, and maintenance of these storm water control features.

  1. Nuclear Manpower Development

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, I. A.; Lee, T. J.; Lee, K. B.; and others

    2012-12-15

    The nuclear manpower development project has concentrated on the systemization and specialization of education and training programs and has actively carried out diverse activities to create new nuclear courses based on the experience of the Nuclear Training and Education Center (NTC) accumulated over the past years. NTC has developed customized education programs on 'Nuclear Introduction' to educate new employees of the Korea Electric Power Corporation (KEPCO) and on 'Technical education for criticality and shielding analysis of the spent fuel' for employees of the Doosan Heavy Industries and Construction. NTC has also developed specialized education programs for the students of nuclear engineering departments and sciences and engineering departments in universities making the most use of experimental equipment at KAERI and providing practical exercise with the research reactor, HANARO. For improving organizational performance and the development of skilled manpower, KAERI-ACE system has offered diverse programs addressing individual competency of industry personnel in terms of type of occupation and position. Also education on IT has been carried out to improve public relations on nuclear and field trips have been arranged to encourage local residents' better understanding of the nuclear industry. As the final outcome, NTC has developed 6 new education programs for employees in industry and students in academia, and offered 64 courses to 9,630 persons (273 domestic nuclear personnel, 509 university students, 8,075 KAERI staff, 773 local resident). Especially, in 2012, NTC is honored to won 'Presidential Awards of National Quality Management Awards'. This present that KAERI-ACE system has performed well through a improvement in recent years.

  2. Nuclear Buildings And Sustainable Development

    International Nuclear Information System (INIS)

    Gomah, A.El.M.H.

    2009-01-01

    The main proposal of this Thesis based on some practical notes and the theoretical readings, the mathematical equations which led to existing a shared relationship between the nuclear institutions and the economical development with preserving the environment and its recourses which achieves the concept of the sustainable development. The Thesis aims also at recognizing the most important characteristics of the nuclear institutions, as the study interests in understanding how the nuclear energy can be distinguished from the other energy resources. Furthermore, the study in its intellectual framework interests in comparing a number of the nuclear institutions that the study finds them related to the research topic and assists in achieving the study goals ,which represent in the environmental evaluation of the nuclear institutions inside its biological surroundings. The study consists of four main chapters in addition to the introduction and the conclusion as follows: The first chapter: recognizing the nuclear institutions and their effect on the environment. This chapter includes studying the characteristics of the nuclear institutions in the frame of its existence in the atmospheric surroundings and this chapter includes: 1- The kinds of the nuclear institutions, the troubles and incidents resulting in them and comparing between it and the study of the nuclear fuel. 2- The economical importance of the nuclear institutions and participating it in the process of developing. The role of the agency of preserving the environment and the extent of its ability to deal with the nuclear incidents and training and guiding the inhabitants how to deal with these incidents.The second chapter: recognizing planning and generalizing the nuclear institutions.This chapter handles by the study and analysis the nature of the nuclear institutions and the development in their designs according to the development in the designs of the nuclear institutions and this chapter includes:1- The

  3. The status of Korean nuclear codes and standards

    International Nuclear Information System (INIS)

    Namha Kim; Jong-Hae Kim

    2005-01-01

    Korea Electric Power Industry Code (KEPIC), a set of integrated standards applicable to the design, construction and operation of electric power facilities including nuclear power plants, has been developed on the basis of referring to the prevailing U.S. codes and standards which had been applied to the electric power facilities in Korea. Being the developing and managing organization of KEPIC, Korea Electric Association (KEA) published its first edition in 1995, the second in 200,0 and is expected to publish the 2005 edition. KEPIC was applied to the construction of Ulchin Nuclear Units 5 and 6 in 1997, and will be applicable to the construction of forthcoming nuclear power plants in Korea. Along with the effectuation of the Agreement on Technical Barriers to Trade (TBT) in 1995, the international trend related to codes and standards is changing rapidly. The KEA is, therefore, making its utmost efforts so as for KEPIC to keep abreast with the changing environment in international arena. KEA notified ISO/IEC Information Centre of its acceptance of the Code of Good Practice in the Agreement on TBT. The 2005 KEPIC edition will be retrofitted according to the ISO/IEC Guide 21- Adoption of International Standards as regional or national standards. KEA's efforts will help KEPIC correspond with international standards such as ISO/IEC standards, and internationally recognized standards such as ASME codes and standards. (authors)

  4. Present problems of standardization in nuclear instrumentation in Romania

    International Nuclear Information System (INIS)

    Purghel, Lidia

    2001-01-01

    The continuos development of nuclear techniques, based on international cooperation, led to the need for producing national and international standards referring to terminology, classification, technical characteristic, testing and calibration methods for nuclear instrumentation. The international standardization activity is organised in the frame of the well-known organization like IEC, ISO, ICRU, ICRP, IOLM, CENELEC, EFOMP, WHO. High advances were obtained in the standardization of the ionising radiation dosimetry in the frame of the International Commission for Radiation Units (ICRU) which started its works 1925. Romania is member of the International Electrotechnical Commission (IEC) from 1920 when its president was the formal member of Romanian Academy, professor Remus Radulet. Romania is effectively involved in standardization activities in the field nuclear instrumentation both as user and manufacturer of nuclear instrumentation. At national level the Technical Committee 45, as a branch of the Romanian Electrotechnical Committee is hosted by Horia Hulubei National Institute for Physics and Nuclear Engineering. The technical committee has the tasks of analysing the market, the regulations and the industry requirements and proposing new standards or revision for existing one. A table is given showing the number of IEC standards considered by TC 45, adopted RS - IEC standards (prepared/published) and planned for 2000/2001. Romania hosted IEC international plenary meetings in 1962 and 1974 and an IEC workshop 1997 with participation of specialists from USA, Sweden, Germany, France, Japan and Romania. As industry is striving to use more and more standard products, that means best quality and safety for less money, more than ever one have to convince the industry about the usefulness and specificity of the nuclear standards

  5. Development, standardization and validation of nuclear based technologies for estimating microbial protein supply in ruminant livestock for improving productivity

    International Nuclear Information System (INIS)

    Makkar, H.P.S.

    2004-01-01

    The primary constraint to livestock production in developing countries is the scarcity and fluctuating quantity and quality of the year-round feed supply. These countries experience serious shortages of animal feeds and fodders of the conventional type. Natural forages are very variable both in quality and quantity, conventional agro-industrial by-products are scarce and vary seasonal, and grains are required almost exclusively for human consumption. The small farmers in developing countries have limited resources available to them for feeding their ruminant livestock. Poor nutrition results in low rates of reproduction and production as well as increased susceptibility to disease and mortality. Providing adequate good-quality feed to livestock to raise and maintain their productivity is a major challenge to agricultural scientists and policy makers all over the world. Recent advances in ration balancing include manipulation of feed to increase the quantity and quality of protein and energy delivered to the small intestine. Selection of feeds based on high efficiency of microbial protein synthesis in the rumen along with the high dry matter digestibility, and development of feeding strategies based on high efficiency as well as high microbial protein synthesis in the rumen will lead to higher supply of protein post-ruminally. The strategy for improving production has therefore been to maximize the efficiency of utilization of available feed resources in the rumen by providing optimum conditions for microbial growth and thereby supplementing dietary nutrients to complement and balance the products of rumen digestion to the animal's requirement

  6. American National Standard: nuclear data sets for reactor design calculations

    International Nuclear Information System (INIS)

    1983-01-01

    This standard identifies and describes the specifications for developing, preparing, and documenting nuclear data sets to be used in reactor design calculations. The specifications include criteria for acceptance of evaluated nuclear data sets, criteria for processing evaluated data and preparation of processed continuous data and averaged data sets, and identification of specific evaluated, processed continuous, and averaged data sets which meet these criteria for specific reactor types

  7. American National Standard nuclear data sets for reactor design calculations

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    A standard is presented which identifies and describes the specifications for developing, preparing, and documenting nuclear data sets to be used in reactor design calculations. The specifications include (a) criteria for acceptance of evaluated nuclear data sets, (b) criteria for processing evaluated data and preparation of processed continuous data and averaged data sets, and (c) identification of specific evaluated, processed continuous, and averaged data sets which meet these criteria for specific reactor types

  8. Merits and difficulties in adopting codes, standards and nuclear regulations

    International Nuclear Information System (INIS)

    El-Saiedi, A.F.; Morsy, S.; Mariy, A.

    1978-01-01

    Developing countries planning for introducing nuclear power plants as a source of energy have to develop or adopt sound regulatory practices. These are necessary to help governmental authorities to assess the safety of nuclear power plants and to perform inspections needed to confirm the established safe and sound limits. The first requirement is to form an independent regulatory body capable of setting up and enforcing proper safety regulations. The formation of this body is governed by several considerations related to local conditions in the developing countries, which may not always be favourable. It is quite impractical for countries with limited experience in the nuclear power field to develop their own codes, standards and regulations required for the nuclear regulatory body to perform its tasks. A practical way is to adopt codes, standards and regulations of a well-developed country. This has merits as well as drawbacks. The latter are related to problems of personnel, software, equipment and facilities. The difficulties involved in forming a nuclear regulatory body, and the merits and difficulties in adopting foreign codes, standards and regulations required for such body to perform its tasks, are discussed in this paper. Discussions are applicable to many developing countries and particular emphasis is given to the conditions and practices in Egypt. (author)

  9. Nuclear Power and Sustainable Development

    International Nuclear Information System (INIS)

    2006-04-01

    Any discussion of 21st century energy trends must take into account the global energy imbalance. Roughly 1.6 billion people still lack access to modern energy services, and few aspects of development - whether related to living standards, health care or industrial productivity - can take place without the requisite supply of energy. As we look to the century before us, the growth in energy demand will be substantial, and 'connecting the unconnected' will be a key to progress. Another challenge will be sustainability. How can we meet these growing energy needs without creating negative side effects that could compromise the living environment of future generations? Nuclear power is not a 'fix-all' option. It is a choice that has a place among the mix of solutions, and expectations for the expanding use of nuclear power are rising. In addition to the growth in demand, these expectations are driven by energy security concerns, nuclear power's low greenhouse gas emissions, and the sustained strong performance of nuclear plants. Each country must make its own energy choices; one size does not fit all. But for those countries interested in making nuclear power part of their sustainable development strategies, it is important that the nuclear power option be kept open and accessible

  10. Development of nuclear power

    International Nuclear Information System (INIS)

    1962-01-01

    An extensive discussion of problems concerning the development of nuclear power took place at the fifth regular session of the IAEA General Conference in September-October 1961. Not only were there many references in plenary meetings to the nuclear power plans of Member States, but there was also a more specific and detailed debate on the subject, especially on nuclear power costs, in the Program, Technical and Budget Committee of the Conference. The Conference had before it a report from the Board of Governors on the studies made by the Agency on the economics of nuclear power. In addition, it had been presented with two detailed documents, one containing a review of present-day costs of nuclear power and the other containing technical and economic information on several small and medium-sized power reactors in the United States. The Conference was also informed of the report on methods of estimating nuclear power costs, prepared with the assistance of a panel of experts convened by the Agency, which was reviewed in the July 1961 issue of this Bulletin

  11. Development of nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1962-01-15

    An extensive discussion of problems concerning the development of nuclear power took place at the fifth regular session of the IAEA General Conference in September-October 1961. Not only were there many references in plenary meetings to the nuclear power plans of Member States, but there was also a more specific and detailed debate on the subject, especially on nuclear power costs, in the Program, Technical and Budget Committee of the Conference. The Conference had before it a report from the Board of Governors on the studies made by the Agency on the economics of nuclear power. In addition, it had been presented with two detailed documents, one containing a review of present-day costs of nuclear power and the other containing technical and economic information on several small and medium-sized power reactors in the United States. The Conference was also informed of the report on methods of estimating nuclear power costs, prepared with the assistance of a panel of experts convened by the Agency, which was reviewed in the July 1961 issue of this Bulletin

  12. The sustainable development of nuclear energy

    International Nuclear Information System (INIS)

    Guo Huifang

    2012-01-01

    The wide use of nuclear energy has promoted the development of China's economy and the improvement of people's living standards. To some extent, the exploitation of nuclear power plants will solve the energy crisis faced with human society. Before the utilization of nuclear fusion energy, nuclear fission energy will be greatly needed for the purpose of alleviating energy crisis for a long period of time. Compared with fossil fuel, on the one hand, nuclear fission energy is more cost-efficient and cleaner, but on the other hand it will bring about many problems hard to deal with, such as the reprocessing and disposal of nuclear spent fuel, the contradiction between nuclear deficiency and nuclear development. This paper will illustrate the future and prospect of nuclear energy from the perspective of the difficulty of nuclear development, the present reprocessing way of spent fuel, and the measures taken to ensure the sustainable development of nuclear energy. By the means of data quoting and comparison, the feasibility of sustainable development of nuclear energy will be analyzed and the conclusion that as long as the nuclear fuel cycling system is established the sustainable development of nuclear energy could be a reality will be drawn. (author)

  13. Nuclear energy and development

    International Nuclear Information System (INIS)

    1991-01-01

    Today, about 80 developing countries are using nuclear techniques in various sectors of their national economies. In the sector of industry, the radiation processing using gamma rays of high energy electrons has grown. While in the sector of health care, an estimated 10000 gamma cameras-imaging instruments are used in combination with radioisotopes in medical diagnosis. In the field of agriculture there is, nearly, 1000 crop varieties derived from radiaton-induced mutations which are grown worldwide. Furthermore and concerning the energy sector there is 417 nuclear power plants operating in 26 countries, accounting for just 16% of the world's total electricity production; the nuclear energy helped in developing and supporting a variety of sciences. 2 tabs

  14. Principles and standards of nuclear safety and their implementation

    International Nuclear Information System (INIS)

    Franzen, L.F.

    1979-01-01

    Nuclear safety starts with the design of a nuclear facility and is only completed with its decommissioning. In the various phases of a nuclear facility's lifetime, safety evaluations are required. The licensing prerequisites for construction, operation, modification, decommissioning are based on elements of the relevant national legislation and related ordinances as well as on international regulations. They should be expanded by a system of criteria and standards spelling out the proven practice as developed over the last decades in the industrialized countries and by international organizations such IAEA with its safety codes and guides. (NEA) [fr

  15. Referring to IAEA system to improve Chinese standards system on nuclear and radiation safety

    International Nuclear Information System (INIS)

    Shang Zhaorong; Wang Wenhai

    2010-01-01

    Referring to the standards system of IAEA, to build and improve the Chinese standards system of nuclear and radiation safety is a long term infrastructure work and an assurance to keep sustainable development of nuclear industry and nuclear technology application in China. The paper analyses the current main problem, and gives some suggestions on developing and improving the system. (authors)

  16. Standards for psychological assessment of nuclear facility personnel. Technical report

    International Nuclear Information System (INIS)

    Frank, F.D.; Lindley, B.S.; Cohen, R.A.

    1981-07-01

    The subject of this study was the development of standards for the assessment of emotional instability in applicants for nuclear facility positions. The investigation covered all positions associated with a nuclear facility. Conclusions reached in this investigation focused on the ingredients of an integrated selection system including the use of personality tests, situational simulations, and the clinical interview; the need for professional standards to ensure quality control; the need for a uniform selection system as organizations vary considerably in terms of instruments presently used; and the need for an on-the-job behavioral observation program

  17. Factors affecting nuclear development

    International Nuclear Information System (INIS)

    Stevens, G.H.; Girouard, P.

    1995-01-01

    Among the factors affecting nuclear development, some depend more or less on public authorities, but many are out of public authorities control (foreign policies, market and deregulation, socials and environmental impacts, public opinion). As far as possible, the following study tries to identify those factors. (D.L.). 2 photos

  18. Development of a standard database for FBR core nuclear design (XI). Analysis of the Experimental Fast Reactor 'JOYO' MK-I start-up test and operation data

    International Nuclear Information System (INIS)

    Yokoyama, Kenji; Numata, Kazuyuki

    2000-03-01

    As a recent research, Japan Nuclear Cycle Development Institute (JNC) develops a database of integral data in addition to the JUPITER experiments, aiming at further improvement for accuracy and reliability. In this report, the authors describe the evaluation of the C/E values and the sensitivity analysis for the Experimental Fast Reactor 'JOYO' MK-I core. The minimal criticality, sodium void reactivity worth, fuel assembly worth and burn-up coefficient were analyzed. The results of both the minimal criticality and the fuel assembly worth, which were calculated by the standard analytical method for JUPITER experiments, agreed well with the measured values. On the other hand, the results of the sodium void reactivity worth have a tendency to overestimate. As for the burn-up coefficient, it was seen that the C/E values had a dispersion among the operation cycles. The authors judged that further investigation for the estimation of the experimental error will increase the applicability of the integral data to the adjusted library. Furthermore, sensitivity analyses for the minimal criticality, sodium void reactivity worth and fuel assembly worth showed the characteristics of 'JOYO' MK-I core in comparison with ZPPR-9 core of JUPITER experiments. (J.P.N.)

  19. Development of porcine transgenic nuclear-transferred embryos derived from fibroblast cells transfected by the novel technique of nucleofection or standard lipofection.

    Science.gov (United States)

    Skrzyszowska, M; Samiec, M; Słomski, R; Lipiński, D; Mały, E

    2008-07-15

    The aim of our study was to determine the in vitro developmental potential of porcine nuclear-transferred (NT) embryos that had been reconstructed with Tg(pWAPhGH-GFPBsd) transgene-expressing fibroblast cells. The gene construct was introduced into fibroblast cells by the novel method of nucleofection or standard lipofection. NT oocytes derived from foetal and adult dermal fibroblast cells were stimulated by either simultaneous fusion and electrical activation (Groups IA and IB) or sequential electrical and chemical activation (Groups IIA and IIB). The percentages of cloned embryos that reached the morula and blastocyst stages were 152/254 (59.8%) and 77/254 (30.3%) or 139/276 (50.4%) and 45/276 (16.3%) in Groups IA or IB, respectively. The rates of NT embryos that developed to the morula and blastocyst stages were 103/179 (57.5%) and 41/179 (22.9%) or 84/193 (43.5%) and 27/193 (14.0%) in Groups IIA and IIB, respectively. In conclusion, the in vitro developmental competences of porcine transgenic NT embryos that had been reconstructed with the Tg(pWAPhGH-GFPBsd) gene-transfected fibroblast cells were relatively high. Further, the nucleofection efficiency of all the porcine fibroblast cell lines as estimated by intra-vitam fluorescent evaluation based on the index of reporter eGFP transgene expression was nearly 100%. However, PCR analysis for transgene screening confirmed the absence of Tg(pWAPhGH-GFPBsd) fusion gene in some of the nucleofected cell lines. To our knowledge, the novel method of nucleofection is the first to transfect nuclear donor cells in the production of transgenic cloned embryos.

  20. JPRS Report, Nuclear Developments

    Science.gov (United States)

    1989-06-14

    area. Today, it is theincreasingly larger mountains of radioactive waste. Disneyland of nuclear technology. That is where the industrious Teko stands ...Africa is ready to launch her own space century, the world is likely to split into two major blocs: program, when financial resources permit. The...enrichment development of developing communities. Given our technology; shaft sinking and deep level mining exper- limited financial resources

  1. Arrangement between the US Nuclear Regulatory Commission (USNRC) and the Belgian Government for Exchange of Technical Information in Regulatory Matters and in Cooperation in Safety Research and in Standards Development

    International Nuclear Information System (INIS)

    1978-01-01

    This Arrangement was concluded on 6 June 1978 between the United States Nuclear Regulatory Commission and the Belgian Government for exchange of technical information in regulatory matters and in co-operation in safety research and in standards development. Both Parties agree to exchange, as available, technical information related to the regulation of safety and the environmental impact of designated nuclear energy facilities and to safety research of designated types of nuclear facilities. As regards co-operation in safety research, the execution of joint programmes and projects under which activities are divided between the two Parties will be agreed on a case by case basis. The Parties further agree to co-operate in the development of regulatory standards applicable to the designated nuclear facilities. The Arrangement is valid for 5 years and may be extended. (NEA) [fr

  2. Standards development status. Summary report

    International Nuclear Information System (INIS)

    1981-12-01

    The Standards Development Status Summary Report is designed for scheduling, monitoring, and controlling the process by which Regulatory Standards, Guides, Reports, Petitions, and Environmental Statements are written. It is a summary of the current schedule plans for development of the above products

  3. Thirty years of international nuclear standards in ISO and IEC

    International Nuclear Information System (INIS)

    Becker, K.

    1991-01-01

    Of over 4700 nuclear and radiation protection standards, laws, regulations, recommendations, etc., which have been issued by 52 countries and several governmental international organizations such as IAEA, or non-government organizations such as ICRP, ICRU, ISO and IEC, more than 90% are national, and more than half of those of a non-regulatory nature. Both number and importance of international standards are, however, increasing. The two most important non-governmental international standards organizations are the International Organization for Standardization (ISO), which founded a Technical Committee (TC) 85 'Nuclear Energy' with several Sub-Committees in 1957, and the closely associated International Electrotechnical Commission (IEC) with its TC 45 'Nuclear Instrumentation' formed in 1960. There are over 20 member countries actively participating in the work in each of them, with additional observer countries and liaison to the relevant other international organizations. A brief review is given on some of the experience which has been gained by ISO/TC 85 and IEC/TC 45, and its work program and accomplishments, considering in particular recent developments. It covers nuclear safety and instrumentation, radiation protection, and the nuclear fuel cycle, as well as interface issues including definitions and terminology, interaction of the activities with the work of other national and international bodies, etc. Some problem areas are also briefly discussed. (orig.)

  4. Nuclear and sustainable development

    International Nuclear Information System (INIS)

    Audebert, P.; Balle, St.; Barandas, Ch.; Basse-Cathalinat, B.; Bellefontaine, E.; Bernard, H.; Bouhand, M.H.; Bourg, D.; Bourgoignon, F.; Bourlat, Y.; Brunet, F.; Buclet, N.; Buquet, N.; Caron, P.; Cartier, M.; Chagneau, E.; Charles, D.; Chateau, G.; Collette, P.; Collignon, A.; Comtesse, Ch.; Crammer, B.; Dasnias, J.; Decroix, G.; Defoy, B.; Delafontaine, E.; Delcroix, V.; Delerue, X.; Demet, M.; Dimmers, G.; Dodivers, S.; Dubigeon, O.; Eimer, M.; Fadin, H.; Foos, J.; Ganiage, D.; Garraud, J.; Girod, J.P.; Gourod, A.; Goussot, D.; Guignard, C.; Heloury, J.; Hondermarck, B.; Hurel, S.; Jeandron, C.; Josse, A.; Lagon, Ch.; Lalleron, Ch.; Laurent, M.; Legrand, H.; Leveau, E.

    2006-01-01

    On September 15. and 16., 2004, at Rene Delcourt invitation, President of the C.L.I. of Paluel and Penly, took place the 4. colloquium of the A.N.C.L.I.. Jean Dasnias, new President of the C.L.I., welcomed the colloquium. Hundred of persons participated. The place of the nuclear power in the energy perspectives of tomorrow, its assets and its weaknesses in front of the other energies and within the framework of a sustainable development, are so many subjects which were discussed. The different tackled subjects are: the stakes in the sustainable development; energy perspectives; the reactors of the fourth generation; nuclear power and transparency; sustainable development and I.R.S.N. (N.C.)

  5. Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E 1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses: 1.1.1 the data quality objective for characterization as an initial step in decommissioning planning. 1.1.2 sampling methods, 1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and 1.1.4 essential documentation of the characterization information. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate saf...

  6. Nuclear applications for development

    International Nuclear Information System (INIS)

    2007-01-01

    Building capacity for the safe application of nuclear technologies produces tangible socioeconomic benefits to developing countries. Identifying killer infections such as extrapulmonary tuberculosis and drug resistant strains of HIV/AIDS in sub-Saharan Africa; Monitoring malaria drug resistance in Myanmar; - Teaching Jordanian farmers how to produce viable crops on salty soils; - Investigating water resources deep beneath the Nubian Desert; - Fighting acid rain in Poland; - Creating an energy strategy for Latin America; - Strengthening the security of nuclear sources in Kazakhstan. These are just some of examples of the practical ways in which the International Atomic Energy Agency (IAEA) fulfils its mandate to 'accelerate and enlarge the contribution of atomic energy to peace, health, and prosperity throughout the world'. And some of the reasons the IAEA's long history of global action was recognized through the Nobel Peace Prize in 2005. This list of activities reflects the diverse needs of Member States. It also demonstrates the enormous potential of nuclear technology and the breadth of expertise that lie within three IAEA technical programmes: Nuclear Sciences and Applications, Nuclear Energy, and Nuclear Safety and Security. More importantly, it speaks to the success of a determined effort to facilitate knowledge sharing and technology transfer through a cross-cutting mechanism known as the technical cooperation programme. Each year, the technical cooperation programme disburses approximately US $90 million, all of which is acquired through voluntary contributions from Member States. The programme concentrates on building capacity through training and education, expert advice, and equipment delivery. It is currently active in more than 110 countries across four geographic regions: Africa, Asia and the Pacific, Europe and Latin America

  7. Development of a standard data base for FBR core nuclear design. 10. Reevaluation of atomic number density of JOYO Mk-II core

    Energy Technology Data Exchange (ETDEWEB)

    Numata, Kazuyuki; Sato, Wakaei [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center; Ishikawa, Makoto; Arii, Yoshio [Nuclear Energy System Incorporation, Tokyo (Japan)

    1999-07-01

    The material composition of JOYO Mk-II core components in its initial core was reevaluated as a part of the effort for developing a standard data base for FBR core nuclear design. The special feature of the reevaluation is to treat the decay of Pu-241 isotope, so that the atomic number densities of Pu-241 and Am-241 in fuel assemblies can be exactly evaluated on the initial critical date, Nov. 22nd, 1982. Further, the atomic number densities of other core components were also evaluated to improve the analytical accuracy. Those include the control rods which were not so strictly evaluated in the past, and the dummy fuels and the neutron sources which were not treated in the analytical model so far. The results of the present reevaluation were as follows: (1) The changes of atomic number densities of the major nuclides such as Pu-239, U-235 and U-238 were about {+-}0.2 to 0.3%. On the other hand, the number density of Pu-241, which was the motivation of the present work, was reduced by 12%. From the fact, the number densities in the past analysis might be based on the isotope measurement of the manufacturing point of time without considering the decay of Pu-241. (2) As the other core components, the number densities of control rods and outer reflector-type A were largely improved. (author)

  8. Nuclear Knowledge Capture and IEC Standards

    International Nuclear Information System (INIS)

    Sheldon, J.

    2016-01-01

    Full text: An International Standard is a document, established by consensus and approved by a recognized body that provides, for common and repeated use, rules, guidelines or characteristics for activities or their results, aimed at the achievement of the optimum degree of order in a given context. As such, it is a mechanism for sharing knowledge in a particular field. The consensus process used to approve the content of standards ensures that the content is essentially peer-reviewed. This presentation will explain how International Standards are developed and used and their importance in the dissemination of scientific and engineering information. It will also explain the role of the IEC in ensuring that the process for developing standards meets the core principles of the Code of Good Practice of the WTO TBT agreement: transparency, openness, impartiality and consensus, effectiveness and relevance, coherence, and addressing the concerns of developing countries. (author

  9. Globalization of ASME Nuclear Codes and Standards

    International Nuclear Information System (INIS)

    Swayne, Rick; Erler, Bryan A.

    2006-01-01

    With the globalization of the nuclear industry, it is clear that the reactor suppliers are based in many countries around the world (such as United States, France, Japan, Canada, South Korea, South Africa) and they will be marketing their reactors to many countries around the world (such as US, China, South Korea, France, Canada, Finland, Taiwan). They will also be fabricating their components in many different countries around the world. With this situation, it is clear that the requirements of ASME Nuclear Codes and Standards need to be adjusted to accommodate the regulations, fabricating processes, and technology of various countries around the world. It is also very important for the American Society of Mechanical Engineers (ASME) to be able to assure that products meeting the applicable ASME Code requirements will provide the same level of safety and quality assurance as those products currently fabricated under the ASME accreditation process. To do this, many countries are in the process of establishing or changing their regulations, and it is important for ASME to interface with the appropriate organizations in those countries, in order to ensure there is effective use of ASME Codes and standards around the world. (authors)

  10. Seismic design standardization of nuclear facilities

    International Nuclear Information System (INIS)

    Reddy, G.R.; Vaze, K.K.

    2011-01-01

    Full text: Structures, Systems and Components (SSCs) of Nuclear Facilities have to be designed for normal operating loads such as dead weight, pressure, temperature etc., and accidental loads such as earthquakes, floods, extreme, wind air craft impact, explosions etc. Man made accidents such as aircraft impact, explosions etc., some times may be considered as design basis event and some times taken care by providing administrative controls. This will not be possible in the case of natural events such as earthquakes, flooding, extreme winds etc. Among natural events earthquakes are considered as most devastating and need to be considered as design basis event. It is generally felt design of SSCs for earthquake loads is very time consuming and expensive. Conventional seismic design approaches demands for large number of supports for systems and components. This results in large space occupation and in turn creates difficulties for maintenance and in service inspection of systems and components. In addition, complete exercise of design need to be repeated for plants being located at different sites due to different seismic demands. However, advanced seismic response control methods will help to standardize the seismic design meeting the safety and economy. These methods adopt passive, semi active and active devices, and base isolators to control the seismic response. In nuclear industry, it is advisable to go for passive devices to control the seismic responses. Ideally speaking, these methods will make the designs made for normal loads can also satisfy the seismic demand without calling for change in material, geometry, layout etc. in the SSCs. This paper explain the basic ideas of seismic response control methods, demonstrate the effectiveness of control methods through case studies and eventually give the procedure to be adopted for seismic design standardization of nuclear facilities

  11. Internationally Standardized Cost Item Definitions for Decommissioning of Nuclear Installations

    International Nuclear Information System (INIS)

    Lucien Teunckens; Kurt Pflugrad; Candace Chan-Sands; Ted Lazo

    2000-01-01

    The European Commission (EC), the International Atomic Energy Agency (IAEA), and the Organization for Economic Cooperation and Development/Nuclear Energy Agency (OECD/NEA) have agreed to jointly prepare and publish a standardized list of cost items and related definitions for decommissioning projects. Such a standardized list would facilitate communication, promote uniformity, and avoid inconsistency or contradiction of results or conclusions of cost evaluations for decommissioning projects carried out for specific purposes by different groups. Additionally, a standardized structure would also be a useful tool for more effective cost management. This paper describes actual work and result thus far

  12. Domestic and International Nuclear Energy Voluntary Consensus Standards Needs

    International Nuclear Information System (INIS)

    Hopper, Calvin Mitchell

    2013-01-01

    This report introduces the reader to the domestic and international standards development organizations (SDOs) and their structures and operations. It also identifies some of the support and subject matter needs for the development of standards on the subject of nuclear energy. The support needs are described with regard to organizational structure and subject-matter-expert (SME) participation that is required for producing voluntary consensus standards. The subject matter needs are described with regard to growing technologies and objectives that approach the boundaries of existing standards; implementation of knowledge; and safety of people, facilities, and the environment. Standards are proposed, developed, and produced by SMEs with the support of industry and government organizations. The voluntary consensus standards development process is, as its name implies, a voluntary effort. The problem in today's competitive market, impacted by global economic uncertainty, is that the voluntary participation is shifting from a collaborative industry and SME effort to a nearly SME-only one. This shift places a financial and/or time burden on the SMEs to the point that they are purposely withdrawing from the standards development process, both domestically and internationally. The standards development process desperately needs participation from more and younger SMEs. The report includes several suggestions on how this can be addressed.

  13. Infrastructure development through civil nuclear cooperation

    International Nuclear Information System (INIS)

    Humphrey, A.M.; Burkart, A.R.

    2010-01-01

    Due to growing concerns over electricity demand, energy security, and climate change, numerous countries are considering the construction of new nuclear power plants. Most of these will be built in nations with existing nuclear power programs, but an increasing number of States have expressed serious interest in developing new nuclear power programs. These countries will be faced with many challenges in establishing the robust infrastructures necessary for the safe, secure, and safeguarded deployment of nuclear power. Fortunately, there is much a State can gain through cooperation with other States with more developed programs. By sharing information on previous experience and established best practices, an emerging nuclear energy State can benefit from the lessons learned by its partners. Through a broad range of civil nuclear cooperation, the United States is helping new entrants develop the sound infrastructure necessary to deploy nuclear power plants with the highest standards of safety, security, and nonproliferation

  14. International standardization of nuclear reactor designs - the way forward

    International Nuclear Information System (INIS)

    Raetzke, Christian

    2010-01-01

    The concept of 'International Standardization of Nuclear Reactor Designs' means that vendors could build their designs in every country without having to adapt it specifically to national safety requirements. Such standardization would have two main effects. It would greatly facilitate nuclear new build worldwide by giving greater efficiency and certainty to the national licensing procedures; by taking into account the fact that vendors, and nowadays also utilities, are active across borders; by helping developing countries to establish their nuclear new build programmes; and by reducing the strain on human resources on both the regulators' and the industry's side. The second valuable effect of standardization would be to further enhance safety by improving the exchange of construction and operating experience among a number of reactors belonging to fleets of the same design. The World Nuclear Association's CORDEL (Cooperation in Reactor Design Evaluation and Licensing) Group has developed a concept for implementation of international standardization of reactor designs. It has defined a number of steps to be taken by industry. At the same time, possibilities offered by national and international regulatory mechanisms would have to be fully made use of, and some changes in regulatory frameworks might be necessary. Some steps especially towards greater cooperation of regulators have already been taken; however, much still remains to be done. The concept of deploying standardized reactor designs across a number of countries supposes an alignment and, if possible, harmonization of national safety standards; a streamlining of national licensing procedures, making them more efficient and predictable; and the willingness of national regulators to take into account licensing done in other countries. In the end, this should lead to a mutual acceptance of design approvals or, in a more distant future, even to a multinational design approval process. All in all, the concept

  15. Nuclear dilemma: power, proliferation, and development

    International Nuclear Information System (INIS)

    Miller, M.

    1979-01-01

    Debate over President Carter's nuclear energy policy centers on how to develop nuclear power for civilian use and prevent the proliferation of nuclear materials for weapons. Both supporters and opponents of nuclear energy have been critical of Carter's policies because each side fails to see the linkage between the two concerns as codified in the 1978 Non-Proliferation Act. The author uses a dialogue format to illustrate the arguments for resisting proliferation and recognizing nuclear energy as an appropriate technology. The consequences of a nuclear moratorium are explored along with implications for foreign policy. U.S. leadership in developing energy technologies that can meet a broad range of appropriate applications, combined with leadership in building appropriate political frameworks, is needed if nuclear energy is to make a positive contribution toward world peace and acceptable living standards. 8 references

  16. Standardized analyses of nuclear shipping containers

    International Nuclear Information System (INIS)

    Parks, C.V.; Hermann, O.W.; Petrie, L.M.; Hoffman, T.J.; Tang, J.S.; Landers, N.F.; Turner, W.D.

    1983-01-01

    This paper describes improved capabilities for analyses of nuclear fuel shipping containers within SCALE -- a modular code system for Standardized Computer Analyses for Licensing Evaluation. Criticality analysis improvements include the new KENO V, a code which contains an enhanced geometry package and a new control module which uses KENO V and allows a criticality search on optimum pitch (maximum k-effective) to be performed. The SAS2 sequence is a new shielding analysis module which couples fuel burnup, source term generation, and radial cask shielding. The SAS5 shielding sequence allows a multidimensional Monte Carlo analysis of a shipping cask with code generated biasing of the particle histories. The thermal analysis sequence (HTAS1) provides an easy-to-use tool for evaluating a shipping cask response to the accident capability of the SCALE system to provide the cask designer or evaluator with a computational system that provides the automated procedures and easy-to-understand input that leads to standarization

  17. International implications of nuclear Q.A. standards

    International Nuclear Information System (INIS)

    Stoddart, D.E.

    1976-01-01

    The work of the International Atomic Energy Agency (I.A.E.A.) in the field of Quality Assurance is aimed at preparing a Code of Practice covering recommendations on safety aspects only which is designed to be usable by all nations. This Code is followed up by a series of Safety Guides as aids to developing nations faced with the need to regulate and assure safety, reliability and quality. The I.A.E.A. Code is not written as a mandatory document and it can only recommend and therefore the term 'should' is used throughout. The International Organization for Standardization (I.S.O.) is concerned with producing standards and as such the proposed I.S.O. draft standard on 'Quality Assurance for Nuclear Power Plants' is written in mandatory language, it uses the word 'shall'. The I.S.O. standard will also cover not only safety aspects but also those of a successfully operating nuclear power plant. The I.S.O. Working Group is charged with producing standards on quality assurance covering the design, procurement, fabrication, construction, operation, maintenance and decommissioning of structure, systems and components of nuclear power plants. The work of both organizations is discussed briefly. (author)

  18. Development of a standard data base for FBR core nuclear design (XIII). Analysis of small sample reactivity experiments at ZPPR-9

    International Nuclear Information System (INIS)

    Sato, Wakaei; Fukushima, Manabu; Ishikawa, Makoto

    2000-09-01

    A comprehensive study to evaluate and accumulate the abundant results of fast reactor physics is now in progress at O-arai Engineering Center to improve analytical methods and prediction accuracy of nuclear design for large fast breeder cores such as future commercial FBRs. The present report summarizes the analytical results of sample reactivity experiments at ZPPR-9 core, which has not been evaluated by the latest analytical method yet. The intention of the work is to extend and further generalize the standard data base for FBR core nuclear design. The analytical results of the sample reactivity experiments (samples: PU-30, U-6, DU-6, SS-1 and B-1) at ZPPR-9 core in JUPITER series, with the latest nuclear data library JENDL-3.2 and the analytical method which was established by the JUPITER analysis, can be concluded as follows: The region-averaged final C/E values generally agreed with unity within 5% differences at the inner core region. However, the C/E values of every sample showed the radial space-dependency increasing from center to core edge, especially the discrepancy of B-1 was the largest by 10%. Next, the influence of the present analytical results for the ZPPR-9 sample reactivity to the cross-section adjustment was evaluated. The reference case was a unified cross-section set ADJ98 based on the recent JUPITER analysis. As a conclusion, the present analytical results have sufficient physical consistency with other JUPITER data, and possess qualification as a part of the standard data base for FBR nuclear design. (author)

  19. Development of fusion safety standards

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Petti, D.A.; Dinneen, G.A.; Herring, J.S.; DeLooper, J.; Levine, J.D.; Gouge, M.J.

    1996-01-01

    Two new U.S. Department of Energy (DOE) standards have been prepared to assist in the design and regulation of magnetic fusion facilities. They are DOE-STD-6002-96, 'Safety of Magnetic Fusion Facilities - Requirements,' and DOE-STD-6003-96 'Safety of Magnetic Fusion Facilities - Guidance.' The first standard sets forth requirements, mostly based on the Code of Federal Regulations, deemed necessary for the safe design and operation of fusion facilities and a set of safety principles to use in the design. The second standard provides guidance on how to meet the requirements identified in DOE-STD-6002-96. It is written specifically for a facility such as the International Thermonuclear Experimental Reactor (ITER) in the DOE regulatory environment. As technical standards, they are applicable only to the extent that compliance with these standards is included in the contracts of the developers. 7 refs., 1 fig

  20. Harmonization of nuclear codes and standards, pacific nuclear council working and task group report

    International Nuclear Information System (INIS)

    Dua, S.S.

    2006-01-01

    Full text: The codes and standards, both at the national and international level, have had a major impact on the industry worldwide and served it well in maintaining the performance and safety of the nuclear reactors and facilities. The codes and standards, in general, are consensus documents and do seek public input at various levels before they are finalized and rolled out for use by the nuclear vendors, consultants, utilities and regulatory bodies. However, the extensive development of prescriptive national standards if unchecked against the global environment and trade agreements (NAFTA, WTO, etc.) can also become barriers and cause difficulties to compete in the world market. During the last decade, the national and international writing standards writing bodies have recognized these issues and are moving more towards the rationalization and harmonization of their standards with the more widely accepted generic standards. The Pacific Nuclear Council (PNC) recognized the need for harmonization of the nuclear codes and standards for its member countries and formed a Task Group to achieve its objectives. The Task Group has a number of members from the PNC member countries. In 2005 PNC further raised the importance of this activity and formed a Working Group to cover a broader scope. The Working Group (WG) mandate is to identify and analyze the different codes and standards introduced to the Pacific Basin region, in order to achieve mutual understanding, harmonization and application in each country. This o requires the WG to develop and encourage the use of reasonably consistent criteria for the design and development, engineering, procurement, fabrication, construction, testing, operations, maintenance, waste management, decommissioning and the management of the commercial nuclear power plants in the Pacific Basin so as to: Promote consistent safety, quality, environmental and management standards for nuclear energy and other peaceful applications of nuclear

  1. Development of nuclear energy and nuclear policy in China

    International Nuclear Information System (INIS)

    You Deliang

    1993-11-01

    Status of nuclear power development in China, nuclear policy and nuclear power programme are described. Issues regarding nuclear fuel cycle system, radioactive waste management and international cooperation in the field of peaceful use of nuclear energy are discussed

  2. Accredited Standards Committee N15 Developments And Future Directions

    International Nuclear Information System (INIS)

    Mathews, Caroline E.; May, Melanie; Preston, Lynne

    2009-01-01

    Accredited Standards Committee (ASC) N15, Methods of Nuclear Material Control, is sponsored by the Institute of Nuclear Materials Management (INMM) to develop standards for protection, control and accounting of special nuclear materials in all phases of the nuclear fuel cycle, including analytical procedures where necessary and special to this purpose, except that physical protection of special nuclear material within a nuclear power plant is not included. Voluntary consensus standards complement federal regulations and technical standards and fulfill an important role for the nuclear regulatory agencies. This paper describes the N15 standards development process, with INMM as the Standards Developing Organization (SDO) and the N15 Committee responsible for implementation. Key components of the N15 standards development process include ANSI accreditation; compliance with the ANSI Essential Requirements (ER), coordination with other SDOs, communication with stakeholders, maintenance of balance between interest categories, and ANSI periodic audits. Recent and future ASC N15 activities are discussed, with a particular focus on new directions in anticipation of renewed growth in nuclear power.

  3. Development of high burnup nuclear fuel technology

    International Nuclear Information System (INIS)

    Suk, Ho Chun; Kang, Young Hwan; Jung, Jin Gone; Hwang, Won; Park, Zoo Hwan; Ryu, Woo Seog; Kim, Bong Goo; Kim, Il Gone

    1987-04-01

    The objectives of the project are mainly to develope both design and manufacturing technologies for 600 MWe-CANDU-PHWR-type high burnup nuclear fuel, and secondly to build up the foundation of PWR high burnup nuclear fuel technology on the basis of KAERI technology localized upon the standard 600 MWe-CANDU- PHWR nuclear fuel. So, as in the first stage, the goal of the program in the last one year was set up mainly to establish the concept of the nuclear fuel pellet design and manufacturing. The economic incentives for high burnup nuclear fuel technology development are improvement of fuel utilization, backend costs plant operation, etc. Forming the most important incentives of fuel cycle costs reduction and improvement of power operation, etc., the development of high burnup nuclear fuel technology and also the research on the incore fuel management and safety and technologies are necessary in this country

  4. Developments in safety standards and regulation

    International Nuclear Information System (INIS)

    Harbison, S.A.

    1994-01-01

    This paper explains, in broad terms, how regulatory control is exercised over licensed nuclear installations in the UK and how HSE has developed its safety standards to support its regulatory approach. It first sets out the scope of HSE's regulatory responsibilities, which NII exercises on its behalf, and briefly describes the licensing process and compliance monitoring through inspection over the life of a nuclear plant. It also refers to the role of assessment in NII's decision-making processes, and the part played in this by the consideration of costs and safety benefits. It then moves on to consider the challenges that HSE/NII are likely to face from the changing nuclear industry in the second half of the 1990s. (author)

  5. Revision of the ASME nuclear quality assurance standard and its historical background

    International Nuclear Information System (INIS)

    Suzuki, Tetsuya

    2009-01-01

    ASME NQA-1-2008 'Quality Assurance Requirements for Nuclear Facility Applications' will be endorsed by US NRC by the end of 2009. This standard will apply to design, construction and operation of nuclear power plants newly erected in USA. It is important to Japanese vendors developing nuclear business in USA. Historical background, significance of revision and main revised points of the ASME nuclear quality assurance standard are described in the present paper. (T. Tanaka)

  6. Applying consensus standards to cask development

    International Nuclear Information System (INIS)

    Leatham, J.; Abbott, D.G.; Warrant, M.M.

    1987-01-01

    The Department of Energy's (DOE's) Office of Civilian Radioactive Waste Management is procuring cask systems for transporting commercial spent nuclear fuel and is encouraging development of innovative cask designs and materials to improve system efficiency. New designs and innovative materials require that consensus standards be established so that cask designers and regulators have criteria for determining acceptability. Recent DOE experience in certifying three spent fuel shipping casks, NUPAC-125B, TN-BRP, and TN-REG, is discussed. Certification of the NUPAC-125B was expedited because it was made of conventional American Society for Testing and Materials (ASTM) materials and complied with the American Society of Mechanical Engineers (ASME) Code and Nuclear Regulatory Commission Regulatory Guides. The TN-BRP and TN-REG cask designs are still being reviewed because baskets included in the casks are made of borated stainless steel, which has no ASTM Specification or ASME Code approval. The process of developing and approving consensus standards is discussed, including the role of ANSI and ANSI N14. Specific procedures for ASTM and ASME are described. A draft specification or standard must be prepared and then approved by the appropriate body. For new material applications to the ASME Code, an existing ASTM Specification is needed. These processes may require several years. The status of activities currently in progress to develop consensus standards for spent fuel casks is discussed, including (1) ASME NUPAC, and (2) ASTM Specifications for ductile cast iron and borated stainless steel

  7. Nuclear knowledge development in Armenia

    International Nuclear Information System (INIS)

    Gevorgyan, A.A.

    2004-01-01

    Armenia has rather rich history of nuclear knowledge development. During the last several decades, depending on circumstances related with the ANPP main mile stones - construction, putting into operation, shutdown, restarting - nuclear knowledge was having its ups and downs. Though it has high level of development, there has been yet a need of preservation accumulated nuclear knowledge, and appropriate proceeding with the nuclear knowledge in Armenia. (author)

  8. Regulatory practices and safety standards for nuclear power plants

    International Nuclear Information System (INIS)

    1989-01-01

    The International Symposium on Regulatory Practices and Safety Standards for Nuclear Power Plants was jointly organized by the International Atomic Energy Agency (IAEA), for Nuclear Energy Agency of the OECD and the Government of the Federal Republic of Germany with the objective of providing an international forum for the exchange of information on regulatory practices and safety standards for nuclear power plants. The Symposium was held in Munich, Federal Republic of Germany, from 7 to 10 November 1988. It was attended by 201 experts from some 32 Member States and 4 international organizations. Fifty-one papers from 19 Member States and 2 international organizations were presented and discussed in 5 technical sessions covering the following subjects: National Regulatory Practices and Safety Standards (14 papers); Implementation of Regulatory Practices - Technical Issues (8 papers); Implementation of Regulatory Practices - Operational Aspects (8 papers); Developments and Trends in Safety Standards and Practices (11 papers); International Aspects (10 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

  9. Nuclear valves latest development

    International Nuclear Information System (INIS)

    Isaac, F.; Monier, M.

    1993-01-01

    In the frame of Nuclear Power Plant upgrade (Emergency Power Supply and Emergency Core Cooling), Westinghouse had to face a new valve design philosophy specially for motor operated valves. The valves have to been designed to resist any operating conditions, postulated accident or loss of control. The requirements for motor operated valves are listed and the selected model and related upgrading explained. As part of plant upgrade and valves replacement, Westinghouse has sponsored alternative hardfacing research programme. Two types of materials have been investigated: nickel base alloys and iron base alloys. Programme requirements and test results are given. A new globe valve model (On-Off or regulating) is described developed by Alsthom Velan permitting the seat replacement in less than 10 min. (Z.S.) 2 figs

  10. Development of nuclear analytical technology

    International Nuclear Information System (INIS)

    Jee, Kwang Yong; Kim, W. H.; Park, Yeong J.; Park, Yong J.; Sohn, S. C.; Song, B. C.; Jeon, Y. S.; Pyo, H. Y.; Ha, Y. K.

    2004-04-01

    The objectives of this study are to develop the technology for the determination of isotopic ratios of nuclear particles detected from swipe samples and to develop the NIPS system. The R and D contents and results of this study are firstly the production of nuclear micro particle(1 ∼ 20 μm) and standardization, the examination of variation in fission track characteristic according to nuclear particle size and enrichment( 235 U: 1-50%), the construction of database and the application of this technique to swipe samples. If this technique is verified its superiority by various field tests and inter-laboratory comparison program with other institutes in developed countries, it can be possible to join NWAL supervised under IAEA and to export our technology abroad. Secondly, characteristics of alpha track by boron (n, α) nuclear reaction were studied to measure both total boron concentration and 10B enrichment. The correlation of number of alpha tracks and various 10B concentration was studied to evaluate the reliability of this method. Especially, cadmium shielding technique was introduced to reduce the background of alpha tracks by covering the solid track detector and the multi-dot detector plate was developed to increase the reproducibility of measurement by making boron solution dried evenly in the plate. The results of the alpha track method were found to be well agreed with those of mass spectroscopy within less than 10 % deviation. Finally, the NIPS system using 252 Cf neutron source was developed and prompt gamma spectrum and its background were obtained. Monte Carlo method using MCNP-4B code was utilized for the interpretation of neutron and gamma-ray shielding condition as well as the moderation of a fast neutron. Gamma-gamma coincidence was introduced to reduce the prompt gamma background. The counting efficiency of the HPGe detector was calibrated in the energy range from 50 keV to 10 MeV using radio isotope standards and prompt gamma rays of Cl for the

  11. Harmonization of nuclear codes and standards. Pacific nuclear council working and task group report

    International Nuclear Information System (INIS)

    Dua, Shami

    2008-01-01

    Nuclear codes and standards have been an integral part of the nuclear industry since its inception. As the industry came into the main stream over the 2nd half of the 20th century, a number of national and international standards were developed to support a specific nuclear reactor concept. These codes and standards have been a key component of the industry to maintain its focus on nuclear safety, reliability and quality. Both national and international standards have served the industry well in obtaining public, shareholder and regulatory acceptance. The existing suite of national and international standards is required to support the emerging nuclear renaissance. However as noted above under Pacific Nuclear Council (PNC), Manufacturing Design Evaluation Program (MDEP) and SMiRT discussions, the time has come now for the codes and standards writing bodies and the industry to take the next step to examine the relevance of existing suite in view of current needs and challenges. This review must account for the changing global environment including global supply chain and regulatory framework, resources, deregulation, free trade, and industry need for competitiveness and performance excellence. The Task Group (TG) has made limited progress in this review period as no additional information on the listing of codes and standards have been received from the members. However, TG Chair has been successful in obtaining considerable interest from some additional individuals from the member countries. It is important that PNC management seek additional participation from the member countries and asks for their active engagement in the Working Group (WG) TG activities to achieve its mandate and deliverables. The harmonization of codes and standards is a key area for the emerging nuclear renaissance and as noted by a number of international organizations (refer to MDEP action noted above) that these tasks can not be completed unless we have the right level of resources and

  12. Complete analysis of a nuclear building to nuclear safety standards

    Energy Technology Data Exchange (ETDEWEB)

    Jaeger, T A

    1975-01-01

    The nuclear standards impose on the designer the necessity of examining the loads, stresses, and strains in a nuclear building even under extreme loading conditions, both due to plant malfunctions and environmental accidents. It is necessary then to generate, combine, and examine a tremendous amount of data; really the lack of symmetry and general complication of the structures and the large number of loading combinations make an automatic analysis quite necessary. A largely automated procedure is presented in view of solving the problem by a series of computer programs linked together. After the seismic analysis has been performed by (SADE CODE) these data together with the data coming from thermal specifications, weight, accident descriptions etc. are fed into a finite element computer code (SAP4) for analysis. They are processed and combined by a computer code (COMBIN) according to the loading conditions (the usual list in Italy is given and briefly discussed), so that for each point (or each selected zone) under each loading condition the applied loads are listed. These data are fed to another computer code (DTP), which determines the amount of reinforcing bars necessary to accommodate the most severe of the loading conditions. The Aci 318/71 and Italian regulation procedures are followed; the characteristics of the program are briefly described and discussed. Some particular problems are discussed, e.g. the thermal stresses due to normal and accident conditions, the inelastic behavior of some frame elements (due to concrete cracking) is considered by means of an 'ad hoc' code. Typical examples are presented and the results are discussed showing a relatively large benefit in considering this inelastic effect.

  13. Problems of nuclear power development

    International Nuclear Information System (INIS)

    Panasenkov, A.

    1982-01-01

    The answers are reported given by the head of the department for peaceful uses of nuclear energy of the secretariat of the Council of Mutual Economic Assistance, Mr. A. Pasenkov to questions given him in an interview for APN. The questions were related to the current state and development of world nuclear power, nuclear safety and the attitude of the general public to nuclear power in the West and in the CMEA countries. (B.S.)

  14. Nuclear regulatory developments in Canada

    International Nuclear Information System (INIS)

    Binder, M.

    2012-01-01

    This paper from CNSC discusses nuclear regulatory developments in Canada. It starts with the Fukushima accident and the effect on the nuclear sector. It summarises what CNSC has done, what it has learned and their plans going forward. It has made recommendations to IAEA for international enhancements to regulatory procedures. It outline the activities of Canada's nuclear power plants, Canada's uranium projects, deep geological repository and waste management as well as nuclear research in Canada.

  15. Developments in nuclear medicine

    International Nuclear Information System (INIS)

    Elias, H.

    1977-01-01

    The article reports on the first international meeting about radiopharmaceutical chemistry in the Brookhaven National Laboratory, Long Island/USA, from 21st to 24th September, 1976. The meeting report is preceded by the explanation of the terms 'radiopharmaceutical chemistry' and 'nuclear medicine' and a brief survey of the history. The interdisciplinary connection of the spheres of nuclear physics, nuclear chemistry, biochemistry, nuclear medicine, and data processing is also briefly shown. This is necessary before radiodiagnosis can be made for a patient. (RB) [de

  16. Towards sustainable nuclear power development

    International Nuclear Information System (INIS)

    Andrianov, Andrei A.; Murogov, Victor M.; Kuptsov, Ilya S.

    2014-01-01

    The review of the current situation in the nuclear energy sector carried out in this article brings to light key problems and contradictions, development trends and prospects, which finally determine the role and significance of nuclear power as a factor ensuring a sustainable energy development. Authors perspectives on the most appropriate developments of nuclear power, which should be based on a balanced use of proven innovative nuclear technologies and comprehensive multilateral approaches to the nuclear fuel cycle are expressed. The problems of wording appropriate and essential requirements for new countries with respect to their preparedness to develop nuclear programs, taking into account their development level of industry and infrastructure as well as national heritages and peculiarities, are explained. It is also indicated that one of the major components of sustainability in the development of nuclear power, which legitimates its public image as a power technology, is the necessity of developing and promoting the concepts of nuclear culture, nuclear education, and professional nuclear ethics. (orig.)

  17. Towards sustainable nuclear power development

    Energy Technology Data Exchange (ETDEWEB)

    Andrianov, Andrei A.; Murogov, Victor M.; Kuptsov, Ilya S. [Obninsk Institute for Nuclear Power Engineering of NNRU MEPhl, Obninsk, Kaluga Region (Russian Federation)

    2014-05-15

    The review of the current situation in the nuclear energy sector carried out in this article brings to light key problems and contradictions, development trends and prospects, which finally determine the role and significance of nuclear power as a factor ensuring a sustainable energy development. Authors perspectives on the most appropriate developments of nuclear power, which should be based on a balanced use of proven innovative nuclear technologies and comprehensive multilateral approaches to the nuclear fuel cycle are expressed. The problems of wording appropriate and essential requirements for new countries with respect to their preparedness to develop nuclear programs, taking into account their development level of industry and infrastructure as well as national heritages and peculiarities, are explained. It is also indicated that one of the major components of sustainability in the development of nuclear power, which legitimates its public image as a power technology, is the necessity of developing and promoting the concepts of nuclear culture, nuclear education, and professional nuclear ethics. (orig.)

  18. Nuclear energy for developing countries

    International Nuclear Information System (INIS)

    Kemery, L.S.

    1980-01-01

    This paper examines the circumstances which must prevail before a reasonable technical, administrative and sociological case can be made to justify the introduction of nuclear power technology to a developing country. The role played by the IAEA in responding to needs of developing countries is considered and problems of nuclear plant safety and materials safeguards discussed. Plans for nuclear power in several developing countries are outlined

  19. Nuclear developments in Europe

    International Nuclear Information System (INIS)

    Taillebois, C.

    2011-01-01

    The main topics of the presentation: FORATOM’s Mission and vision, Nuclear overview in Europe before and after Fukushima; post-Fukushima political decisions; European Council conclusions; European nuclear industry’s response; EU “Stress Tests” specifications; What will the consequences of Fukushima be?

  20. Safety standards and safety record of nuclear power plants

    International Nuclear Information System (INIS)

    Davis, A.B.

    1984-01-01

    This paper focuses on the use of standards and the measurement and enforcement of these standards to achieve safe operation of nuclear power plants. Since a discussion of the safety standards that the Nuclear Regulatory Commission (NRC) uses to regulate the nuclear power industry can be a rather tedious subject, this discussion will provide you with not only a description of what safety standards are, but some examples of their application, and various indicators that provide an overall perspective on safety. These remarks are confined to the safety standards adopted by the NRC. There are other agencies such as the Environmental Protection Agency, the Occupational Safety and Health Administration, and the state regulatory agencies which impact on a nuclear power plant. The NRC has regulatory authority for the commercial use of the nuclear materials and facilities which are defined in the Atomic Energy Act of 1954 to assure that the public health and safety and national security are protected

  1. Manpower development for nuclear power

    International Nuclear Information System (INIS)

    1980-01-01

    This Guidebook provides policy-makers and managers of nuclear power programmes with information and guidance on the role, requirements, planning and implementation of manpower development programmes. It presents and discusses the manpower requirements associated with the activities of a nuclear power programme, the technical qualifications of this manpower and the manpower development corresponding to these requirements and qualifications. The Guidebook also discusses the purpose and conditions of national participation in the activities of a nuclear power programme

  2. Nuclear new developments in Europe

    International Nuclear Information System (INIS)

    Lucaciu, G.; Chirica, T.

    2012-01-01

    Conclusions: The European nuclear industry has supported a common EU-level approach to analyzing the consequences of the Fukushima accident and to developing a common framework for reassessing the safety of its nuclear power plants; FORATOM assertion is that nuclear power should feature prominently in the EC Energy Roadmap 2050 later this year; Long-term benefits of nuclear for EU energy supply remain valid: security of supply, competitiveness and low-carbon; Innovative financial instruments are requested for large projects finance; Fukushima will complicate the financing and insurance frames, and possibly affect the overall cost of the nuclear projects; Fair treatment of all production technologies is required

  3. Economic development and nuclear geography

    International Nuclear Information System (INIS)

    Giraud, Andre.

    1976-01-01

    In a study previously presented at the European Nuclear Conference on the Maturity of Nuclear Energy (Paris-1975), an overall balance of the world energy needs had been drawn and the part played by nuclear energy had been underlined. A model is presented here, which, on the basis of the present situation in each country (i.e. its population, level of development, and level of power consumption), of selected outlines of foreseeable growth, and the possible mechanics of introduction and penetration of nuclear power, offers the possibility of simulating the evolution of nuclear capacity in that country [fr

  4. Developing standardized facility contingency plans

    International Nuclear Information System (INIS)

    Davidson, D.A.

    1993-01-01

    Texaco consists of several operating departments that are, in effect, independent companies. Each of these departments is responsible for complying with all environmental laws and regulations. This includes the preparation by each facility to respond to an oil spill at that location. For larger spills, however, management of the response will rest with corporate regional response teams. Personnel from all departments make up the regional teams. In 1990, Congress passed the Oil Pollution Act. In 1991, the US Coast Guard began developing oil spill response contingency plan regulations, which they are still working on. Meanwhile, four of the five west coast states have also passed laws requiring contingency plans. (Only Hawaii has chosen to wait and see what the federal regulations will entail). Three of the states have already adopted regulations. Given these laws and regulations, along with its corporate structure, Texaco addressed the need to standardize local facility plans as well as its response organization. This paper discusses how, by working together, the Texaco corporate international oil spill response staff and the Texaco western region on-scene commander developed: A standard contingency plan format crossing corporate boundaries and meeting federal and state requirements. A response organization applicable to any size facility or spill. A strategy to sell the standard contingency plan and response organization to the operating units

  5. Software Development Standard Processes (SDSP)

    Science.gov (United States)

    Lavin, Milton L.; Wang, James J.; Morillo, Ronald; Mayer, John T.; Jamshidian, Barzia; Shimizu, Kenneth J.; Wilkinson, Belinda M.; Hihn, Jairus M.; Borgen, Rosana B.; Meyer, Kenneth N.; hide

    2011-01-01

    A JPL-created set of standard processes is to be used throughout the lifecycle of software development. These SDSPs cover a range of activities, from management and engineering activities, to assurance and support activities. These processes must be applied to software tasks per a prescribed set of procedures. JPL s Software Quality Improvement Project is currently working at the behest of the JPL Software Process Owner to ensure that all applicable software tasks follow these procedures. The SDSPs are captured as a set of 22 standards in JPL s software process domain. They were developed in-house at JPL by a number of Subject Matter Experts (SMEs) residing primarily within the Engineering and Science Directorate, but also from the Business Operations Directorate and Safety and Mission Success Directorate. These practices include not only currently performed best practices, but also JPL-desired future practices in key thrust areas like software architecting and software reuse analysis. Additionally, these SDSPs conform to many standards and requirements to which JPL projects are beholden.

  6. Nuclear powerplant standardization: light water reactors. Volume 2. Appendixes

    International Nuclear Information System (INIS)

    1981-06-01

    This volume contains working papers written for OTA to assist in preparation of the report, NUCLEAR POWERPLANT STANDARDIZATION: LIGHT WATER REACTORS. Included in the appendixes are the following: the current state of standardization, an application of the principles of the Naval Reactors Program to commercial reactors; the NRC and standardization, impacts of nuclear powerplant standardization on public health and safety, descriptions of current control room designs and Duke Power's letter, Admiral Rickover's testimony, a history of standardization in the NRC, and details on the impact of standardization on public health and safety

  7. JPRS Report, Nuclear Developments.

    Science.gov (United States)

    1989-09-18

    the 33rd Regular Session of the MAGATE General Conference. HUNGARY Results of Leakage Tests at Power Plant 25020265a Budapest ENERGIA ES...Empresas Nucleares Brasileiras S.A. (Nuclebras) to Industrias Nucleares do Brasil S.A. (INB), and trans- ferred the shares of its capital stock...96.622 authorizes the establishment of Uranium of Brasil S.A. as a subsidiary of INB, with headquarters in the city of Caldas, Minas Gerais State

  8. Nuclear trade between developing countries

    International Nuclear Information System (INIS)

    Stahl, K.

    1990-01-01

    The analysis of nuclear south-south cooperation is based on the evaluation of official documents (the texts of laws, of contracts for nuclear cooperation treaties, safeguard treaties, official government policy speeches etc.). These data were supplemented by numerous interviews with representatives of atomic energy authorities, foreign ministries, nuclear industries, members of parliament, representatives of the nuclear energy opposition movement and military representatives in the three states and by interviews with representatives of the IAEO and OPANAL in Mexico. The study deals with each country in turn: Chapter 2 gives an overview of the Indian nuclear energy programme and India's nuclear export activity and export policy. Chapter 3 analyzes Brazil's nuclear energy policy and Brazilian export capacities, exports and export policy in the nuclear sector. Chapter 4 looks at the development of the Argentinian nuclear energy programme and the crisis in it, at Argentina's nuclear export activities and its export policy and technology transfer policy in this field. Chapter 5 analyzes separately relations between Argentina and Brazil on nuclear cooperation, since they differ considerably from the two countries' relations with other Third World countries on this topic. The appendix documents the most important contractual agreements and government policy declarations on nuclear cooperation between the two states. (orig.) [de

  9. Nuclear technology transfer via standards: the OMB Circular A-119 in action

    International Nuclear Information System (INIS)

    Zapp, F.C.

    1986-01-01

    The Performance Assurance Project Office (PAPO) has 23 nuclear energy (NE) standards in some phase of conversion to the national consensus standards, and identified three new NE standards for possible conversion. The author describes the methods of developing a consensus for standards through the use of working groups and ballots and the process of adopting a standard. Voluntary NE standards categories cover operation, instrumentation and controls, equipment, programs and procedures, materials, electrical, and structures and building. 4 references, 2 tables

  10. National Nuclear Technology Map Development

    International Nuclear Information System (INIS)

    Shin, J. I.; Lee, T. J.; Yoon, S. W.

    2005-03-01

    The objective of NuTRM is to prepare a plan of nuclear R and D and technological innovations which is very likely to make nuclear technology a promising power source for future national developments. The NuTRM finds out systematically the nuclear R and D vision and the high-value-added strategic technologies to be developed by the efficient cooperation of actors including government, industry, academy and research institute by 2020. In other words, NuTRM aims at a long-term strategic planning of nuclear R and D and technological innovation in order to promote the socio-economic contributions of nuclear science and technology for the nation's future competitiveness and sustainable development and to raise the global status of the Korean nuclear R and D and Industry

  11. Nuclear power in developing countries

    International Nuclear Information System (INIS)

    Morrison, R.W.

    1980-01-01

    A few of the essential issues which arise when we consider nuclear power and development together in the context of energy policy are discussed. Ethical concerns must ultimately be expressed through policies and their impact on people. There are ethical issues associated with nuclear power in the developing countries which deserve our attention. Four aspects of the question of nuclear power in developing countries are considered: their energy situation; the characteristics of nuclear power which are relevant to them; whether developing countries will undertake nuclear power programmes; and finally the ethical implications of such programmes. It is concluded that what happens in developing countries will depend more on the ethical nature of major political decisions and actions than on the particular technology they use to generate their electricity. (LL)

  12. Sustainable development and nuclear liability

    International Nuclear Information System (INIS)

    Schwartz, J.

    2001-01-01

    Although the high safety standards of the nuclear industry mean that the risk of an accident is low, the magnitude of damage that could result to third parties from such an accident is considerable. It was thus recognised from the very inception of the nuclear power industry that a special legal regime would need to be established to provide for the compensation of victims of a nuclear accident. The ordinary rules of tort and contract law were simply not suited to addressing such a situation in an efficient and effective manner. (authors)

  13. The latest trend of nuclear standards

    International Nuclear Information System (INIS)

    Tobioka, Toshiaki

    2000-01-01

    In Japan, the Atomic Energy Fundamental Law is enacted as a fundamental law on application of atomic energy. According to provision of the Law, various regulations essential to prevent national disaster, to protect nuclear substances and to secure public safety are carried out. From a viewpoint of disaster prevention, 'the Law on Regulation of Nuclear Raw Materials, Nuclear Fuel Substances and Nuclear Reactors' is enacted for its main law. On countermeasure to an emergency of accident formation at a nuclear facility, 'the Disaster Countermeasure Fundamental Law' is enacted as a general law for disaster countermeasure and defined obligation, organization, and so on of government, local community, and so on for the disaster containing large scale natural disaster, and recently 'the Nuclear Disaster Special Measure Act' was enacted by receiving necessity of enforced cooperation between government and local community. However, for a general tendency, these regulation rules and now transferring from the conventional system where a means to establish an object in safety is regulated in a meaning to a form required to finish a concrete safe target. (G.K.)

  14. Advanced passive technology: A global standard for nuclear plant requirements

    International Nuclear Information System (INIS)

    Novak, V.

    1994-01-01

    Since 1984, Westinghouse has been developing AP8OO, a 800 MW, two-loop advanced passive plant, in response to an initiative established by the Electric Power Research Institute (EPRI) and the U.S. Department of Energy' (DOE). The preliminary design was cornpleved in 1989. AP6OO's Standard Safety Analysis and Probabilistic Risk analysis Reports were submitted to the U.S. Nuclear Regulatory Commission for design certification in 1992. Design simplification is the key strategy behind the AP6OO. The basic technical concept Of simplification has resulted in a simplified reactor coolant systems, simplified plant systems, a simplified plant arrangement, reduced number of components, simplified operation and maintenance

  15. Knowledge management for assuring high standards in nuclear safety

    International Nuclear Information System (INIS)

    Hahn, L.

    2004-01-01

    The primary incentives for introducing knowledge management in organisations active in the nuclear field are the impending loss of knowledge due to an ageing workforce and the necessity to transfer knowledge to the next generation. However, knowledge management may reach much further, and it is shown that ultimately, the goals of knowledge management are congruent with establishing, maintaining and further developing high standards of safety. Knowledge-based activities to reach these goals are discussed, and examples given for producing, utilising and sharing knowledge in organisations and in national and international networks. (author)

  16. Nuclear Power and Sustainable Development

    International Nuclear Information System (INIS)

    2016-09-01

    Transforming the energy system is at the core of the dedicated sustainable development goal on energy within the new United Nations development agenda. This publication explores the possible contribution of nuclear energy to addressing the issues of sustainable development through a large selection of indicators. It reviews the characteristics of nuclear power in comparison with alternative sources of electricity supply, according to economic, social and environmental pillars of sustainability. The findings summarized in this publication will help the reader to consider, or reconsider, the contribution that can be made by the development and operation of nuclear power plants in contributing to more sustainable energy systems.

  17. Nuclear Data Center International Standard Towards TSO Initiative

    International Nuclear Information System (INIS)

    Raja Murzaferi Raja Moktar; Mohd Fauzi Haris; Siti Nurbahyah Hamdan

    2011-01-01

    Nuclear Data Center is the main facility for Nuclear Malaysia Agency IT infrastructure comprising of main critical servers, research and operational data storage, HPC-clusters system and vital network core equipment. In recent years, international body such as TIA-Telecommunication Industry Association and Up time Institute have came out with proper international data center standards in order to ensure data center operation on achieving maximum operational up time and minimal downtime. The standard are currently being rated as tier level ranging from Data Center tier I up to tier IV, differentiate by facility standard and up time/ downtime percentage ratio. This paper will discuss Nuclear Data Center adopting international standards in supporting Nuclear Malaysia TSO initiative thus ensuring the critical core component of agency IT services availability and further more International standard recognitions. (author)

  18. Nuclear power for developing countries

    International Nuclear Information System (INIS)

    Hirschmann, H.; Vennemann, J.

    1980-01-01

    The paper describes the energy policy quandary of developing countries and explains why nuclear power plants of a suitable size - the KKW 200 MW BWR nuclear power plant for electric power and/or process steam generation is briefly presented here - have an economic advantage over fossil-fuelled power plants. (HP) [de

  19. Nuclear power development in Japan

    International Nuclear Information System (INIS)

    Sugawara, A.

    1994-01-01

    Energy situation in Japan and Japan's strategy for stable supply of energy are discussed. Benefits of nuclear power in comparison with other energy sources is considered. History of nuclear power development in Japan, modern status and future trends are described. 6 figs

  20. The unstoppable world nuclear development

    International Nuclear Information System (INIS)

    Dominguez, M. T.

    2009-01-01

    To meet energy needs and curb climate change, the number of reactors will continue to increase because more and more countries are going the need nuclear power. At present, there are 436 nuclear reactors in the world that produce 16% of the electricity, and another 48 units are under construction in all, 31 countries in the world use nuclear power to produce electricity, and some countries that do not have reactors, e.g. Poland and Italy, are seriously planning to include nuclear power in their energy mix. Global nuclear development is a reality; energy and environmental challenges have led to new support for nuclear power, which is a safe, stable emission-free source. (Author)

  1. Sustainable development and nuclear power

    International Nuclear Information System (INIS)

    Grimston, M.C.

    1994-01-01

    The United Kingdom Government's strategy aimed at securing sustainable development has recently been published, and is analysed here by the Energy Issues Adviser, for the British Nuclear Industry Forum. The energy framework aims to ensure secure supplies of energy at competitive prices and to minimise possible adverse environmental impacts of energy use. It is argued here that both of these aims will be promoted by the continued and growing use of nuclear power in the United Kingdom. As the cost of nuclear electricity depends chiefly on the price of uranium, which is likely to stabilize due to increased supplies from nuclear weapons destruction, uranium recycling and mixed oxide fuel reprocessing, it is unlikely that world fuel price inflation will affect these costs. Secondly, nuclear power is not associated with acid rain or the threat of global warming, so its environment protection claims can be substantiated. Indeed, unlike other fuel sources, nuclear power already pays for its waste and decommissioning procedures. (UK)

  2. Role of radiation standards in peaceful uses of nuclear energy

    International Nuclear Information System (INIS)

    Mahant, A.K.; Sathian, V.; Joseph, L.

    2009-01-01

    Radiation standards play an acute role in all the peaceful applications of nuclear energy, which is not limited to generation of electrical power anymore. Radioactive sources are being used in a very wide variety of applications, which can be broadly classified as medicine, agriculture, industry and scientific research. All these applications involve the use of radiation in a well-controlled manner and hence require accurate characterization and quantification of the radiation. Radiation Standards Section of Radiation Safety Systems Division at BARC is the apex national laboratory for all the radiological quantities related to various types of radiation sources. The laboratory develops, maintains and disseminates the standards to the users of the radiation sources all over the country and some of the neighbouring countries viz. Nepal, Bangladesh, Sri Lanka and Myanmar with an essential objective to bring homogeneity in all radiological measurements and make them compatible with the international standards. Various services provided by the Radiation Standards Section have been briefly described in the following sections. (author)

  3. Nuclear energy and sustainable development

    International Nuclear Information System (INIS)

    Arts, F.; De Ruiter, W.; Turkenburg, W.C.

    1994-01-01

    The purposes of the title workshop were to exchange ideas on the possible impact of nuclear energy on the sustainable development of the society, to outline the marginal conditions that have to be fulfilled by nuclear energy technology to fit in into sustainable development, to asses and determine the differences or agreements of the workshop participants and their argumentations, and to determine the part that the Netherlands could or should play with respect to a further development and application of nuclear energy. 35 Dutch experts in the field of energy and environment attended the workshop which is considered to be a success. It is recommended to organize a follow-up workshop

  4. DOE [Department of Energy]-Nuclear Energy Standards Program annual assessment, FY 1990

    International Nuclear Information System (INIS)

    Williams, D.L. Jr.

    1990-11-01

    To meet the objectives of the programs funded by the Department of Energy (DOE)-Nuclear Energy (NE) Technology Support Programs, the Performance Assurance Project Office (PAPO) administers a nuclear standards program and related activities and fosters the development and application of standards. This standards program is carried out in accordance with the principles in DOE Order 1300.2, Department of Energy Standards Program, December 18, 1980. The purposes of this effort, as set forth in three subtasks, are to (1) manage the NE Standards Program, (2) manage the development and maintenance of NE standards, and (3) operate an NE Standards Information Program. This report assesses the Performance Assurance Project Office (PAPO) activities in terms of the objectives of the Department of Energy-Nuclear Energy (DOE-NE) funded programs. To meet these objectives, PAPO administers a nuclear standards program and related activities and fosters the development and application of standards. This task is carried out in accordance with the principles set forth in DOE Order 1300.2, Department of Energy Standards Program, December 18, 1980, and DOE memorandum, Implementation of DOE Orders on Quality Assurance, Standards, and Unusual Occurrence Reporting for Nuclear Energy Programs, March 3, 1982, and with guidance from the DOE-NE Technology Support Programs. 1 tab. (JF)

  5. Developing nuclear law

    International Nuclear Information System (INIS)

    1968-01-01

    Many aspects of nuclear energy pose special problems for the lawmakers because of the unusual materials and processes involved. Much of it calls for international agreements to protect people, to guard against military exploitation of peaceful work, to promote trade in the new industry, to increase collaboration and to encourage new projects. Mr. Werner Boulanger, Director of the IAEA Legal Division, here indicates the part played by the Agency and other international organizations in securing compatibility of legislation. (author)

  6. JPRS Report, Nuclear Developments

    Science.gov (United States)

    1991-05-31

    French market . 1230 GMT 30 Apr 91 Yang Shangkun Boldly Directs Arms Exporting [Caroline Puelle report from Beijing] On New Year’s Eve, at the same time...it is so industrial material in the international market . determined. [Kang] Given its use of gas-cooled nuclear reactors, [Kang] Even designing...in transferring sensitive technologies and a harder line in the negotia- In remarks to AMBITO FINANCIERO while he was in tions regarding Brazil’s

  7. Nuclear power development in Japan

    International Nuclear Information System (INIS)

    Sugawara, A.

    1994-01-01

    The energy situation in Japan is briefly outlined. Vulnerability in energy structure of the country is shown by a comparison of primary energy supply patterns of Japan and Western countries. Japan's energy policy consists in reducing dependence on oil, promoting efficient use of energy and increasing use of non-fossil fuels. Nuclear power is a core of alternative energy for petroleum because of stable supply of nuclear fuel, low detrimental emissions and less dependence on the fuel. A short historical review of nuclear power development in Japan is presented. Some future issues as development of entire nuclear fuel cycle, social acceptance, reactor safety and nuclear power economics are also discussed. 6 figs. (R.T.)

  8. Toward analytic aids for standard setting in nuclear regulation

    International Nuclear Information System (INIS)

    Brown, R.V.; O'Connor, M.F.; Peterson, C.R.

    1979-05-01

    US NRC promulgates standards for nuclear reprocessing and other facilities to safeguard against the diversion of nuclear material. Two broad tasks have been directed toward establishing performance criteria for standard settings: general-purpose modeling, and analysis specific to a particular performance criterion option. This report emphasizes work on the second task. Purpose is to provide a framework for the evaluation of such options that organizes the necessary components in a way that provides for meaningful assessments with respect to required inputs

  9. Results of nuclear fusion development

    International Nuclear Information System (INIS)

    Yamamoto, Kenzo

    1975-01-01

    Compared with the nuclear fission research which followed that in advanced countries, Japan has treaded on its own track in nuclear fusion development; in the former, she had been far behind other leading countries. Characteristic of the efforts in Japan is the collaboration with educational institutions. Works are now carried out mainly in Tokamak plasma confinement, though other means being studied simultaneously. The nation's fusion research program is the realization of a fusion reactor at the turn of the present century, based on the world-level results attained with Tokamak. Past developments in the nuclear fusion research, the current status, and aspects for the future are discribed. (Mori, K.)

  10. Nuclear power to aid development

    International Nuclear Information System (INIS)

    1969-01-01

    Before nuclear power can play its full role in contributing to the development of less advanced countries, full understanding of the capital investment, fuel costs and other economic factors as well as of the place it must take in existing power programmes is essential. Some insight into the problems and prospects was gained at the symposium arranged by the Agency, and held in Istanbul in October, on 'Nuclear Energy Costs and Economic Development'. (author)

  11. Nuclear power and sustainable development

    International Nuclear Information System (INIS)

    Sandklef, S.

    2000-01-01

    Nuclear Power is a new, innovative technology for energy production, seen in the longer historic perspective. Nuclear technology has a large potential for further development and use in new applications. To achieve this potential the industry needs to develop the arguments to convince policy makers and the general public that nuclear power is a real alternative as part of a sustainable energy system. This paper examines the basic concept of sustainable development and gives a quality review of the most important factors and requirements, which have to be met to quality nuclear power as sustainable. This paper intends to demonstrate that it is not only in minimising greenhouse gas emissions that nuclear power is a sustainable technology, also with respect to land use, fuel availability waste disposal, recycling and use of limited economic resources arguments can be developed in favour of nuclear power as a long term sustainable technology. It is demonstrated that nuclear power is in all aspects a sustainable technology, which could serve in the long term with minimal environmental effects and at minimum costs to the society. And the challenge can be met. But to achieve need political leadership is needed, to support and develop the institutional and legal framework that is the basis for a stable and long-term energy policy. Industry leaders are needed as well to stand up for nuclear power, to create a new industry culture of openness and communication with the public that is necessary to get the public acceptance that we have failed to do so far. The basic facts are all in favour of nuclear power and they should be used

  12. Developing Infrastructure for New Nuclear Power Programmes

    International Nuclear Information System (INIS)

    2011-09-01

    Many countries are interested in introducing or expanding nuclear energy programmes because they regard nuclear power as a clean and stable source of electricity that can help to mitigate the impact of climate change. However, the March 2011 accident at the Fukushima Daiichi nuclear power plant in Japan - caused by an earthquake and tsunami of unprecedented proportions - demonstrated that there is a constant need to improve global nuclear safety, despite the great progress made in the previous 25 years. A 'safety first' approach needs to become fully entrenched among nuclear power plant operators, governments and regulators everywhere. Safety first must also be the watchword for Member States considering the introduction of nuclear power. I believe that all IAEA Member States should have access to nuclear power if they wish to add it their energy mix. While it is up to each country to decide whether or not to opt for nuclear power, the IAEA has a key role to play in ensuring that the development of nuclear power programmes takes place in a safe, efficient, responsible and sustainable manner. The IAEA has developed guidelines and milestones to help countries work in a systematic way towards the introduction of nuclear power. Use of the 'Milestones' approach can increase transparency both within a country introducing nuclear power, and between it and other States. This brochure summarizes the services which the IAEA offers to Member States considering introducing nuclear power. These include advice on proper planning, building the required human resources and infrastructure, establishing legal and regulatory frameworks, and ensuring the highest standards of safety and security, without increasing proliferation risks. The IAEA offers independent know-how on the construction, commissioning, startup and operation of nuclear reactors. Through the Technical Cooperation programme, we provide targeted support to 'newcomer' countries in response to national development needs

  13. Recent EU institutional developments in the nuclear field: outlook positive

    International Nuclear Information System (INIS)

    Ivens, Richard

    2008-01-01

    The main topics presented and discussed are:European Nuclear Energy Forum (ENEF); European Nuclear Installations Safety Standards (ENISS); High Level Group on Safety and Radioactive Waste (HLG); Sustainable Nuclear Energy Technology Platform (SNETP); Strategic Energy Technology Plan (SETP); EP report on Conventional Energies Forthcoming EU developments

  14. Practical standard for nuclear power plant life management programs: 2007

    International Nuclear Information System (INIS)

    2006-03-01

    The standard specifies the method of implementing nuclear power plant life management programs. The plant life management programs evaluate the integrity of the plant structures, systems and components, assessing if appropriate measures are taken against existing aging phenomena, if there are possibilities of occurrence and development of aging phenomena and if a sufficient level of margin is maintained to assure the integrity throughout the future operating period. The programs also assess the validity of the current maintenance activities, such as trend monitoring, walkdowns, periodic tests and inspections, repair and replacement work for the purpose of preventive maintenance, and utilization of lessons learned from past trouble experience, in order to newly identify maintenance measures. The technical evaluation on aging phenomena is conducted to establish the 10 year maintenance program for nuclear power plants until the plant reaches 30 years of service. The standard was established and issued by the Atomic Energy Society of Japan (AESJ) through the discussion of experts in the associated fields. (T. Tanaka)

  15. Nuclear power in developing countries

    International Nuclear Information System (INIS)

    Laue, H.J.; Bennett, L.L.; Skjoeldebrand, R.

    1984-01-01

    Experience clearly indicates that most developing countries actively planning and implementing nuclear power require broad-scope assistance if their use of nuclear technology is to be safe, economic, and reliable. The IAEA's assistance is directed both to general planning, and to the development of supporting structures and is based on an assessment of needs which cannot be satisfied by other means. The Agency's Division of Nuclear Power has the technical background and tools to support a comprehensive programme of assistance in nuclear power assessment, planning, and implementation. The overall objective of such a programme is to help strengthen national capabilities of executing the following tasks: Analysis of overall energy and electricity demand and supply projections; planning the possible role of nuclear power in electricity supply, through determining the economically optimal extent and schedule for the introduction of nuclear power plants; assessing the available infrastructures and the need, constraints, and possibilities for their development; and developing master schedules, programmes, and recommendations for action. Proposed programmes must be reviewed periodically, and one of the Agency's aims is to ensure that national competence to carry out such reviews exists or can be developed. Training of local staff is therefore one of the most important objectives

  16. Standard leach tests for nuclear waste materials

    International Nuclear Information System (INIS)

    Strachan, D.M.; Barnes, B.O.; Turcotte, R.P.

    1980-01-01

    Five leach tests were conducted to study time-dependent leaching of waste forms (glass). The first four tests include temperature as a variable and the use of three standard leachants. Three of the tests are static and two are dynamic (flow). This paper discusses the waste-form leach tests and presents some representative data. 4 figures

  17. Perspective on worldwide nuclear developments

    International Nuclear Information System (INIS)

    Doub, W.O.; Muntzing, L.M.

    1976-01-01

    While this article centers on discussing the world need for energy, reviewing some of the problems that are being encountered in meeting that demand, and making some recommendations, the overriding point is that much depends upon America's own internal policies. Most of the nuclear technology-recipient nations are the less-developed countries, and just meeting present needs is forcing them to financial limits in terms of attracting external financing. Meanwhile, the dollar dimensions of ''going nuclear'' are increasing and the fact that it can take eight to ten years before a nuclear plant begins paying out threatens to take proposals for external financing ''off the market.'' There must be direct government support of nuclear plant proposals in recipient nations. There is a parallel need for institutions--such as the United States' own Export-Import Bank--to come up with policies specifically geared to nuclear needs. Both actions should receive support because building those plants is of national importance, both to the exporter and the recipient. In the view of those involved in such financing, there is no doubt the global money markets can meet the demand, but the allocation process needs tailoring to the specific nuclear situation. The export of nuclear power, in a properly competitive atmosphere that does not encourage reduction of protective features and that effectively controls the risks of nuclear power, is one of the most feasible means by which the U.S. can help mankind toward an improved world society

  18. NASA Occupant Protection Standards Development

    Science.gov (United States)

    Somers, Jeffrey; Gernhardt, Michael; Lawrence, Charles

    2012-01-01

    Historically, spacecraft landing systems have been tested with human volunteers, because analytical methods for estimating injury risk were insufficient. These tests were conducted with flight-like suits and seats to verify the safety of the landing systems. Currently, NASA uses the Brinkley Dynamic Response Index to estimate injury risk, although applying it to the NASA environment has drawbacks: (1) Does not indicate severity or anatomical location of injury (2) Unclear if model applies to NASA applications. Because of these limitations, a new validated, analytical approach was desired. Leveraging off of the current state of the art in automotive safety and racing, a new approach was developed. The approach has several aspects: (1) Define the acceptable level of injury risk by injury severity (2) Determine the appropriate human surrogate for testing and modeling (3) Mine existing human injury data to determine appropriate Injury Assessment Reference Values (IARV). (4) Rigorously Validate the IARVs with sub-injurious human testing (5) Use validated IARVs to update standards and vehicle requirement

  19. International physical protection standards: support for development and implementation

    International Nuclear Information System (INIS)

    Soo Hoo, M.S.

    2002-01-01

    Full text: Since 1972, the IAEA has been a recognized organization in promoting the development of international standards on the physical protection of nuclear materials. This responsibility has continued through the present in the 1999 publication of the fourth revision of INFCIRC/225, the physical protection of nuclear material and nuclear facilities and in being the repository for the convention on the physical protection of nuclear material which was originally published in 1980 as INFCIRC/274. The IAEA has also published other reference documents in support these two standards. With changing world events and greater concern for the physical protection of nuclear materials and facilities, IAEA member states have increased IAEA physical protection responsibilities. Currently, the IAEA is serving as the secretariat for drafting revisions to the physical protection convention. The proposed revisions will strengthen international physical protection standards through the incorporation of physical protection fundamentals that should apply to all nuclear materials in international or domestic use, storage and transport. Furthermore, the physical protection fundamentals would also extend to include nuclear facilities. Presently, the physical protection convention applies only to nuclear materials that are in international transport. To complement efforts to develop and promote international physical protection standards, the IAEA is actively involved in assisting member states with the implementation of the standards. This is accomplished through the delivery of training courses, workshops and hosting other international forums for the exchange of information. Through review services such as the international physical protection advisory service (IPPAS), the IAEA provides advice to member states on the application of international standards at national and facility-specific levels. These services can be followed up with technical support to implement the

  20. Developing and maintaining nuclear competencies

    International Nuclear Information System (INIS)

    Gobert, C.

    2004-01-01

    The paper discusses the following aspects on the nuclear knowledge management: assimilation of knowledge management, recognition of the nuclear specificity, attracting young talents. Another feature which, possibly, differentiates nuclear from other high-tech industries is that time constraints in some nuclear development may very well exceed the duration of a generation of professionals. That means, not only maintaining scientific and technical knowledge, which, as a minimum, leads to maintain: a rigorous supervision of human resources in quality and quantity; anticipatory planning of human resources, with a special focus on succession planning concerning expertise positions; a steady and continuous effort in training and retraining programs. Maintaining the safety culture is also one of the major managerial duties. Taking full account of the nuclear specificity in knowledge maintenance and development in the AREVA group, requests a multifunctional approach, which combines efforts of Research and Innovation, and Human Resources departments, plus the group Nuclear inspectorate. It is acknowledged that the industry, basically, would readily rely on the capabilities of the academic world and research centers in ensuring that training and education in nuclear science and technologies are attuned to the evolving needs of the industry, in maintaining the proper educational programs and in fostering fruitful cooperations between them

  1. Future developments in nuclear power

    International Nuclear Information System (INIS)

    Phillips, G.J.

    1978-12-01

    To date, the peaceful application of nuclear energy has been largely restricted to the generation of electricity. Even with such an application there is potential for wider use of the nuclear energy generated in providing heat for dwellings, control of climate for the production of vegetables and providing warm water for fish and lobster farming. It is possible to envisage specific applications of nuclear power reactors to process industries requiring large blocks of energy. These and other future developments are reviewed in this report. (author)

  2. Status of ANSI standards on decommissioning of nuclear reprocessing facilities

    International Nuclear Information System (INIS)

    Graham, H.B.

    1975-01-01

    A definition of decommissioning is given, and the preparation of ANSI Standard, ''General Design Criteria for Nuclear Reprocessing Facilities'' (N101.3) is discussed. A Eurochemic report, entitled ''The Shutdown of Reprocessing Facilities--Results of Preliminary Studies on the Installations Belonging to Eurochemic,'' was used in the preparation of this standard. (U.S.)

  3. The status of nuclear development

    International Nuclear Information System (INIS)

    Brown, B.J.

    1974-01-01

    The purpose of this review is to report on topics discussed at the Congress which are relevant to developments in the more applied areas of nuclear technology. These include subjects related to the short- and long-term potentials of nuclear power (fission and fusion) in the perspective of future energy requirements, the industrial uses of atomic radiation and the effects of ionising radiation on man. (R.L.)

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

    International Nuclear Information System (INIS)

    Soman, S.D.

    1996-01-01

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

  5. IEEE [Institute of Electrical and Electronics Engineers] standards and nuclear software quality engineering

    International Nuclear Information System (INIS)

    Daughtrey, T.

    1988-01-01

    Significant new nuclear-specific software standards have recently been adopted under the sponsorship of the American Nuclear Society and the American Society of Mechanical Engineers. The interest of the US Nuclear Regulatory Commission has also been expressed through their issuance of NUREG/CR-4640. These efforts all indicate a growing awareness of the need for thorough, referenceable expressions of the way to build in and evaluate quality in nuclear software. A broader professional perspective can be seen in the growing number of software engineering standards sponsored by the Institute of Electrical and Electronics Engineers (IEEE) Computer Society. This family of standards represents a systematic effort to capture professional consensus on quality practices throughout the software development life cycle. The only omission-the implementation phase-is treated by accepted American National Standards Institute or de facto standards for programming languages

  6. Nuclear power in developing countries

    International Nuclear Information System (INIS)

    Lane, J.A.; Covarrubias, A.J.; Csik, B.J.; Fattah, A.; Woite, G.

    1977-01-01

    This paper is intended to be a companion to similar papers by OECD/NEA and CMEA and will summarize the nuclear power system plans of developing Member States most likely to have nuclear programmes before the year 2000. The information that is presented is derived from various sources such as the Agency 1974 study of the market for nuclear power in developing countries, the annual publication, ''Power Reactors in Member States - 1976 Edition'', various nuclear power planning studies carried out by the Agency during the period 1975 and 1976, direct correspondence with selected Member States and published information in the open literature. A preliminary survey of the prospects for nuclear power in Member States not belonging to the OECD or having centrally planned economies indicates that about 27 of these countries may have operating nuclear power plants by the end of the century. In the 1974 Edition of the ''Market Survey'' it was estimated that the installed nuclear capacity in these countries might reach 24 GW by 1980, 157 GW by 1190 and 490 GW by the year 2000. It now appears that these figures are too high for a number of reasons. These include 1) the diminished growth in electrical demand which has occurred in many Member States during the last several years, 2) the extremely high cost of nuclear plant construction which has placed financial burdens on countries with existing nuclear programmes, 3) the present lack of commercially available small and medium power reactors which many of the smaller Member States would need in order to expand their electric power systems and 4) the growing awareness of Member States that more attention should be paid to exploitation of indigenous energy sources such as hydroelectric power, coal and lignite

  7. Nuclear Thermal Propulsion Development Risks

    Science.gov (United States)

    Kim, Tony

    2015-01-01

    There are clear advantages of development of a Nuclear Thermal Propulsion (NTP) for a crewed mission to Mars. NTP for in-space propulsion enables more ambitious space missions by providing high thrust at high specific impulse ((is) approximately 900 sec) that is 2 times the best theoretical performance possible for chemical rockets. Missions can be optimized for maximum payload capability to take more payload with reduced total mass to orbit; saving cost on reduction of the number of launch vehicles needed. Or missions can be optimized to minimize trip time significantly to reduce the deep space radiation exposure to the crew. NTR propulsion technology is a game changer for space exploration to Mars and beyond. However, 'NUCLEAR' is a word that is feared and vilified by some groups and the hostility towards development of any nuclear systems can meet great opposition by the public as well as from national leaders and people in authority. The public often associates the 'nuclear' word with weapons of mass destruction. The development NTP is at risk due to unwarranted public fears and clear honest communication of nuclear safety will be critical to the success of the development of the NTP technology. Reducing cost to NTP development is critical to its acceptance and funding. In the past, highly inflated cost estimates of a full-scale development nuclear engine due to Category I nuclear security requirements and costly regulatory requirements have put the NTP technology as a low priority. Innovative approaches utilizing low enriched uranium (LEU). Even though NTP can be a small source of radiation to the crew, NTP can facilitate significant reduction of crew exposure to solar and cosmic radiation by reducing trip times by 3-4 months. Current Human Mars Mission (HMM) trajectories with conventional propulsion systems and fuel-efficient transfer orbits exceed astronaut radiation exposure limits. Utilizing extra propellant from one additional SLS launch and available

  8. Nuclear power for developing countries

    International Nuclear Information System (INIS)

    Kendall, J.; Kupitz, J.; Rogner, H. H.

    2000-01-01

    Nuclear power is a proven technology which currently makes a large contribution to the electricity supply in a number of countries and, to a much less extent, to heat supply in some countries. Nuclear power is economically competitive with fossil fuels for base load electricity generation in many countries, and is one of the commercially proven energy supply options that could be expanded in the future to reduce environmental burdens, especially greenhouse gas emissions, from the electricity sector. Over the past five decades, nearly ten thousand reactor-years of operating experience have been accumulated with current nuclear power plants. Building upon this background of success and applying lessons learned from the experience of operating plants, new generations of nuclear power plants have been, or are being developed. Improvements incorporated into these advance designs include features that will allow operators more time to perform equipment protection and safety actions in response to equipment failures and other off normal operating conditions, and that will reduce and simplify the actions required. Great attention is also paid to making new plants simpler to operate, inspect, maintain and repair, thus increasing their overall cost efficiency and their compatibility with the infrastructure of developing countries. The paper provides a discussion of future world energy supply and demand projections, current status and prospects for nuclear power, a short summary of advanced reactor concepts and non-electrical applications of nuclear energy for developing countries, and a review of the role of the IAEA. (author)

  9. Development of nuclear waste concrete drum

    International Nuclear Information System (INIS)

    Wen Yinghui

    1995-06-01

    The raw materials selection and the properties for nuclear waste concrete drum, the formula and properties of the concrete, the specification and technical quality requirement of the drum were described. The manufacture essentials and technology, the experiments and checks as well as the effective quality control and quality assurance carried out in the course of production were presented. The developed nuclear waste drum has a simple structure, easily available raw materials and rational formula for concrete. The compressive strength of the drum is more than 70 MPa, the tensile strength is more than 5 MPa, the nitrogen permeability is (2.16∼3.6) x 10 -18 m 2 . The error of the drum in dimensions is +-2 mm. The external surface of the drum is smooth. The drum accords with China standards in the sandy surface, void and crack. The results shows China has the ability to develop and manufacture nuclear waste concrete container and lays the foundation for standardization and series of the nuclear waste container for packing and transporting nuclear wastes in China. (5 figs., 10 tabs.)

  10. Indicators for Nuclear Power Development

    International Nuclear Information System (INIS)

    2015-01-01

    Considering the scale of nuclear power aspirations, the number of planned nuclear new builds and the prospects of a number of countries constructing their first nuclear power plants, there is a need to assess the broader context of nuclear energy programmes in areas of macro-and socioeconomic conditions, energy systems and nuclear power, and the environment. It is important to assess the degree to which introduction or expansion of nuclear power is beneficial under these specific circumstances. This publication provides a set of indicators for nuclear power development that can serve as a tool to help explore these issues. The indicators are meant to provide a first order assessment of the situation and identify the issues that present the benefits and challenges in a balanced and objective manner and thereby help guide more detailed evaluations in the next stage of planning and preparations. Methodology sheets are provided to help users in data collection, quantification and interpretation of the indicators. The application of the indicators set is flexible. Users can select a subset of indicators that are most relevant for the questions they wish to explore in a given study or decision making process

  11. Rhodium self-powered neutron detector's lifetime for korean standard nuclear power plants

    International Nuclear Information System (INIS)

    Yoo, Choon Sung; Kim, Byoung Chul; Park, Jong Ho; Fero, Arnold H.; Anderson, S. L.

    2005-01-01

    A method to estimate the relative sensitivity of a self-powered rhodium detector for an upcoming cycle is developed by combining the rhodium depletion data from a nuclear design with the site measurement data. This method can be used both by nuclear power plant designers and by site staffs of Korean standard nuclear power plants for determining which rhodium detectors should be replaced during overhauls

  12. Nuclear safeguards research and development

    Science.gov (United States)

    Henry, C. N.

    1981-11-01

    The status of a nuclear safeguard research and development program is presented. Topics include nondestructive assay technology development and applications, international safeguards, training courses, technology transfer, analytical chemistry methods for fissionable materials safeguards, the Department of Energy Computer Security Technical Center, and operational security.

  13. Nuclear microprobe analysis of the standard reference materials

    International Nuclear Information System (INIS)

    Jaksic, M.; Fazinic, S.; Bogdanovic, I.; Tadic, T.

    2002-01-01

    Most of the presently existing Standard Reference Materials (SRM) for nuclear analytical methods are certified for the analyzed mass of the order of few hundred mg. Typical mass of sample which is analyzed by PIXE or XRF methods is very often below 1 mg. By the development of focused proton or x-ray beams, masses which can be typically analyzed go down to μg or even ng level. It is difficult to make biological or environmental SRMs which can give desired homogeneity at such low scale. However, use of fundamental parameter quantitative evaluation procedures (absolute method), minimize needs for SRMs. In PIXE and micro PIXE setup at our Institute, fundamental parameter approach is used. For exact calibration of the quantitative analysis procedure just one standard sample is needed. In our case glass standards which showed homogeneity down to micron scale were used. Of course, it is desirable to use SRMs for quality assurance, and therefore need for homogenous materials can be justified even for micro PIXE method. In this presentation, brief overview of PIXE setup calibration is given, along with some recent results of tests of several SRMs

  14. World nuclear developments after Chernobyl

    International Nuclear Information System (INIS)

    Rippon, S.

    1987-01-01

    1986 will inevitably go down in history as the year of Chernobyl, the consequences of which must be delays in and even withdrawals from the development of nuclear power. On the credit side, the Soviet Union has done a rapid and remarkable job in sealing the damaged reactor and rehabilitating the station and the area while improving the safety of its total program. Equally effective has been the response of the IAEA. In terms of nuclear power's claim as a major source of energy, nothing has changed as a result of Chernobyl. 15% of the world's electricity is now produced from nearly 400 power reactors. In comparison with any other energy form nuclear energy must rank high in terms of economy, safety and environmental effects. What has changed is the public perception of nuclear power, and the effort world-wide which will need to be made to restore public confidence

  15. Nuclear knowledge, trust and public acceptance of nuclear developments

    International Nuclear Information System (INIS)

    Berdahl, A.L.; Bell, B.S.; Bourassa, C.M.; Fried, D.J.

    2014-01-01

    While nuclear sector activities remain contentious public issues, studies suggest that knowledge levels and trust in nuclear actors can influence public attitudes. Drawing on original data from a 2013 representative telephone survey of Saskatchewan residents, this paper considers the extent to which knowledge and trust influence support for nuclear developments. Saskatchewan provides an interesting case study: while the province has a robust uranium mining industry, there are no nuclear power facilities, and the potential development of nuclear energy and nuclear fuel waste storage has been a source of spirited public debate. The study's results have implications for public education and policy initiatives regarding nuclear power developments. (author)

  16. Nuclear knowledge, trust and public acceptance of nuclear developments

    Energy Technology Data Exchange (ETDEWEB)

    Berdahl, A.L.; Bell, B.S.; Bourassa, C.M.; Fried, D.J., E-mail: Loleen.Berdahl@usask.ca, E-mail: Bourassa@edwards.usask.ca, E-mail: Scott.Bell@usask.ca, E-mail: Jana.Fried@usask.ca [Univ. of Saskatchewan, Saskatoon, SK (Canada)

    2014-07-01

    While nuclear sector activities remain contentious public issues, studies suggest that knowledge levels and trust in nuclear actors can influence public attitudes. Drawing on original data from a 2013 representative telephone survey of Saskatchewan residents, this paper considers the extent to which knowledge and trust influence support for nuclear developments. Saskatchewan provides an interesting case study: while the province has a robust uranium mining industry, there are no nuclear power facilities, and the potential development of nuclear energy and nuclear fuel waste storage has been a source of spirited public debate. The study's results have implications for public education and policy initiatives regarding nuclear power developments. (author)

  17. Advanced passive technology: A global standard for nuclear plant requirements

    Energy Technology Data Exchange (ETDEWEB)

    Novak, V

    1994-12-31

    Since 1984, Westinghouse has been developing AP8OO, a 800 MW, two-loop advanced passive plant, in response to an initiative established by the Electric Power Research Institute (EPRI) and the U.S. Department of Energy` (DOE). The preliminary design was cornpleved in 1989. AP6OO`s Standard Safety Analysis and Probabilistic Risk analysis Reports were submitted to the U.S. Nuclear Regulatory Commission for design certification in 1992. Design simplification is the key strategy behind the AP6OO. The basic technical concept Of simplification has resulted in a simplified reactor coolant systems, simplified plant systems, a simplified plant arrangement, reduced number of components, simplified operation and maintenance.

  18. Nuclear Power and Sustainable Development (French Edition)

    International Nuclear Information System (INIS)

    2008-01-01

    Any discussion of 21st century energy trends must take into account the global energy imbalance. Roughly 1.6 billion people still lack access to modern energy services, and few aspects of development - whether related to living standards, health care or industrial productivity - can take place without the requisite supply of energy. As we look to the century before us, the growth in energy demand will be substantial, and 'connecting the unconnected' will be a key to progress. Another challenge will be sustainability. How can we meet these growing energy needs without creating negative side effects that could compromise the living environment of future generations? Nuclear power is not a 'fix-all' option. It is a choice that has a place among the mix of solutions, and expectations for the expanding use of nuclear power are rising. In addition to the growth in demand, these expectations are driven by energy security concerns, nuclear power's low greenhouse gas emissions, and the sustained strong performance of nuclear plants. Each country must make its own energy choices; one size does not fit all. But for those countries interested in making nuclear power part of their sustainable development strategies, it is important that the nuclear power option be kept open and accessible [fr

  19. Nuclear Power and Sustainable Development (Spanish Edition)

    International Nuclear Information System (INIS)

    2008-02-01

    Any discussion of 21st century energy trends must take into account the global energy imbalance. Roughly 1.6 billion people still lack access to modern energy services, and few aspects of development - whether related to living standards, health care or industrial productivity - can take place without the requisite supply of energy. As we look to the century before us, the growth in energy demand will be substantial, and 'connecting the unconnected' will be a key to progress. Another challenge will be sustainability. How can we meet these growing energy needs without creating negative side effects that could compromise the living environment of future generations? Nuclear power is not a 'fix-all' option. It is a choice that has a place among the mix of solutions, and expectations for the expanding use of nuclear power are rising. In addition to the growth in demand, these expectations are driven by energy security concerns, nuclear power's low greenhouse gas emissions, and the sustained strong performance of nuclear plants. Each country must make its own energy choices; one size does not fit all. But for those countries interested in making nuclear power part of their sustainable development strategies, it is important that the nuclear power option be kept open and accessible [es

  20. Development of nuclear track detectors

    International Nuclear Information System (INIS)

    Somogyi, Gyoergy

    1985-01-01

    The birth and development of two decades of a new nuclear detection method is briefly summarized by one of the first inventors. The main steps of the development and broadening application of nuclear solid state track detectors are described underlying the contribution and main results of the research group of ATOMKI, Hungary (i.e. the finding of the proper plastic materials for track detectors, the discovery of correlations between the track diameter and the particle energy, the increasing of energy resolution, explanation of the track developing process, elaboration of new electrochemical track analyzing methods and automatic track analyzers). Recently, this detecting technique has grown to the phase of the industrial mass production and broad application in radiogeochemistry, mining, radioecology, personal monitoring in nuclear power plants, etc. (D.Gy.)

  1. Nuclear power development: History and outlook

    International Nuclear Information System (INIS)

    Char, N.L.; Csik, B.J.

    1987-01-01

    The history of nuclear power development is briefly described (including the boosts from oil price shocks to the promotion of nuclear energy). The role of public opinion in relation to nuclear power is mentioned too, in particular in connection with accidents in nuclear plants. The recent trends in nuclear power development are described and the role of nuclear power is foreseen. Estimates of total and nuclear electrical generating capacity are made

  2. An operational approach to standard nuclear process model (SNPM) and SAP nuclear software implementation at Slovenske Elektrarne

    International Nuclear Information System (INIS)

    Warren, C.C.

    2010-01-01

    Benchmarking efforts in the fall of 2006 showed significant performance gaps in multiple measured processes between the Slovenske Elektrarne (SE) nuclear organization and the highest performing nuclear organizations in the world. While overall performance of the SE nuclear fleet was good and in the second quartile, when compared to the worldwide population of Pressurized Water Reactors (PWR), SE leadership set new goals to improve safety and operational performance to the first decile of the worldwide PWR Fleet. To meet these goals the SE nuclear team initiated a project to identify and implement the Best Practice nuclear processes in multiple areas. The benchmarking process identified the Standard Nuclear Performance Model (SNPM), used in the US nuclear fleet, as the industry best practice process model. The Slovenske Elektrarne nuclear management team used various change management techniques to clearly establish the case for organizational and process change within the nuclear organization. The project organization established by the SE nuclear management team relied heavily on functional line organization personnel to gain early acceptance of the project goals and methods thereby reducing organizational opposition to the significant organizational and process changes. The choice of a standardized process model used, all or in part, by approximately one third of the nuclear industry worldwide greatly facilitated the development and acceptance of the changes. Use of a nuclear proven templated software platform significantly reduced development and testing efforts for the resulting fully integrated solution. In the spring of 2007 SE set in motion a set of initiatives that has resulted in a significant redesign of most processes related to nuclear plant maintenance and continuous improvement. Significant organizational structure changes have been designed and implemented to align the organization to the SNPM processes and programs. The completion of the initial

  3. An operational approach to standard nuclear process model (SNPM) and SAP nuclear software implementation at Slovenske Elektrarne

    Energy Technology Data Exchange (ETDEWEB)

    Warren, C.C. [Nuclear Power Plants Operation Department, Slovenske Elektrarne, a.s., Mlynske nivy 47, 821 09 Bratislava (Slovakia)

    2010-07-01

    Benchmarking efforts in the fall of 2006 showed significant performance gaps in multiple measured processes between the Slovenske Elektrarne (SE) nuclear organization and the highest performing nuclear organizations in the world. While overall performance of the SE nuclear fleet was good and in the second quartile, when compared to the worldwide population of Pressurized Water Reactors (PWR), SE leadership set new goals to improve safety and operational performance to the first decile of the worldwide PWR Fleet. To meet these goals the SE nuclear team initiated a project to identify and implement the Best Practice nuclear processes in multiple areas. The benchmarking process identified the Standard Nuclear Performance Model (SNPM), used in the US nuclear fleet, as the industry best practice process model. The Slovenske Elektrarne nuclear management team used various change management techniques to clearly establish the case for organizational and process change within the nuclear organization. The project organization established by the SE nuclear management team relied heavily on functional line organization personnel to gain early acceptance of the project goals and methods thereby reducing organizational opposition to the significant organizational and process changes. The choice of a standardized process model used, all or in part, by approximately one third of the nuclear industry worldwide greatly facilitated the development and acceptance of the changes. Use of a nuclear proven templated software platform significantly reduced development and testing efforts for the resulting fully integrated solution. In the spring of 2007 SE set in motion a set of initiatives that has resulted in a significant redesign of most processes related to nuclear plant maintenance and continuous improvement. Significant organizational structure changes have been designed and implemented to align the organization to the SNPM processes and programs. The completion of the initial

  4. Overview of the ANS [American Nuclear Society] mathematics and computation software standards

    International Nuclear Information System (INIS)

    Smetana, A.O.

    1991-01-01

    The Mathematics and Computations Division of the American Nuclear Society sponsors the ANS-10 Standards Subcommittee. This subcommittee, which is part of the ANS Standards Committee, currently maintains four ANSI/ANS software standards. These standards are: Recommended Programming Practices to Facilitate the Portability of Scientific Computer Programs, ANS-10.2; Guidelines for the Documentation of Computer Software, ANS-10.3; Guidelines for the Verification and Validation of Scientific and Engineering Computer Programs for the Nuclear Industry, ANS-10.4; and Guidelines for Accommodating User Needs in Computer Program Development, ANS-10.5. 5 refs

  5. SWOT of nuclear power plant sustainable development

    International Nuclear Information System (INIS)

    Abbaspour, M.; Ghazi, S.

    2008-01-01

    SWOT Analysis is a Useful tool that can he applied to most projects or business ventures. In this article we are going to examine major strengths, weaknesses, opportunities and threats of nuclear power plants in view of sustainable development. Nuclear power plants have already attained widespread recognition for its benefits in fossil pollution abatement, near-zero green house gas emission, price stability and security of energy supply. The impressive new development is that these virtues are now a cost -free bonus, because, in long run, nuclear energy has become an inexpensive way to generate electricity. Nuclear energy's pre-eminence economically and environmentally has two implications for government policy. First, governments should ensure that nuclear licensing and safety oversight arc not only rigorous but also efficient in facilitating timely development of advanced power plants. Second, governments should be bold incentivizing the transformation to clean energy economics, recognizing that such short-term stimulus will, in the case of nuclear plants, simply accelerate desirable changes that now have their own long-term momentum. The increased competitiveness of nuclear power plant is the result of cost reductions in all aspects of nuclear economics: Construction, financing, operations, waste management and decommissioning. Among the cost-lowering factors are the evolution to standardized reactor designs, shorter construction periods, new financing techniques, more efficient generation technologies, higher rates of reactor utilization, and longer plant lifetimes. U.S World Nuclear Association report shows that total electricity costs for power plant construction and operation were calculated at two interest rates. At 10%, midrange generating costs per kilowatt-hour are nuclear at 4 cents, coal at 4.7 cents and natural gas at 5.1 cent. At a 5% interest rate, mid-range costs per KWh fall to nuclear at 2.6 cents, coal at 3.7 cents and natural gas at 4.3 cents

  6. Prospects of Nuclear Power for Developing Countries

    International Nuclear Information System (INIS)

    Mourogov, V. M.; Khan, A. M.; Rogner, H-H.; Kagramanian, V. S.

    1998-01-01

    The demand for electricity in developing countries of the world is expected to grow rapidly in the coming decades as these countries undergo the process of industrialization, accompanied by increased urbanization, and seek to improve the living standards of their growing population. The continued heavy reliance of the power sector on fossil fuels will result in an increased dependence of a number of the developing countries on energy imports, with consequentbalance of payment difficulties and implications in terms of reduced energy security, cause severe degradation of the local and regional environment, and will also lead to increasing emissions of greenhouse gases. Increasing the share of hydropower in most of the developing countries is constrained by the limited potential of hydro resources as well as environmental considerations. Other renewable energy technologies such as solar PV and wind power are not expected to play a significant role in the commercial supply of electricity in the foreseeable future in the most part of the developing world. Thus nuclear power as a non-fossil alternative with a proven and mature technology may be called upon to play an increasing role in the future supply of electricity to developing countries. The paper discusses the main factors that are likely to affect, both positively and negatively, the deployment of nuclear power in developing countries and presents the results of the recent IAEA projections on nuclear power capacity growth up to the 2020. The paper also briefly reviews the prospects of nuclear power in Central and Eastern European countries. (author)

  7. Career Development in Nuclear Engineering

    International Nuclear Information System (INIS)

    Sibbens, G.

    2015-01-01

    In the eighties it was not common for girls to study engineering. But a few young girls have always been fascinated by science and technical applications and dared to go for a gender untypical education. What are these female engineers doing today? This paper describes the career development of a woman, who completed her Master of Science in Nuclear Engineering, found first a job in an international company as cooperator in the research group of radiation physics and later as head of technical support and quality assurance of medical systems and then succeeded in a competition to be recruited at the European Commission (EC). There she started as an assistant for the primary standardisation of radionuclides and high-resolution alpha-particle spectrometry including the preparation of radioactive sources in the radionuclide metrology sector at the Institute for Reference Materials and Measurements of the European Commission’s Joint Research Centre and consequently published her work in scientific journals. Today, 29 years later, I am the laboratory responsible for the preparation and characterisation of nuclear targets at EC-JRC-IRMM, leading a team that has unique know-how in the preparation of thin film deposits (called targets) tailor-made for nuclear physics measurements at the EC–JRC–IRMM and international accelerator sites. High quality measurements of nuclear data and materials are being asked for in the context of nuclear safety, minimisation of high level nuclear waste and safeguards and security. The different steps of my career development and the repeated process of managing learning, work, family and leisure are presented. The career path across different jobs and responsibilities and the career progress via a certification training programme are also explained to encourage the next generation of female professionals to continue playing a vital role in nuclear science and technology. (author)

  8. ASME nuclear codes and standards: Scope of coverage and current initiatives

    International Nuclear Information System (INIS)

    Eisenberg, G. M.

    1995-01-01

    The objective of this paper is to address the broad scope of coverage of nuclear codes, standards and guides produced and administered by the American Society of Mechanical Engineers (ASME). Background information is provided regarding the evolution of the present activities. Details are provided on current initiatives intended to permit ASME to meet the needs of a changing nuclear industry on a worldwide scale. During the early years of commercial nuclear power, ASME produced a code for the construction of nuclear vessels used in the reactor coolant pressure boundary, containment and auxiliary systems. In response to industry growth, ASME Code coverage soon broadened to include rules for construction of other nuclear components, and inservice inspection of nuclear reactor coolant systems. In the years following this, the scope of ASME nuclear codes, standards and guides has been broadened significantly to include air cleaning activities for nuclear power reactors, operation and maintenance of nuclear power plants, quality assurance programs, cranes for nuclear facilities, qualification of mechanical equipment, and concrete reactor vessels and containments. ASME focuses on globalization of its codes, standards and guides by encouraging and promoting their use in the international community and by actively seeking participation of international members on its technical and supervisory committees and in accreditation activities. Details are provided on current international representation. Initiatives are underway to separate the technical requirements from administrative and enforcement requirements, to convert to hard metric units, to provide for non-U. S. materials, and to provide for translations into non-English languages. ASME activity as an accredited ISO 9000 registrar for suppliers of mechanical equipment is described. Rules are being developed for construction of containment systems for nuclear spent fuel and high-level waste transport packagings. Intensive

  9. standards used for quality control of nuclear fuels

    International Nuclear Information System (INIS)

    Guereli, L; Can, S.

    1997-01-01

    Nuclear fuels and fuel materials are subject to stringent restrictions as to their quality. The standards and regulations that apply vary according to reactor type and country and the standards are stated in the quality assurance documents. The concept of quality assurance has altered the conventional quality control tests and procedures, defining which control tests are to be applied and how. Although most of the tests and measurements allow the determination of tolerances to be decided according to the agreement between the buyer and the seller, exacting procedures apply to which instruments and equipment are used for these tests and measurements, how these instruments are standardized.Detailed explanations of test methods and their documentation is a requirement in all standards. The purpose of this work is to study which standards, tests and measurements apply to the nuclear fuel production. Only the standards that apply to various stages of the nuclear fuel production (powder preparation, pellet production, fuel element and fuel assembly fabrication) are reviewed. Process and documentation control, design and licensing requirements and the frequency of inspections are quality assurance subjects. Some ASTM standards are given as examples

  10. Nuclear technology for sustainable development

    International Nuclear Information System (INIS)

    2001-01-01

    Introduces three of the IAEA's current programmes: Promoting food security - use of the sterile insect technique to eradicate the tsetse fly in Sub-Saharan Africa; Managing water resources - use of isotope hydrology to check water for traces of arsenic in Bangladesh; Improving human health - use of nuclear techniques for diagnosis, imaging and cancer treatment in developing countries

  11. Nuclear imaging drug development tools

    International Nuclear Information System (INIS)

    Buchanan, L.; Jurek, P.; Redshaw, R.

    2007-01-01

    This article describes the development of nuclear imaging as an enabling technology in the pharmaceutical industry. Molecular imaging is maturing into an important tool with expanding applications from validating that a drug reaches the intended target through to market launch of a new drug. Molecular imaging includes anatomical imaging of organs or tissues, computerized tomography (CT), magnetic resonance imaging (MRI) and ultrasound.

  12. Human Resources Development for Jordan’s Nuclear Energy Programme

    International Nuclear Information System (INIS)

    Malkawi, Salaheddin; Amawi, Dala’

    2014-01-01

    Jordan's HRD strategy: • Utilize Jordan’s academic infrastructure: – 25 Universities (10 public & 15 private); – 35 Community Colleges (15 public & 20 private). • Build on existing programmes and establish new ones to support Nuclear Energy Programme. • Nuclear Education in Jordan: – B. Sc. Nuclear Engineering at Jordan University of Science & Technology (JUST); – M. Sc. Nuclear Physics at University of Jordan, Yarmouk University and Al-Balqa Applied University. • Scholarships for M. Sc. and Ph. D in Nuclear Engineering and Nuclear Science from Universities outside Jordan: – United States, Russia, France, Japan, China, Korea. Utilization of JSA and JRTR; • Vendor supplied training; • Support through Nuclear Cooperation Agreements; • IAEA Technical Cooperation; • Development of a Jordan-Specific Qualification and Certification Programmes; • Specialized Training in International Codes & Standards: – Transition to JNRC Developed/Adopted Standards, Codes, Regulations

  13. Development of a standard for indoor radon measurements in Australia

    International Nuclear Information System (INIS)

    O'Brien, R.S.; Solomon, S.B.

    1994-01-01

    A standard covering methodologies for the measurement of indoor radon and radon progeny concentrations in air in Australian buildings is currently under preparation as part of a set of standards covering total indoor air quality. This paper outlines the suggested methodology for radon and discusses some of the problems associated with the development of the standard. The draft standard recommends measurement of the radon concentration in air using scintillation cells, charcoal cups and solid state nuclear track detectors, and measurement of radon progeny concentration in air using the Rolle method or the Nazaroff method. 14 refs., 1 tab

  14. Standard specification for nuclear-grade zirconium oxide powder

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2008-01-01

    1.1 This specification defines the physical and chemical requirements for zirconium oxide powder intended for fabrication into shapes, either entirely or partially of zirconia, for use in a nuclear reactor core. 1.2 The material described herein shall be particulate in nature. 1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

  15. Technology standards for structure, etc. concerning nuclear power generating facilities

    International Nuclear Information System (INIS)

    1977-01-01

    Based on the Ordinance for the Technology Standards concerning Nuclear Power Generating Facilities, the technology standards are established for the vessels of class 1 to 4 (including reactor pressure vessels, reactor containment vessels, etc.), the pipes of class 1 to 3, safety valves, pressure test and monitoring test specimens. Those specified are materials, nondestructive tests, structures, shapes, shells, flanges, etc. for the vessels and the pipes, and so on. (Mori, K.)

  16. Historical aspects of the nuclear right development

    International Nuclear Information System (INIS)

    Puig, Diva E.

    1999-01-01

    This paper analyses the historical aspects of the nuclear right development. It makes the evolution of the fundamental principles of nuclear right, in special, the civil responsibility for nuclear damages. (author)

  17. Issues and relationships among software standards for nuclear safety applications. Version 2.0

    International Nuclear Information System (INIS)

    Scott, J.A.; Preckshot, G.G.; Lawrence, J.D.; Johnson, G.L.

    1996-01-01

    Lawrence Livermore National Laboratory is assisting the Nuclear Regulatory Commission with the development of draft regulatory guides for selected software engineering standards. This report describes the results of the initial task in this work. The selected software standards and a set of related software engineering standards were reviewed, and the resulting preliminary elements of the regulatory positions are identified in this report. The importance of a thorough understanding of the relationships among standards useful for developing safety-related software is emphasized. The relationship of this work to the update of the Standard Review Plan is also discussed

  18. Development of Nuclear Analytical Technology

    International Nuclear Information System (INIS)

    Park, Yong Joon; Kim, J. Y.; Sohn, S. C.

    2007-06-01

    The pre-treatment and handling techniques for the micro-particles in swipe samples were developed for the safeguards purpose. The development of screening technique for the swipe samples has been established using the nuclear fission track method as well as the alpha track method. The laser ablation system to take a nuclear particle present in swipe was designed and constructed for the determination of the enrichment factors for uranium or plutonium, and its performance was tested in atmosphere as well as in vacuum. The optimum conditions for the synthesis of silica based micro-particles were obtained for mass production. The optimum ion exchange resin was selected and the optimum conditions for the uranium adsorption in resin bead technique were established for the development of the enrichment factor for nuclear particles in swipe. The established technique was applied to the swipe taken directly from the nuclear facility and also to the archive samples of IAEA's environmental swipes. The evaluation of dose rate of neutron and secondary gamma-ray for the radiation shields were carried out to design the NIPS system, as well as the evaluation of the thermal neutron concentration effect by the various reflectors. D-D neutron generator was introduced as a neutron source for the NIPS system to have more advantages such as easier control and moderation capability than the 252 Cf source. Simulated samples for explosive and chemical warfare were prepared to construct a prompt gamma-ray database. Based on the constructed database, a computer program for the detection of illicit chemical and nuclear materials was developed using the MATLAB software

  19. Development of Nuclear Analytical Technology

    Energy Technology Data Exchange (ETDEWEB)

    Park, Yong Joon; Kim, J. Y.; Sohn, S. C. (and others)

    2007-06-15

    The pre-treatment and handling techniques for the micro-particles in swipe samples were developed for the safeguards purpose. The development of screening technique for the swipe samples has been established using the nuclear fission track method as well as the alpha track method. The laser ablation system to take a nuclear particle present in swipe was designed and constructed for the determination of the enrichment factors for uranium or plutonium, and its performance was tested in atmosphere as well as in vacuum. The optimum conditions for the synthesis of silica based micro-particles were obtained for mass production. The optimum ion exchange resin was selected and the optimum conditions for the uranium adsorption in resin bead technique were established for the development of the enrichment factor for nuclear particles in swipe. The established technique was applied to the swipe taken directly from the nuclear facility and also to the archive samples of IAEA's environmental swipes. The evaluation of dose rate of neutron and secondary gamma-ray for the radiation shields were carried out to design the NIPS system, as well as the evaluation of the thermal neutron concentration effect by the various reflectors. D-D neutron generator was introduced as a neutron source for the NIPS system to have more advantages such as easier control and moderation capability than the {sup 252}Cf source. Simulated samples for explosive and chemical warfare were prepared to construct a prompt gamma-ray database. Based on the constructed database, a computer program for the detection of illicit chemical and nuclear materials was developed using the MATLAB software.

  20. Recent developments in nuclear instruments

    International Nuclear Information System (INIS)

    Vaidya, P.P.

    2004-01-01

    Full text : Nuclear Instrumentation is a field of vital importance for DAE. It has important applications in many areas of interest such as Reactor Monitoring and control, Accelerator based research, Laser and nuclear physics experiments, Health and environmental monitoring, Astrophysics experiments etc. It is a specialized field involving expertise in detection of radioactivity down to the level of few events per minute as well as processing and analysis of signals which can be as small as few hundred micro volts embedded in noise. Some applications involve digitizing and processing these signals with 0.001% accuracy and timing accuracies of a fraction of nano sec. Rapid developments in semiconductor related technologies have influenced the field of nuclear instrumentation. Development of FPGA's and ASIC's have made it possible to develop miniaturized smart and portable instruments for field applications. Advancements in field of computers, communications and various field buses have been successfully utilized for smart, portable and DSP based instrumentation. Smart sensor with detector and front-end electronics on a single silicon chip is now a reality. These instruments are also made intelligent by addition of fuzzy logic, artificial neural networks and expert systems. Electronics Division of BARC has made significant contribution to the field of nuclear instrumentation to achieve self-reliance in this area. This has also led to development of several new methods, which have been published in international journals and appreciated worldwide. As a step towards achieving complete self-reliance a programme for development of FPGA's, HMC's and ASIC's has been undertaken and is being followed with special emphasis. This also includes development of detector and front- end electronics on a single chip. This talk brings out details of these developments and describes the 'state of art' work done in India

  1. Nuclear data applications in developing countries

    International Nuclear Information System (INIS)

    Mehta, M.K.; Schmidt, J.J.

    1985-01-01

    The peaceful applications of nuclear science and technology currently receive an increasing attention in many developing countries. More than 15 developing countries operate, construct or plan nuclear power reactors, 70 developing countries are using or planning to use nuclear techniques in medicine, agriculture, industry, and for other vital purposes. The generation, application and computer processing of nuclear data constitute important elements of the nuclear infrastructure needed for the successful implementation of nuclear science and technology. Developing countries become increasingly aware of this need, and, with the help and cooperation of the IAEA Nuclear Data Section, are steadily gaining in experience in this field. The paper illustrates this development in typical examples. (orig.)

  2. A nuclear standard high-efficiency adsorber for iodine

    International Nuclear Information System (INIS)

    Wang Jianmin; Qian Yinge

    1988-08-01

    The structure of a nuclear standard high-efficiency adsorber, adsorbent and its performance are introduced. The performance and structure were compared with the same kind product of other firms. The results show that the leakage rate is less than 0.005%

  3. Standard Specification for Nuclear Grade Zirconium Oxide Pellets

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This specification applies to pellets of stabilized zirconium oxide used in nuclear reactors. 1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

  4. INDC/NEANDC nuclear standards file 1980 version

    International Nuclear Information System (INIS)

    1981-09-01

    This working document of the Nuclear Standards Subcommittee of the International Nuclear Data Committee (INDC) summarizes the status of nuclear standards as of the 11th INDC meeting (6/'80) with selective updating to approximately 5/'81. This version of the file is presented in two sections as per the following. The first section (A) consists of numerical tabulations of the respective quantities generally including quantitative definition of the uncertainties. Most of these numerical values are taken from the ENDF/B-V file which is available on a world-wide basis through the 4-Center network. Some guidelines as to appropriate usage are also given. The objective is the provision of a concise and readily used reference guide to essential standard-nuclear quantities useful for a diversity of basic and applied endeavors. The second section (B) briefly summarizes the contemporary status of each of the standards tabulated in Section A and additional items, including recent relevant work and areas of continuing uncertainty. These brief reviews were prepared under the auspices of the Committee by outstanding specialists in the respective fields. In many instances they are new statements but, where review indicates that the previous statement (see INDC-30/L+sp) remains appropriate, the previous summaries were retained; often with additional remarks by the editor

  5. ASME nuclear codes and standards: Recent technical initiatives

    International Nuclear Information System (INIS)

    Feigel, R. E.

    1995-01-01

    Although nuclear power construction is currently in a hiatus in the US, ASME and its volunteer committees remain committed to continual improvements in the technical requirements in its nuclear codes. This paper provides an overview of several significant recent revisions to ASME' s nuclear codes. Additionally, other important initiatives currently being addressed by ASME committees will be described. With the largest population of operating light water nuclear plants in the world and worldwide use of its nuclear codes, ASME continues to support technical advancements in its nuclear codes and standards. While revisions of various magnitude are an ongoing process, several recent revisions embody significant changes based on state of the art design philosophy and substantial industry experience. In the design area, a significant revisions has recently been approved which will significantly reduce conservatisms in seismic piping design as well as provide simplified design rules. Major revisions have also been made to the requirements for nuclear material manufacturers and suppliers, which should result in clearer understanding of this difficult administrative area of the code. In the area of Section XI inservice rules, substantial studies are underway to investigate the application of probabilistic, risked based inspection in lieu of the current deterministic inspection philosophy. While much work still is required in this area, it is an important potential application of the emerging field of risk based inspection

  6. Activities of nuclear human resource development in nuclear industry

    International Nuclear Information System (INIS)

    Tsujikura, Yonezo

    2010-01-01

    Since 2007, the JAIF (Japan Atomic Industrial Forum) had established the nuclear energy human resource development council to make analysis of the issue on nuclear human resource development. The author mainly contributed to develop its road map as a chairman of working group. Questionnaire survey to relevant parties on issues of nuclear human resource development had been conducted and the council identified the six relevant issues and ten recommendations. Both aspects for career design and skill-up program are necessary to develop nuclear human resource at each developing step and four respective central coordinating hubs should be linked to each sector participating in human resource development. (T. Tanaka)

  7. The Brazilian nuclear power manpower development programme

    International Nuclear Information System (INIS)

    Barbalho, A.R.; Spitalnik, J.; Machado, J.B.

    1983-01-01

    Since the early stages of decision making, manpower availability has been recognized to be a key factor for the implementation of Brazil's nuclear power programme. Though care has been given to securing an industrial base and financial resources, the consequences of a lack of sufficient qualified manpower could be critical for the success of the whole programme. The broad scope of the Brazilian nuclear power programme which, as a main concept, aimed at establishing in the country a complete fuel cycle industry together with the construction of nuclear power plants, added another burden to the already complex task of providing appropriate human resources when advanced technologies are introduced in a developing country. Thus, not only the work-force required for nuclear power plant operation but also that needed for plant design, component manufacture, fuel cycle plant design and operation, had to be made available in number and qualification in accordance with the standards of the nuclear industry. The feasibility of the Brazilian programme depended on a complete transfer of technology, essentially achieved through personnel training. Again, the process of manpower preparation for an efficient know-how transfer required careful planning, and the great difficulty in its implementation was the lack of reliable experience at the time. (author)

  8. Development of a quantitative risk standard

    International Nuclear Information System (INIS)

    Temme, M.I.

    1982-01-01

    IEEE Working Group SC-5.4 is developing a quantitative risk standard for LWR plant design and operation. The paper describes the Working Group's conclusions on significant issues, including the scope of the standard, the need to define the process (i.e., PRA calculation) for meeting risk criteria, the need for PRA quality requirements and the importance of distinguishing standards from goals. The paper also describes the Working Group's approach to writing this standard

  9. Nuclear medicine in developing countries

    International Nuclear Information System (INIS)

    Kremenchuzky, S.; Degrossi, O.J.

    1991-01-01

    The economic crisis through which developing countries are passing means that every field of endeavour must adapt to new realities imposed by each particular's country's situation. Public health is no exception, although it is obviously a priority field in view of the repercussions which social and economic phenomena can have on the health of a country's inhabitants. This article briefly considers ways in which nuclear medicine facilities in Argentina may be improved

  10. Sustainable development and nuclear power

    International Nuclear Information System (INIS)

    Rosen, M.

    2000-01-01

    The substantial increase in global energy consumption in coming decades will be driven principally by the developing world. Although there is some awareness on both the technical and political levels of the advantages of nuclear power, it is not a globally favored option in a sustainable energy future. This paper, after discussion of rising energy consumption, concentrates on a comparison of the environmental impacts of the available energy options. (author)

  11. Sustainable development and nuclear energy

    International Nuclear Information System (INIS)

    2000-05-01

    This report has four chapters .In the first chapter world energy statute and future plans;in the second chapter Turkey's energy statute and future plans; in the third chapter world energy outlook and in the last chapter sustainable development and nuclear energy has discussed in respect of environmental effects, harmony between generations, harmony in demand, harmony in sociapolitic and in geopolitic. Additional multimedia CD-ROM has included

  12. IAEA nuclear data for applications: Cross section standards and the reference input parameter library (RIPL)

    International Nuclear Information System (INIS)

    Capote Noy, Roberto; Nichols, Alan L.; Pronyaev, Vladimir G.

    2003-01-01

    An integral part of the activities of the IAEA Nuclear Data Section involves the development of nuclear data for a wide range of user applications. When considering low-energy nuclear reactions induced by neutrons, photons and charged particles, a detailed knowledge is required of the production cross sections over a wide energy range, spectra of emitted particles and their angular distributions. Two highly relevant IAEA data development projects are considered in this paper. Neutron reaction cross-section standards represent the basic quantities needed in nuclear reaction cross-section measurements and evaluations. These standards and the covariance matrices of their uncertainties were previously evaluated and released in 1987. However, the derived uncertainties were subsequently considered to be unrealistic low due to the effect of the low uncertainties obtained in fitting the light element standards to the R-matrix model; as a result, evaluators were forced to scale up the uncertainties to 'expected values'. An IAEA Coordinated Research Project (CRP) entitled 'Improvement of the Standard Cross Sections for Light Elements' was initiated in 2002 to improve the evaluation methodology for the covariance matrix of uncertainty in the R-matrix model fits, and to produce R-matrix evaluations of the important light element standards. The scope of this CRP has been substantially extended to include the preparation of a full set of evaluated standard reactions and covariance matrices of their uncertainties. While almost all requests for nuclear data were originally addressed through measurement programmes, our theoretical understanding of nuclear phenomena has reached a reasonable degree of reliability and nuclear modeling has become standard practice in nuclear data evaluations (with measurements remaining crucial for data testing and benchmarking). Since nuclear model codes require a considerable amount of numerical input, the IAEA has instigated extensive efforts to

  13. Nuclear anapole moment and tests of the standard model

    International Nuclear Information System (INIS)

    Flambaum, V. V.

    1999-01-01

    There are two sources of parity nonconservation (PNC) in atoms: the electron-nucleus weak interaction and the magnetic interaction of electrons with the nuclear anapole moment. A nuclear anapole moment has recently been observed. This is the first discovery of an electromagnetic moment violating fundamental symmetries--the anapole moment violates parity and charge-conjugation invariance. We describe the anapole moment and how it can be produced. The anapole moment creates a circular magnetic field inside the nucleus. The interesting point is that measurements of the anapole allow one to study parity violation inside the nucleus through atomic experiments. We use the experimental result for the nuclear anapole moment of 133 Cs to find the strengths of the parity violating proton-nucleus and meson-nucleon forces. Measurements of the weak charge characterizing the strength of the electron-nucleon weak interaction provide tests of the Standard Model and a way of searching for new physics beyond the Standard Model. Atomic experiments give limits on the extra Z-boson, leptoquarks, composite fermions, and radiative corrections produced by particles that are predicted by new theories. The weak charge and nuclear anapole moment can be measured in the same experiment. The weak charge gives the mean value of the PNC effect while the anapole gives the difference of the PNC effects for the different hyperfine components of an electromagnetic transition. The interaction between atomic electrons and the nuclear anapole moment may be called the ''PNC hyperfine interaction.''

  14. Nuclear Regulatory Authority Personnel Educating and Training within the National Nuclear Program Development

    International Nuclear Information System (INIS)

    Potapov, V.; Goryaeva, T.; Moiseenko, A.; Kapralov, E.; Museridze, A.

    2014-01-01

    International Cooperation for Nuclear Education and Knowledge: Aims: •Creation of system of continuous personnel training for EvrAzES states in the field of nuclear power applications based on the international standards; •Development of educational service export as following of export of Russian nuclear technology; • Development of educational and scientific contacts to IAEA, WNU, ENEN, ANENT, biggest scientific centers and universities of USA, EU and Asia. Directions of activities: • Education. Transfer of knowledge to new generation, to new developing countries and cooperation with the nuclear education of leading powers; • Scientific enlightening activity – students, specialists, decision makers; • Informational and analytical work

  15. Nuclear cardiology for developing countries

    International Nuclear Information System (INIS)

    Feinendegen, L.E.

    1986-01-01

    The role of nuclear medicine in developing countries must be oriented to the local needs for clinical practice, the health care of large populations and the demands for research with sometimes extremely limited resources. To help define the locally differing needs, it is stressed that nuclear medicine provides the unique opportunity to observe the body at the molecular level of organization and thus makes the body biochemically transparent. Depending on the particular diagnostic demands, complex imaging with gamma scintigraphy or emission tomography may be the only method to choose in some instances, but for others it may be an unnecessary luxury. Nuclear cardiology, with the purpose of non-invasively assessing cardiac function, myocardial perfusion and myocardial metabolism, is a particular challenge in both respects for developing countries. Given such requirements, single-probe devices with multipurpose application are less expensive than gamma cameras and promise advanced diagnostic uses. In one examination, left ventricular function, global cardio-pulmonary circulation and the general circulatory adaptation to exercise can be investigated by non-gated simultaneous blood pool measurements over four lung regions, the heart and the liver. In addition, such devices have the advantages of compactness, robustness and electronic stability. Despite enormous difficulties regarding funding, infrastructure, equipment and maintenance, developing countries should be encouraged to participate in the evolution of nuclear medicine by responding and adapting to defined needs and perhaps by maintaining at least one national centre of excellence with capacities for research and training. Funds are best secured by providing an indispensable service in co-operation with the various clinical disciplines. (author)

  16. Revision of AESJ standard 'the code of implemnetation of periodic safety review of nuclear power plants'

    International Nuclear Information System (INIS)

    Hirano, Masashi; Narumiya, Yoshiyuki

    2010-01-01

    The Periodic Safety Review (PSR) was launched in June 1992, when the Agency for Natural Resources and Energy issued a notification that required licensees to conduct comprehensive review on the safety of each existing nuclear power plant (NPP) once approximately every ten years based on the latest technical findings for the purpose of improving the safety of the NPP. In 2006, the Standard Committee of the Atomic Energy Society of Japan established the first version of 'The Standard of Implementation for Periodic Safety Review of Nuclear Power Plants: 2006'. Taking into account developments in safety regulation of PSR after the issuance of the first version, the Standard Committee has revised the Standard. This paper summarizes background on PSR, such developments are major contents of the Standard as well as the focal points of the revision. (author)

  17. Nuclear energy development in Europe

    International Nuclear Information System (INIS)

    Banal, Michel

    1975-01-01

    The present state of the nuclear development in Europe is discussed. Power plants already operating and those presently being built or to be put in operation before 1980 are considered. Only the large industrial countries near France are dealt with, the situation of the Eastern countries being too different to be envisaged in the same paper. A table gives the whole electric power production and its nuclear component for the more important industrial countries in 1974, the respective powers of the power plants operating on january 1, 1975 and those that must be in operation in 1980 and 1985, in the same countries, France, the U.K., Germany, Spain, Italy, Sweden and Belgium are successively considered [fr

  18. Development of compact nuclear simulator

    International Nuclear Information System (INIS)

    Ham, Chang Shik; Kwon, Kee Choon; Lyu, Sung Pil; Kim, Jung Taek; Kim, Young Gill; Hwang, In Ku

    1986-12-01

    Every one knows that the TMI accident resulted from the defeat of the man-machine interfacing of main control room design and of the quality of the operators. So it is necessary to develop CNS which is very efficient to train operators, operation and maintenance supervisors, maintenance personnel and inspectors of regulation committee to uderstand the dynamic transient phenomena. The following are major parts of this projects: 1. Data collection and review. 2. Make into a contract for CNS with STUDSVIK. 3. Selection of malfunction. 4. Design of console panel and modification. 5. List up measuring instruments. We design and make CNS with STUDSVIK in Sweden, and install a simulator in Nuclear Training Center of KAERI not only for fundamental training of nuclear power plant, but also safety analysis by transient analysis and NSSS design. (Author)

  19. IEEE standard for qualification of class 1E lead storage batteries for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    IEEE Std 323-1974, Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, was developed to provide guidance for demonstrating and documenting the adequacy of electrical equipment used in all Class 1E and interface systems. This standard, IEEE Std 535-1979, was developed to provide specific methods and type test procedures for lead storage batteries in reference to IEEE Std 323-1974

  20. Turkish nuclear legislation: Developments for a nuclear newcomer

    International Nuclear Information System (INIS)

    Ercan, Erinc; Schneider, Horst

    2013-01-01

    The scope of legal investigation in this article focuses on nuclear legislation with regard to siting, construction, operation and decommissioning of NPPs, taking into account the main issues of nuclear safety, security, safeguards, radiological protection and nuclear third party liability. The state of existing legislation and, furthermore, of drafts published or announced related to substantive regulations and organisational aspects are at the centre of this article. International conventions and agreements, national legislation consisting of the constitution, laws, decrees and regulations as binding norms and otherwise, directives and non-binding guides provide the legal structure for nuclear activities. The evaluation of Turkish nuclear legislation with regard to the accomplishment of the obligations under, in particular, the CNS and Euratom directives, leads finally to the perspective on the specific issues that should be addressed in the regulation of nuclear energy for Turkey's future energy needs and to ensure conformity with international standards of the International Atomic Energy Agency (IAEA) and the OECD Nuclear Energy Agency (NEA). A brief discussion of Turkish energy legislation and institutional structure is necessary, because NPPs also need a licence for electricity production under Turkey's energy legislation. The Turkish government is aiming for greater privatisation in the energy sector. The current electricity market is governed, on the one hand, by the Electricity Market Law and Electricity Market License Regulation, which requires NPPs to have an electricity production licence and, on the other hand, by specific institutions. In terms of the Electricity Market Law, private legal entities who wish to obtain an electricity generation licence must 'be established as incorporated or limited liability companies in accordance with the provisions of the Turkish Commercial Law'. The relevant institutions in Turkey's energy sector include: the Energy

  1. Nuclear power in the developing world

    International Nuclear Information System (INIS)

    Sokolov, Y.

    2005-01-01

    Current trends in the interest in nuclear power development confirm important changes in opinions around the world about nuclear power's future. Much of the expansion of nuclear power in the sustainable development scenarios takes place in developing countries. For these countries to introduce nuclear power, they need to pass through three main steps: energy planning, infrastructure development and then deployment. The paper gives an overview of the IAEA's activity in this area. In order to meeting the energy needs of developed and developing countries, developing a global vision for nuclear energy, assessing and clarifying the afford ability and acceptability requirements for large-scale nuclear energy use in the 21st century in both developed and developed countries, facilitating international cooperation in developing different types of new generation nuclear energy systems which meet these requirement, and facilitating international discussions aimed at establishing enhanced institutional system acceptable to both developed and developing countries

  2. Summary of the co-ordinated research project on development, standardization and validation of nuclear based technologies for estimating microbial protein supply in ruminant livestock for improving productivity

    International Nuclear Information System (INIS)

    Jayasuriya, M.C.N.

    1999-01-01

    A major constraint to animal production in developing countries is poor nutrition due to inadequate or fluctuating nutrient supply. This results in low rates of reproduction and production as well as increased susceptibility to disease and mortality. Microbial cells formed as a result of rumen degradation of carbohydrates under anaerobic conditions are a major source of protein for ruminants. They provide the majority of the amino acids that the host animal requires for tissue maintenance, growth and production. In roughage-fed ruminants, micro-organisms are virtually the only source of protein. Therefore, a knowledge of the microbial contribution to the nutrition of the host animal is essential to developing feed supplementation strategies for improving ruminant production. While this factor has been recognized for many years, it has been extremely difficult to determine the microbial protein contribution to ruminant nutrition. The methods generally used for determining microbial protein production depend on the use of natural microbial markers such as RNA (ribonucleic acid) and DAPA (diamino-pimelic acid) or of isotopes 35 S, 15 N or 32 P. However, these methods involve surgical intervention such as post-rumen cannulation and complex procedures that require accurate and quantitative information on both digesta and microbial marker flow. A calorimetric technique using enzymatic procedures was developed for measuring purine derivatives (PD) in urine under a Technical Contract. With knowledge of the amount of PD excreted in the urine, the microbial protein supply to the host animal can be estimated. The principle of the method is that nucleic acids leaving the rumen are essentially of microbial origin. The nucleic acids are extensively digested in the small intestine and the resulting purines are absorbed

  3. Report on ANSI/ASME nuclear air and gas treatment standards for nuclear power plants

    International Nuclear Information System (INIS)

    Fish, J.F.

    1979-01-01

    Original N Committee, N45-8, has completed and published through the approved American National Standards Institute process two Standards, N-509 and N-510. This committee has been dissolved and replaced by ASME Committee on Nuclear Air and Gas Treatment with expanded scope to cover not only air cleaning, but thermal treatment equipment. Current efforts are directed to produce Code documents rather than Standards type publications. This report summarizes changed scope, current organization and sub-committee coverage areas

  4. New nuclear technology; International developments. Review 1995

    International Nuclear Information System (INIS)

    Devell, L.; Aggeryd, I.; Hultgren, Aa.; Lundell, B.; Pedersen, T.

    1995-09-01

    A summary review of the development of new nuclear rector technology is presented in this report. Fuel cycle strategies and waste handling developments are also commented. Different plans for dismantling nuclear weapons are presented. 18 refs

  5. Project on standards on good behaviour for the civilian nuclear industry

    International Nuclear Information System (INIS)

    Strohl, Pierre; Derche, Bernard

    1995-01-01

    Nuclear energy has provoked complex and sometimes heated debates involving politic, economic, scientific and moral issues, objective data alongside irrational feelings, short-term calculations as well as concerns touching on the far-reaching of humanity and the earth. These debates go beyond national borders as it is obvious that even though each country may hold divergent positions regarding the development of nuclear energy, their effects have an international scope, and, therefore, must be taken into account by all nations, even those who do not operate nuclear installations. Whatever conclusion may be drawn from these debates, decisions on nuclear energy are always taken by the political authorities, almost always at the highest level, be it national or international. These political decisions then become the body of legal standards, particularly the regulations which govern how nuclear energy is used. The main standards are for technical and scientific quality, applying to energy resource needs, to the reasons why the nuclear industry should be developed, to radioprotection and nuclear security, to protection of the environment, to radioactive waste management, to information and consulting to the public, to international cooperation, to non-proliferation of atomic weapons and to physical protection of nuclear materials. (author)

  6. European standards and approaches to EMC in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Bardsley, D.J.; Dillingham, S.R.; McMinn, K. [AEA Technology, Dorset (United Kingdom)

    1995-04-01

    Electromagnetic Interference (EMI) arising from a wide range of sources can threaten nuclear power plant operation. The need for measures to mitigate its effects have long been recognised although there are difference in approaches worldwide. The US industry approaches the problem by comprehensive site surveys defining an envelope of emissions for the environmental whilst the UK nuclear industry defined many years ago generic levels which cover power station environments. Moves to standardisation within the European community have led to slight changes in UK approach, in particular how large systems can be tested. The tests undertaken on UK nuclear plant include tests for immunity to conducted as well as radiated interference. Similar tests are also performed elsewhere in Europe but are not, to the authors` knowledge, commonly undertaken in the USA. Currently work is proceeding on draft international standards under the auspices of the IEC.

  7. Standard rules for liability and cover for nuclear installations

    International Nuclear Information System (INIS)

    Pfaffelhuber, J.K.; Kuckuck, B.

    1980-01-01

    To afford full protection for possible victims, the authors of this article are in favour of doing away with the limitation of liability of nuclear operators presently provided under the German Atomic Energy Act, the principle of which is based on the Paris Convention and the Brussels Supplementary Convention. In support of this argument reference is made to the recent accident at Three Mile Island, trends in other national legislation towards unlimited liability as well as high safety standards in German nuclear plants. Finally, possible ways of providing unlimited liability are proposed, in particular increased insurance cover and the constitution of an interest-bearing fund in addition to State intervention in case of a major nuclear incident. (NEA) [fr

  8. Nuclear data standards - International Evaluation Co-operation volume 7

    International Nuclear Information System (INIS)

    Carlson, A.D.; Shibata, K.; Vonach, H.; Hambsch, F.J.; Chen, Z.; Hofmann, H.M.; Oh, S.Y.; Badikov, S.A.; Gai, E.V.; Pronyaev, V.G.; Smith, D.L.; Hale, G.M.; Kawano, T.; Larson, N.M.

    2006-01-01

    A Working Party on International Evaluation Co-operation was established under the sponsorship of the OECD/NEA Nuclear Science Committee (NSC) to promote the exchange of information on nuclear data evaluations, validation and related topics. Its aim is also to provide a framework for co-operative activities between members of the major nuclear data evaluation projects. This includes the possible exchange of scientists in order to encourage co-operation. Requirements for experimental data resulting from this activity are compiled. The working party determines common criteria for evaluated nuclear data files with a view to assessing and improving the quality and completeness of evaluated data. The parties to the project are: ENDF (United States), JEFF/EFF (NEA Data Bank member countries) and JENDL (Japan). Co-operation with evaluation projects of non-OECD countries is organised through the Nuclear Data Section of the International Atomic Energy Agency (IAEA). This report was issued by Subgroup 7, which was in charge of producing new evaluated neutron cross-section standards. When starting the project, there was a general consensus on the need to update these standards, as significant improvements had been made to the experimental database since 1991 when the last evaluation of these standards was performed. The present work was accomplished through efficient collaboration between a task force of the US Cross-section Evaluation Working Group (CSEWG), a Co-ordinated Research Project (CRP) of the International Atomic Energy Agency (IAEA) and Subgroup 7 of the Working Party on International Evaluation Co-operation (WPEC) of the NEA Nuclear Science Committee. Work is reported on the results of an international effort to evaluate the neutron cross-section standards. The evaluations include the H(n,n), 6 Li(n,t), 10 B(n,α), 10 B(n,α1γ), 197 Au(n,γ), 235 U(n,f) and 238 U(n,f) standard reactions. Evaluations were also produced for the non-standard 238 U(n,γ) and 239 Pu

  9. Regulatory Endorsement Activities for ASME Nuclear Codes and Standards

    International Nuclear Information System (INIS)

    West, Raymond A.

    2006-01-01

    The ASME Board on Nuclear Codes and Standards (BNCS) has formed a Task Group on Regulatory Endorsement (TG-RE) that is currently in discussions with the United States Nuclear Regulatory Commission (NRC) to look at suggestions and recommendations that can be used to help with the endorsement of new and revised ASME Nuclear Codes and Standards (NC and S). With the coming of new reactors in the USA in the very near future we need to look at both the regulations and all the ASME NC and S to determine where we need to make changes to support these new plants. At the same time it is important that we maintain our operating plants while addressing ageing management needs of our existing reactors. This is going to take new thinking, time, resources, and money. For all this to take place the regulations and requirements that we use must be clear concise and necessary for safety and to that end both the NRC and ASME are working together to make this happen. Because of the influence that the USA has in the world in dealing with these issues, this paper is written to inform the international nuclear engineering community about the issues and what actions are being addressed under this effort. (author)

  10. Development of a nuclear plant analyzer (NPA)

    International Nuclear Information System (INIS)

    De Vlaminck, M.; Mampaey, L.; Vanhoenacker, L.; Bastenaire, F.

    1990-01-01

    A Nuclear Plant Analyzer has been developed by TRACTABEL. Three distinct functional units make up the Nuclear Plant Analyser, a model builder, a run time unit and an analysis unit. The model builder is intended to build simulation models which describe on the one hand the geometric structure and initial conditions of a given plant and on the other hand command control logics and reactor protection systems. The run time unit carries out dialog between the user and the thermal-hydraulic code. The analysis unit is aimed at deep analyzing of the transient results. The model builder is being tested in the framework of the International Standard Problem ISP-26, which is the simulation of a LOCA on the Japanese ROSA facility

  11. Development of compact nuclear simulator

    International Nuclear Information System (INIS)

    Ham, Chang Shik; Kwon, Kee Choon; Lyu, Sung Phil; Kim, Jung Taek; Jung, Chul Hwan; Lee, Dong Young; Hwang, In Koo; Kim, Young Gil; Kim, Jung Soo; Park, Won Man

    1988-12-01

    Compact nuclear simulator is designed to carry out the various operational modes as real nuclear power plant, start-up, preoperational test, preheating, hot start-up, cold shutdown, power control and the operational conditions in steady and accident states. It can be used for the fundamental training of the operators, maintenance personnel, inspectors of regulatory body, system or component designers, NSSS designers, safety analysis by transient analysis and for the making questions for an operator qualifying examination and the training of research fellows in the Nuclear Training Center of KAERI. Everyone knows that the TMI accident resulted from the defect of the man-machine interface of main control room and of the quality of the operators. No proper action on the malfunction of small part in a system can cause severe accident like TMI-2 accident, so it is very important urgent to upgrade the operators' capability and to train operators for the understanding of dynamic transient phenomena in plant system. So it is necessary to develop CNS which is very efficient to train operators, operation and maintenance supervisors, maintenance personnel and inspectors of regulation committee to understand the dynamic transient phenomena. This report is the final report of KAERI-CNS project which was designed and manufactured in '85.7-'88.12. This CNS was designed and fabricated in conjunction with STUDSVIK, Sweden and installed at KAERI-NTC, and entitled KAERI-CNS. KAERI and STUDSVIK have developed math. modeling software. Many parts of CNS hardware were supplied by local firms.The followings are major parts of this project performed in '85.7-'88.12. 1.Contract with STUDSVIK for joint design and manufacturing CNS 2.Selection of malfunctions and design and manufacture of console panel 3.Manufacture of interface card and graphic display system 4.Software module development 5.S/W and H/W integration 6.Factory acceptance test and Site acceptance test 7.Running test. (Author)

  12. Ontology-based information standards development

    OpenAIRE

    Heravi, Bahareh Rahmanzadeh

    2012-01-01

    This thesis was submitted for the degree of Doctor of Philosophy and awarded by Brunel University. Standards may be argued to be important enablers for achieving interoperability as they aim to provide unambiguous specifications for error-free exchange of documents and information. By implication, therefore, it is important to model and represent the concept of a standard in a clear, precise and unambiguous way. Although standards development organisations usually provide guidelines for th...

  13. A systematic approach to the training in the nuclear power industry: The need for standard

    International Nuclear Information System (INIS)

    Wilkinson, J.D.

    1995-01-01

    The five elements of a open-quotes Systematic Approach to Trainingclose quotes (SAT) are analysis, design, development, implementation and evaluation. These elements are also present in the effective application of basic process control. The fundamental negative feedback process control loop is therefore an excellent model for a successful, systematic approach to training in the nuclear power industry. Just as standards are required in today's manufacturing and service industries, eg ISO 9000, so too are control standards needed in the training industry and in particular in the training of nuclear power plant staff. The International Atomic Energy Agency (IAEA) produced its TECDOC 525 on open-quotes Training to Establish and Maintain the Qualification and Competence of Nuclear Power Plant Operations Personnelclose quotes in 1989 and the American Nuclear Society published its open-quotes Selection, Qualification, and Training of Personnel for Nuclear Power Plants, an American National Standardclose quotes in 1993. It is important that community colleges, training vendors and organizations such as the Instrument Society of America (ISA), who may be supplying basic or prerequisite training to the nuclear power industry, become aware of these and other standards relating to training in the nuclear power industry

  14. A brief review of nuclear electronics standards . . . Past, present and future

    International Nuclear Information System (INIS)

    Larsen, R.S.

    2000-01-01

    Modular Nuclear Instrument Standards have played a key role in U. S. Department of Energy National Laboratories and similar scientific laboratories worldwide for more than three decades. The scientific and engineering efficiency and economic benefits have been well documented. Standards are constantly evolving with the introduction of new technologies and the present is a time of rapid change. This report is based on an invited talk presented at the Joint Meeting of the U.S. Nuclear Instrument Module (NIM) and European Standards for Norms in Electronics (ESONE) Standards Committees, Lyon, France, October 20, 2000. It provides a brief overview of past developments and attempts to identify areas of possible opportunities for renewed standardization efforts to meet future challenges

  15. WP1 Development of New Standardization Process

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard

    2016-01-01

    The purpose of this work package can be divided into two main areas: 1. Review of existing standardization procedures with focus on leading edge fatigue cracks and recommendations / rules for avoiding leading edge cracks. 2. Development of a new standardization process focusing on leading edge...

  16. China's High-technology Standards Development

    Institute of Scientific and Technical Information of China (English)

    2007-01-01

    There are several major technology standards, including audio video coding (AVS), automotive electronics, third generation (3G) mobile phones, mobile television, wireless networks and digital terrestrial television broadcasting, that have been released or are currently under development in China. This article offers a detailed analysis of each standard and studies their impact on China's high-technology industry.

  17. History of nuclear technology development in Japan

    Science.gov (United States)

    Yamashita, Kiyonobu

    2015-04-01

    Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident.

  18. History of nuclear technology development in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Yamashita, Kiyonobu, E-mail: yamashita.kiyonobu@jaea.go.jp [Visiting Professor, at the Faculty of Petroleum and Renewable Energy Engineering, University Teknologi Malaysia Johor Bahru 81310 (Malaysia); General Advisor Nuclear HRD Centre, Japan Atomic Energy Agency, TOKAI-mura, NAKA-gun, IBARAKI-ken, 319-1195 (Japan)

    2015-04-29

    Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident.

  19. History of nuclear technology development in Japan

    International Nuclear Information System (INIS)

    Yamashita, Kiyonobu

    2015-01-01

    Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident

  20. Mongolia and nuclear medicine development

    International Nuclear Information System (INIS)

    Onkhuudai, P.; Gonchigsuren, D.

    2007-01-01

    Full text: Mongolia is a large, landlocked and sparsely populated country in the northern part of Central Asia, located between Russia on the north and China on east, south and west. Its total land area of 1.5 millions square kilometers is about the size if India or large than Alaska, but contains only 2.3 million population or 1.3 person per square kilometer. It is 2400 kilometers long from east to west maximum of 1260 kilometers from north to south.The priority problems in health.Democratic political reforms since 1990 saw a major transformation process, which is aimed at changing the centrally planned economy to one based on market orient principles. Mongolia is in a gradual epidemiological transition from preponderance of infectious diseases towards non-communicable and degenerative diseases. Mean features of this transition are sharp decrease in mortality from infectious and parasitic diseases and sharp increase in mortality from diseases of the circulatory system and neoplasms. Life expectancy at birth was 65.7 year in 1997. Cardiovascular diseases and cancer are among the leading causes of death in Mongolia.Nuclear Medicine in Mongolia-1975-1981 Beginning First Medical Application of radioisotopes in 1972. First Rectilinear scanner. Single and dual scintillation detectors system, Thyroid Uptake Test; 1982-1999 Settlement, IAEA TC Project since 1982, Thematic Program on Health Care (RAS) since 1997, First Gamma Camera since 1997, Radioimmunological Laboratory and first Radioiodine treatment since 1982, Mongolian Society of Nuclear Medicine since 1982, Member of World and Federation of Nuclear Medicine and Biology since 1994, Member of Asia and Oceania Radionuclide Therapy Council , 2000 Development, First SPECT and Quantitative Measurement in 2000 Second Gamma Camera, New Thyroid Uptake System-Atomlab 950 PC Spectrometer Radioimmunological Laboratory replacement, Myocardial Perfusion Scintigraphy, Liver Cancer Treatment with Re-188, Radiosynovectomy with Re

  1. Prospects of nuclear power development in Romania

    International Nuclear Information System (INIS)

    Valeca, Serban Constantin; Popescu, Dan

    2003-01-01

    Nuclear Power Development in Romania of a series of projects and national programs among which the Research Development and Innovation National Plan, Rainless, Infrastructure and Standardization, Infra, Quality and Standardization, Castle, Agriculture and Food, Aural, Environment Power and Energy Resources, Territory Remedy and Transportation, Aminotris, Life and Health, Vitasan, Stimulation of Patent Applications, Invent, Information based Society, Infancies, Bio technologies, Biotech, New Materials, Micro-Nano Technologies Machinate, Aeronautical and Space Technologies, Basic Research of Socioeconomic and Cultural Significance, Cereus, International Cooperation and Partnership, Coring, Also discussed are the nuclear national organizations implication in connection with numerous international on-going programs and projects such as U E Frame Program 6, IAEA Technical Cooperation Programs, Jr Research Programs, Technical Cooperation with DOE-USA (LANL), JINR Research Programs, CERN Research Programs and the programs of other international organizations working in the field of nuclear regulations, radiation protection, radioactive waste and spent fuel management, nuclear safety at Cernavoda NPP and improvement of radiotherapy services, The paper presents the major issues of the peaceful uses of nuclear energy worldwide and in Romania as well as the objectives and strategies of the National Nuclear Plan. The objective of covering 40% of the energy demand from nuclear sources will be reached under strict compliance with the principles of sustainable socio-economic development, in a competitive market environment and strict observance of nuclear safety assurance within the international standard provisions. Finally, the paper addresses issues relating to personnel education and training, public information and acceptance, legislative aspects, the great advantages of nuclear power (small cost, implication of domestic industry in the nuclear effort, environment friendly, earth

  2. Promoting nuclear power, achieving sustainable development of nuclear industry in China

    International Nuclear Information System (INIS)

    Kang, R.

    2006-01-01

    The past 5 decades witnessed the rapid growth of China's nuclear industry. The sustained and rapid economic growth and continuous improvement of people's living standards have placed higher requirements for energy and power supplies. As a safe and clean energy source, nuclear energy has been gradually and widely accepted by the Chinese government and the public. The Chinese government has adopted the policy a ctively pushing forward the nuclear power development , set up the target to reach 40GWe of nuclear power installed capacity by 2020, accounting for about 4% of the total installed capacity in China. In this regard, this paper presents the China's nuclear program to illustrate how China is going to achieve the target. The paper is composed of 3 parts. The first part gives a review of the achievements in nuclear power in the last 20 years. The second part presents China's ''three approach'' strategy for furthering the nuclear power development: carrying out duplication projects at the existing plant sites; introducing GUI technology via international bidding; developing the brand C NP1000 , i.e. Chinese Nuclear Power lOOOMwe class, with China's own intellectual property. This part also explores the ways of securing the fuel supply for nuclear power development. The third part concludes with CNNC's ''3221'' strategy which aims at building a world class conglomerate, and expresses its sincere wish to work with the nuclear community to push the nuclear industry worldwide by strengthening international cooperation

  3. AP1000 - the new standard for nuclear power

    International Nuclear Information System (INIS)

    Lipman, Daniel S.

    2006-01-01

    Full text of publication follows: The AP1000 is the only Generation III+ reactor to receive Final Design Approval (FDA) from the Nuclear Regulatory Commission, and is expected to receive its Design Certification by the end of the year. Building on the proven features of current generation nuclear plants, the AP1000 combines experience with innovation into a design that surpasses current standards of safety and reliability. Use of passive safety features results in a simpler and more compact design that enhances safety, simplifies O and M requirements, and reduces capital and operating costs. At 1117 Mwe, the AP1000 is well suited for almost any grid system and will be fully competitive with combined-cycle gas and comparable fossil fuel plants. The AP1000 is ready to help launch a renaissance in new nuclear plant construction throughout the world. Maturity of Design: In excess of 1300 man-years and $400 million in development funding have been expended on the AP1000. It has undergone extensive, part scale testing at the system, sub-system and component level, in addition to a series of part scale integrated tests. The AP1000 is the most analyzed of the next generation reactors. Simplicity of Design/Economics: The AP1000 uses simplified and innovative passive safety systems to an unprecedented extent. Simplified passive safety systems provide reliable operation, reduced capital costs, and enhanced plant safety with large plant operating margins. The AP1000 features improved reliability through simplicity rather than addition of redundant safety trains. This simpler design is easier and less costly to operate and maintain than larger, more complex plants, while less equipment and smaller buildings translate into lower capital costs and shorter construction durations. After construction, economic benefit will be found in reduced operating and maintenance costs, largely due to reduced operating and maintenance staffing requirements. Construction aspects

  4. Integrating industry nuclear codes and standards into United States Department of Energy facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jacox, J.

    1995-02-01

    Recently the United States Department of Energy (DOE) has mandated facilities under their jurisdiction use various industry Codes and Standards developed for civilian power reactors that operate under U.S. Nuclear Regulatory Commission License. While this is a major step forward in putting all our nuclear facilities under common technical standards there are always problems associated with implementing such advances. This paper will discuss some of the advantages and problems experienced to date. These include the universal challenge of educating new users of any technical documents, repeating errors made by the NRC licensed facilities over the years and some unique problems specific to DOE facilities.

  5. Reliability programs for nuclear power plants. Regulatory standard S-98 revision 1

    International Nuclear Information System (INIS)

    2005-07-01

    The purpose of this regulatory standard is to help assure, in accordance with the purpose of the Nuclear Safety and Control Act (NSCA), that a licensee who constructs or operates a nuclear power plant (NPP) develops and implements a reliability program that assures that the systems important to safety at the plant can and will meet their defined design and performance specifications at acceptable levels of reliability throughout the lifetime of the facility. This regulatory standard describes the requirements of a reliability program for a nuclear power plant. The licensee shall implement the requirements described in this regulatory standard when a condition of a licence or other legally enforceable instrument so requires.(author)

  6. Nuclear power in the developing world

    International Nuclear Information System (INIS)

    Poneman, D.

    1982-01-01

    This book explores the increasingly urgent issue of nuclear power policies in developing countries. It examines the motives which drive nuclear policies in the developing world and explores how security and economic objectives, domestic politics, and foreign influence shape nuclear policies, enriching the analysis with examples from South American, African and Asian experiences. (author)

  7. Methodology to evaluate the site standard seismic motion for a nuclear facility

    International Nuclear Information System (INIS)

    Soares, W.A.

    1983-03-01

    An overall view of the subjects involved in the determination of the site standard seismic motion to a nuclear facility is presented. The main topics discussed are: basic priciples of seismic instrumentation; dynamic and spectral concepts; design earthquakes definitions; fundamentals of seismology; empirical curves developed from prior seismic data; avalable methodologies and recommended procedures to evaluate the site standard seismic motion. (E.G.) [pt

  8. Development of nuclear powered ship in Japan

    International Nuclear Information System (INIS)

    Sato, Hiroshi

    1976-01-01

    The development of nuclear merchant ship in Japan was started in 1955 by the establishment of Nuclear Ship Study Group, and since then, the investigation, test and research on nuclear ships have been continued. As a result, a nuclear ocean observation and supply ship was designed for trial. Researches were carried out also in JAERI and Institute for Technical Research of Ships. Meanwhile, the nuclear icebreaker Lenin was completed in Soviet Union in 1959, the nuclear ship Savannah set out for maiden voyage in U.S. in 1962, and the construction of the nuclear ore carrier Otto Hahn was prepared in FRG. Japan Nuclear Ship Development Corp. was established in 1963, and started the design and construction of the first nuclear ship in Japan, Mutsu. The basic policy in the construction is the improvement of nuclear ship technology, the securing of safety, and the use of domestic technologies as far as possible. The progress of the design, construction and test of the Mutsu is described. Owing to the problem of radiation leak, the development of nuclear ships stagnated for a while, but the nuclear plant of the Mutsu demonstrated the expected performance in the functional test, land criticality test and zero output test, and it is expected that the bud of the independent development brought up so far can bear valuable fruit. The independent development of marine nuclear reactors should be continued by selecting the way most suitable to Japan. (Kako, I.)

  9. Update to nuclear data standards for nuclear measurements. Summary report of a consultants` meeting

    Energy Technology Data Exchange (ETDEWEB)

    Wienke, H. [ed.; International Atomic Energy Agency, Vienna (Austria). Nuclear Data Section; Carlson, A. D. [National Inst. of Standards and Technology, Gaithersburg, MD (United States); Chiba, S. [Japan Atomic Energy Research Inst., Tokai (Japan); Hambsch, F. J. [Institute for Reference Materials and Measurements, Geel (Belgium); Olsson, N. [Department of Neutron Research, Uppsala Univ., Uppsala (Sweden); Smirnov, A. N. [V.G. Khlopin Radium Inst., St. Petersburg (Russian Federation)

    1997-05-01

    This document is an update of the 1991 NEANDC/INDC Nuclear Standards File (INDC(SEC)-101) to indicate the status and extension of cross section standards for the {sup 10}B(n,{alpha}) reaction in the energy region below 20 Mev; and the H(n,n), {sup 235}U9(n,f), {sup 238}U(n,f), and {sup 209}Bi(n,f) reactions for selected energy regions above 20 Mev. Refs, figs, tabs.

  10. Update to nuclear data standards for nuclear measurements. Summary report of a consultants' meeting

    International Nuclear Information System (INIS)

    Wienke, H.; Chiba, S.; Hambsch, F.J.; Olsson, N.; Smirnov, A.N.

    1997-05-01

    This document is an update of the 1991 NEANDC/INDC Nuclear Standards File (INDC(SEC)-101) to indicate the status and extension of cross section standards for the 10 B(n,α) reaction in the energy region below 20 Mev; and the H(n,n), 235 U9(n,f), 238 U(n,f), and 209 Bi(n,f) reactions for selected energy regions above 20 Mev. Refs, figs, tabs

  11. Nuclear energy and sustainable development

    International Nuclear Information System (INIS)

    Gonzalez, E.

    2005-01-01

    To sustain decent environmental conditions, it is essential to contain the emission of greenhouse gases. to a great extent, this can be achieved by reducing the almost exclusive dependence of fossil fuels for producing electricity and by championing nuclear energy and the renewable, which in the end are the least contaminating. Specifically, operation of the European nuclear fleet avoids the yearly emission of 700 million tons of CO 2 to the atmosphere. The need to combat climate change is very serious and increasingly imminent, especially if we remember that the World Health Organization has said that climate change could eventually cause 300,000 deaths. The different social players are aware of the problem. In fact, the European Union's Cabinet of Ministers approved the post-kyoto Environmental Strategy, which underlines the need to reduce CO e missions by 80% by the year 2050. It seems obvious that, in the long run, technological research and development will be fundamental pieces in the battle against environmental change and in the effort to one day provide 2,000 million people with access to electricity. (Author)

  12. Nuclear station safety standardization from a risk concept

    International Nuclear Information System (INIS)

    Veksler, L.M.

    1986-01-01

    This paper presents a method of standardizing safety-system reliability on an entirely new basis: all hypothetical accidents are approximated as groups, for each of which one proposes permissible frequencies on the basis of the risk concept. In this risk concept, the ''average person'' is a person living near a nuclear station or working in it, who is of average age, average state of health, and so on. Therefore, the risk can be found by summing the estimated individual risks for a particular group in the population followed by division by the number of people in that group. Basic assumptions in deriving permissible safety-system reliability are presented. Estimated permissible failure probabilities are given to illustrate the proposed method and to refine the initial data. The probabilities may also be used to lay down the reliability requirements for safety systems in particular nuclear stations on the risk basis

  13. Standardized safety management of AP1000 nuclear power plant

    International Nuclear Information System (INIS)

    Li Xingwen; Cao Zhiqiang; Cong Jiuyuan

    2011-01-01

    In 2002, China published and implemented the Law of the People's Republic of China on Work Safety and promulgated a series of guidelines and policies, which strengthened the safety management supervision. Standardization of safety, as another important step on safety supervision, comes after safety assesment and safety production licensing system, is also a permanent solution. Standardization of safety is a strategic, long term and fundamental work, which is also the basic access to achieving scientific safety management and increasing the inherent safety of an enterprise. Haiyang AP1000 nuclear power plant, adopting the modularized, 'open-top' and parallel construction means, overturned the traditional construction theory of installation work comes after the civil work and greatly shorten the construction period. At the same time, the notable increase of oversize module transportation and lifting and parallel construction raises higher demands for safety management. This article combines the characteristics and difficulties of safety management for Haiyang AP1000 nuclear power plant, puts forward ideas and methods for standardized safety management, and could also serve as reference to the safety management for other AP1000 projects. (authors)

  14. A call for the adoption of nuclear utility information standards

    International Nuclear Information System (INIS)

    Slone, B.J. III; Richardson, C.E.

    1993-01-01

    In December 1986, the International Organization for Standardization (SO) issued a standard for document representation, ISO 8879, open-quotes Standard Generalized Markup Languageclose quotes (SGML). The standard prescribes a method for defining documents in two parts, one containing text and the other describing its structure without reference to word processing or publishing system software or hardware. It provides a method for open-quotes marking upclose quotes information, a way to place open-quotes tagsclose quotes on pieces of information to define their purpose. The SGML is part of a group of ISO standards titled open-quotes Information Processing-Text and Office Systems.close quotes This group contains the Document Style Specification and Semantics Language, the Standard Document Interchange Format, the Standard Page Description Language, and the fonts standard. The Department of Defense (DoD) has taken a standards initiative to improve the efficiency and reliability of systems by mandating that DoD suppliers comply with specific standards when delivering technical information. The initiative is called the Computer-aided Acquisition and Logistics Support (CALS) and includes a package of standards to address engineering drawings, raster font images, vector illustrations, text, and magnetic tape format. SGML is the CALS standard for documentation representation. Other industries have adopted this standard. Several industry groups, such as the Air Transport Association, American Association of Publishers, and the Telecommunications Industry Forum, are moving ahead vigorously with their own applications of SGML. The Institute of Electrical and Electronics Engineers has also adopted the ISO standard for production of its documents. Work is under way to develop their own SGML application

  15. Comparison of ISO 9000 and recent software life cycle standards to nuclear regulatory review guidance

    International Nuclear Information System (INIS)

    Preckshot, G.G.; Scott, J.A.

    1998-01-01

    Lawrence Livermore National Laboratory is assisting the Nuclear Regulatory Commission with the assessment of certain quality and software life cycle standards to determine whether additional guidance for the U.S. nuclear regulatory context should be derived from the standards. This report describes the nature of the standards and compares the guidance of the standards to that of the recently updated Standard Review Plan

  16. Nuclear energy supports sustainable development

    International Nuclear Information System (INIS)

    Koprda, V.

    2005-01-01

    The article is aimed at acceptability, compatibility and sustainability of nuclear energy as non-dispensable part of energy sources with vast innovation potential. The safety of nuclear energy , radioactive waste deposition, and prevention of risk from misuse of nuclear material have to be very seriously abjudged and solved. Nuclear energy is one of the ways how to decrease the contamination of atmosphere with carbon dioxide and it solves partially also the problem of global increase of temperature and climate changes. Given are the main factors responsible for the renaissance of nuclear energy. (author)

  17. The transfer from nuclear development

    International Nuclear Information System (INIS)

    Smith, L.

    1993-01-01

    The Department of Energy's task of cleaning up the extensive nuclear weapons complex is of such enormous proportions that there can be no definitive solution that can be adjusted to a predictable cost. The cleanup and disposition of hazardous wastes in many cases will take thirty or more years. In the near term, the economic impact affecting the communities and large number of displaced workers is a significant concern to the Department and the nation. However, before a useful transfer of DOE land, facilities, and sites to the public for economic development can be realized, a consistent and comprehensive process of compliance with regulatory requirements needs to be established. The simultaneous pursuit of these goals creates an unprecedented challenge to the Department of Energy and the US

  18. Nuclear Regulatory Commission and its role in environmental standards

    International Nuclear Information System (INIS)

    Mattson, R.J.

    1976-01-01

    The NRC and its predecessors in the Atomic Energy Commission represent considerable experience in environmental standards setting. The Atomic Energy Act of 1954, the 1970 Supreme Court decision on Federal pre-emption of radiation standards, the Calvert Cliffs decision of 1971, the Energy Reorganization Act of 1974, and the Appendix I ''as low as reasonably achievable'' decision of 1975, to name a few of our landmarks, are representative of the scars and the achievements of being in a role of national leadership in radiation protection. The NRC, through a variety of legislative authorities, administrative regulations, regulatory guides, and national consensus standards regulates the commercial applications of nuclear energy. The purposes of regulation are the protection of the environment, public health and safety, and national security. To understand NRC's responsibilities relative to those of other Federal and state agencies concerned with environmental protection, we will briefly review the legislative authorities which underlie our regulatory program. Then we will examine the intent or the spirit of that program as embodied in our system of regulations, guides, and standards. Finally we will speak to what's happening today and what we see in the future for environmental standards

  19. Development of CSA N1600-14: general requirements for nuclear emergency management programs

    Energy Technology Data Exchange (ETDEWEB)

    Sellar, C. [Canadian Standards Association Group, Mississauga, ON (Canada); Coles, J. [Ontario Power Generation, Darlington, ON (Canada)

    2014-07-01

    CSA Group has published a new standard on General requirements for nuclear emergency management programs (CSA N1600-14). The standard establishes criteria for the emergency management programs of on- and off-site organizations to address nuclear emergencies at Canadian nuclear power plants (NPPs). It provides the requirements to develop, implement, evaluate, maintain, and continuously improve a nuclear emergency management program for prevention and mitigation, preparedness, response, and recovery from a nuclear emergency at a NPP. This paper discusses the development of the standard, and provides the key drivers, structure, scope, and outline of the standard, while highlighting key features, impacts, and benefits. (author)

  20. 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

  1. Standard development at the Human Variome Project.

    Science.gov (United States)

    Smith, Timothy D; Vihinen, Mauno

    2015-01-01

    The Human Variome Project (HVP) is a world organization working towards facilitating the collection, curation, interpretation and free and open sharing of genetic variation information. A key component of HVP activities is the development of standards and guidelines. HVP Standards are systems, procedures and technologies that the HVP Consortium has determined must be used by HVP-affiliated data sharing infrastructure and should be used by the broader community. HVP guidelines are considered to be beneficial for HVP affiliated data sharing infrastructure and the broader community to adopt. The HVP also maintains a process for assessing systems, processes and tools that implement HVP Standards and Guidelines. Recommended System Status is an accreditation process designed to encourage the adoption of HVP Standards and Guidelines. Here, we describe the HVP standards development process and discuss the accepted standards, guidelines and recommended systems as well as those under acceptance. Certain HVP Standards and Guidelines are already widely adopted by the community and there are committed users for the others. © The Author(s) 2015. Published by Oxford University Press.

  2. Development of standard components for remote handling

    International Nuclear Information System (INIS)

    Taguchi, Kou; Kakudate, Satoshi; Nakahira, Masataka; Ito, Akira

    1998-01-01

    The core of Fusion Experimental Reactor consists of various components such as superconducting magnets and forced-cooled in-vessel components, which are remotely maintained due to intense of gamma radiation. Mechanical connectors such as cooling pipe connections, insulation joints and electrical connectors are commonly used for maintenance of these components and have to be standardized in terms of remote handling. This paper describes these mechanical connectors developed as the standard component compatible with remote handling and tolerable for radiation. (author)

  3. Development of standard components for remote handling

    Energy Technology Data Exchange (ETDEWEB)

    Taguchi, Kou; Kakudate, Satoshi; Nakahira, Masataka; Ito, Akira [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-04-01

    The core of Fusion Experimental Reactor consists of various components such as superconducting magnets and forced-cooled in-vessel components, which are remotely maintained due to intense of gamma radiation. Mechanical connectors such as cooling pipe connections, insulation joints and electrical connectors are commonly used for maintenance of these components and have to be standardized in terms of remote handling. This paper describes these mechanical connectors developed as the standard component compatible with remote handling and tolerable for radiation. (author)

  4. China's nuclear energy demand and CGNPC's nuclear power development

    International Nuclear Information System (INIS)

    Rugang, Sh.

    2007-01-01

    By importation, assimilation and innovation from French nuclear power technology and experience, the China Guangdong Nuclear Power Plant Holding Company (CGNPC) has developed the capabilities of indigenous construction and operation of 1000 MW-class nuclear power plants. Through the industrial development over the past 20 years, four 1000 MW-class reactors have been built and put into commercial operation in China. CGNPC is negotiating with AREVA on the transfer of the EPR technology and the application of this technology for the Yangjang nuclear power plant depends on the negotiation results. Since China became a member of the 4. Generation International Forum, CGNPC as a large state-owned enterprise, will take an active part in the 4. generation nuclear power technology developments under the leadership of China Atomic Energy Authority, particularly it will contribute to the research work on the high-temperature gas-cooled reactor and on the super-critical water reactor

  5. IAEA Nuclear Security Human Resource Development Program

    International Nuclear Information System (INIS)

    Braunegger-Guelich, A.

    2009-01-01

    The IAEA is at the forefront of international efforts to strengthen the world's nuclear security framework. The current Nuclear Security Plan for 2006-2009 was approved by the IAEA Board of Governors in September 2005. This Plan has three main points of focus: needs assessment, prevention, detection and response. Its overall objective is to achieve improved worldwide security of nuclear and other radioactive material in use, storage and transport, and of their associated facilities. This will be achieved, in particular, through the provision of guidelines and recommendations, human resource development, nuclear security advisory services and assistance for the implementation of the framework in States, upon request. The presentation provides an overview of the IAEA nuclear security human resource development program that is divided into two parts: training and education. Whereas the training program focuses on filling gaps between the actual performance of personnel working in the area of nuclear security and the required competencies and skills needed to meet the international requirements and recommendations described in UN and IAEA documents relating to nuclear security, the Educational Program in Nuclear Security aims at developing nuclear security experts and specialists, at fostering a nuclear security culture and at establishing in this way sustainable knowledge in this field within a State. The presentation also elaborates on the nuclear security computer based learning component and provides insights into the use of human resource development as a tool in achieving the IAEA's long term goal of improving sustainable nuclear security in States. (author)

  6. Technical requirements for the ASME PRA standard for nuclear power plant applications

    International Nuclear Information System (INIS)

    Fleming, Karl N.; Bernsen, Sidney A.; Simard, Ronald L.

    2000-01-01

    In 1998 the American Society of Mechanical Engineers (ASME) formed the Committee on Nuclear Risk Management (CNRM) and a Project Team to develop a standard on PRAs for use in risk informed applications. This ASME standard is being developed to help provide an adequate level of quality in PRAs that are being used to support ASME initiatives to risk informed in-service inspection (ISI) and in-service testing (IST) of nuclear power plant components. A related need supported by the industry and the U.S. Nuclear Regulatory Commission is to reduce the level of effort that is being expended in pilot applications of risk informed initiatives to address questions about the sufficiency of quality in the supporting PRA models. The purpose of this paper is to discuss the authors' views on some of the technical issues that were encountered in the effort to develop the ASME PRA standard. Draft 12 of this standard has been issued for comment, and is currently being finalized with the aim of releasing the standard in early 2001. (author)

  7. Regional cooperation in nuclear energy development

    International Nuclear Information System (INIS)

    Chung, K.; Muntzing, L.M.

    1987-01-01

    In November 1985, PBNCC (the Pacific Basin Nuclear Cooperation Committee) was formally established. Currently six Pacific Basin members have been participating in PBNCC: Canada, Japan, South Korea, Mexico, Taiwan of Chian, and the United States of America. The People's Republic of China has sent observes to the PBNCC meetings. The technical contents of PBWCC working groups are as follows: 1. Regional cooperative for pooled spare parts of nuclear power plants and inventory management; 2. Regional cooperation in nuclear training; 3. Regional cooperation on nuclear safety; 4. Regional cooperation in Codes and Standards; 5. Regional Cooperation in public acceptance; 6. Regional cooperation on radwaste management. (Liu)

  8. 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

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

    International Nuclear Information System (INIS)

    Lee, Gihyung; Kim, Sanghyun; Lee, Gyehwi; Yoon, Yeonhwa; Song, Song Hyerim; Jeong, Jina; Byun, Jaehyung; Seo, Jonghwan

    2013-01-01

    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

  10. Iran's Nuclear Program: Recent Developments

    National Research Council Canada - National Science Library

    Squassoni, Sharon

    2006-01-01

    International Atomic Energy Agency (IAEA) inspections since 2003 have revealed almost two decades' worth of undeclared nuclear activities in Iran, including uranium enrichment and plutonium separation efforts...

  11. Iran's Nuclear Program: Recent Developments

    National Research Council Canada - National Science Library

    Squassoni, Sharon

    2007-01-01

    International Atomic Energy Agency (IAEA) inspections since 2003 have revealed two decades' worth of undeclared nuclear activities in Iran, including uranium enrichment and plutonium separation efforts...

  12. Iran's Nuclear Program: Recent Developments

    National Research Council Canada - National Science Library

    Squassoni, Sharon

    2006-01-01

    International Atomic Energy Agency (IAEA) inspections since 2003 have revealed almost two decades worth of undeclared nuclear activities in Iran, including uranium enrichment and plutonium separation efforts...

  13. Iran's Nuclear Program: Recent Developments

    National Research Council Canada - National Science Library

    Squassoni, Sharon

    2006-01-01

    International Atomic Energy Agency (IAEA) inspections since 2003 have revealed two decades worth of undeclared nuclear activities in Iran, including uranium enrichment and plutonium separation efforts...

  14. Safety culture development in nuclear electric plc

    International Nuclear Information System (INIS)

    Gibson, G.P.; Low, M.B.J.

    1995-01-01

    Nuclear Electric plc (NE) has always given the highest priority to safety. However, past emphasis has been directed towards ensuring safety thorough engineering design and hazard control procedures. Whilst the company did achieve high safety standards, particularly with respect to accidents, it was recognized that further improvements could be obtained. Analysis of the safety performance across a wide range of industries showed that the key to improving safety performance lay in developing a strong safety culture within the company. Over the last five years, NE has made great strides to improve its safety culture. This has resulted in a considerable improvement in its measured safety performance indicators, such as the number of incidents at international nuclear event scale (INES) rating 1, the number of lost time accidents and the collective radiation dose. However, despite this success, the company is committed to further improvement and a means by which this process becomes self-sustaining. In this way the company will achieve its prime goal, to ''ensure the safety of people, plant and the environment''. The paper provides an overview of the development of safety culture in NE since its formation in November 1989. It describes the research and international developments that have influenced the company's understanding of safety culture, the key initiatives that the company has undertaken to enhance its safety culture and the future initiatives being considered to ensure continual improvement. (author). 5 refs, 2 figs, 2 tabs

  15. Development of nano-roughness calibration standards

    International Nuclear Information System (INIS)

    Baršić, Gorana; Mahović, Sanjin; Zorc, Hrvoje

    2012-01-01

    At the Laboratory for Precise Measurements of Length, currently the Croatian National Laboratory for Length, unique nano-roughness calibration standards were developed, which have been physically implemented in cooperation with the company MikroMasch Trading OU and the Ruđer Bošković Institute. In this paper, a new design for a calibration standard with two measuring surfaces is presented. One of the surfaces is for the reproduction of roughness parameters, while the other is for the traceability of length units below 50 nm. The nominal values of the groove depths on these measuring surfaces are the same. Thus, a link between the measuring surfaces has been ensured, which makes these standards unique. Furthermore, the calibration standards available on the market are generally designed specifically for individual groups of measuring instrumentation, such as interferometric microscopes, stylus instruments, scanning electron microscopes (SEM) or scanning probe microscopes. In this paper, a new design for nano-roughness standards has been proposed for use in the calibration of optical instruments, as well as for stylus instruments, SEM, atomic force microscopes and scanning tunneling microscopes. Therefore, the development of these new nano-roughness calibration standards greatly contributes to the reproducibility of the results of groove depth measurement as well as the 2D and 3D roughness parameters obtained by various measuring methods. (paper)

  16. Summary of component reliability data for probabilistic safety analysis of Korean standard nuclear power plant

    International Nuclear Information System (INIS)

    Choi, S. Y.; Han, S. H.

    2004-01-01

    The reliability data of Korean NPP that reflects the plant specific characteristics is necessary for PSA of Korean nuclear power plants. We have performed a study to develop the component reliability DB and S/W for component reliability analysis. Based on the system, we had have collected the component operation data and failure/repair data during plant operation data to 1998/2000 for YGN 3,4/UCN 3,4 respectively. Recently, we have upgraded the database by collecting additional data by 2002 for Korean standard nuclear power plants and performed component reliability analysis and Bayesian analysis again. In this paper, we supply the summary of component reliability data for probabilistic safety analysis of Korean standard nuclear power plant and describe the plant specific characteristics compared to the generic data

  17. Development of molecular nuclear medicine

    International Nuclear Information System (INIS)

    Tang Ganghua

    2002-01-01

    The basic theory of molecular nuclear medicine is briefly introduced. The hot areas of molecular nuclear medicine including metabolic imaging and blood flow imaging, radioimmunoimaging and radioimmunotherapy, radioreceptor imaging and receptor-radioligand therapy, and imaging gene expression and gene radiation therapy are emphatically described

  18. New development on the nuclear publicities

    International Nuclear Information System (INIS)

    Anon.

    2001-01-01

    A series of accidents and scandals in nuclear facilities made us not only importance of nuclear safety security again but also difference between technical safety and social relief at development promoting side further large. Then, it is at an actual state that in spite of being positioned at basic electric source as well, nuclear power generation is made further delay of its development without obtaining easy understanding of peoples as shown in difficulty of its new construction and location. Under such conditions, as the nuclear relatives have efforted development of its publicity actions earnestly, it seems to take some times to realize formation of peoples' agreements. Here was groped toward some future ways by reviewing traditional nuclear publicities, through nine articles such as subjects on future nuclear publicity, efforts to nuclear publicity as a manufacturer, a required approach based on 'negative national character', a network bound between women at source and consumption sites, friendliness to the earth and human beings, a promotive action of understanding toward relief recovery and new addition on nuclear power, a report on meeting of evaluation and investigation of the nuclear publicity, toward reconstruction of nuclear publicity strategy by the Tohoku Electric Power Co., Ltd., and development on publicity action of the Hokkaido Electric Power Co., Ltd. In the 'Nuclear Ten Days' at allover of Hokkaido. (G.K.)

  19. Nuclear methods in national development

    International Nuclear Information System (INIS)

    1993-01-01

    This volume of the proceedings of the First National Conference on Nuclear Methods held at Kongo Conference Hotel Zaria from 2-4 September 1993, contains the full text of about 30 technical papers and speeches of invited dignitaries presented at the conference. The technical papers are original or review articles containing results and experiences in nuclear and related analytical techniques. Topics treated include neutron generator operation and control, nuclear data, application of nuclear techniques in environment, geochemistry, medicine, biology, agriculture, material science and industries. General topics in nuclear laboratory organization and research experiences were also covered. The papers were fully discussed during the conference and authors were requested to make changes in the manuscripts where necessary. However, they were further edited. The organizing committee wishes to thank all authors for their presentation and cooperation in submitting their manuscripts promptly and the participants for their excellent contribution during the conference

  20. Contributions of the ORNL piping program to nuclear piping design codes and standards

    International Nuclear Information System (INIS)

    Moore, S.E.

    1975-11-01

    The ORNL Piping Program was conceived and established to develop basic information on the structural behavior of nuclear power plant piping components and to prepare this information in forms suitable for use in design analysis and codes and standards. One of the objectives was to develop and qualify stress indices and flexibility factors for direct use in Code-prescribed design analysis methods. Progress in this area is described

  1. Working group 2: regulatory and standards development

    Energy Technology Data Exchange (ETDEWEB)

    Bunch, Chad; Lee, Shu; Peters, Mike; Parsonage, Kevin; Saad, Ziad

    2011-07-01

    This second workshop explored regulatory standards and developments in the pipeline industry. New methods of improved damage prevention for regulators and pipelines to implement were presented. First, incident trends were discussed, using incident analysis to identify the possible causes and solutions of incidents. The determination of realistic goals was attempted. Next, leak detection was discussed with the presentation of current work in annex E which will form part of the new CSA Z662 standard in a few years time. New testing methods such as external methods of leak detection were studied. A third presentation showed the recent development in overpressure protection with reference to the new annex M incorporated in the CSA Z662-11 standard. The last presentation introduced the topic of public safety issues associated with CO2 pipelines with regard to different failure scenarios and the appropriate emergency responses.

  2. The nuclear power development policy of Taipower

    International Nuclear Information System (INIS)

    Chen, J.H.

    1987-01-01

    Taipower began its nuclear power epoch in 1978 when the first unit of its First Nuclear Power Station was synchronized to the system on November 1977. At present, Taipower has six units installed in three nuclear power plants, totalling 5144 MW in operation. These units are the mainstay of the 16,600 MW system and have played a significant role in the energy supply of Taiwan. This paper will firstly give a brief overview of Taipower's system, then introduce Taipower's nuclear power policies within the frame of issues on nuclear power economy, nuclear fuel cycle management, nuclear safety and environmental concerns, radioactive waste management, public communications and personnel training. At last, this paper will present the prospect for future nuclear power development in Taiwan with reference to the above discussion. (author)

  3. Development of a quality management system for Brazilian nuclear installations

    International Nuclear Information System (INIS)

    Kibrit, Eduardo; Zouain, Desiree Moraes

    2005-01-01

    The present work is a proposal for developing a quality management system for Brazilian nuclear installations, based on applicable standards. The standard ISO 9001:2000 [4] establishes general requirements for the implementation of a quality management system in all kinds of organizations. The standard IAEA 50-C/SG-Q [1] establishes general requirements for the implementation of a quality assurance system in nuclear installations. The standard CNEN-NN- 1.16 [5] establishes the regulating requirements for the quality assurance systems and programs of nuclear installations, for licensing and authorization for operation of these installations in Brazil. The revision of standard IAEA 50-C/SG-Q [1], to be replaced by IAEA DS 338 [2] and IAEA DPP 349 [3], introduces the concept of 'Integrated Management System' for the nuclear area, in preference to the concept of 'Quality Assurance'. This approach is incorporated with the current tendency, because it guides the system to manage, in an integrated way, the requirements of quality, safety, health, environment, security and economics of the installation. The results of the characterization of the quality management systems established in the applicable standards are presented, with the determination of the common and conflicting points among them. Referring data to quality assurance program/quality management system in some nuclear installations of IAEA Member States are also presented. (author)

  4. Nuclear international trade: The point of view of the countries in nuclear development

    International Nuclear Information System (INIS)

    Manovil, R.M.

    1986-01-01

    To establish unified legal rules to regulate the international nuclear trade it is hard to compatibilize the social, economic, political and financial values and interests. An attempt to codify the flow of nuclear supplies and services might be regarded by the developing countries as an attempt to impose upon them a 'minimum standard'. This appears often as the benefit of the enterprises of the industrialized countries. (CW) [de

  5. Development of standardized radioactive 46Sc solution

    International Nuclear Information System (INIS)

    Du Hongshan; Jia Zhang; Yu Yiguang; Sun Naiyao

    1988-01-01

    A method of preparation of standardized radioactive 46 Sc solution is developed. The separation of 46 Sc, the composition of 46 Sc solution and its stability, and radioactivity measurement of 46 Sc are systematically studied. The results obtained in the study and in the applications in many laboratories have shown that our method is effective and reliable

  6. Secondary standard dosimetry laboratories: Development and trends

    International Nuclear Information System (INIS)

    1985-08-01

    This publication describes the work of the IAEA and the WHO in the establishment of a network of Secondary Standard Dosimetry Laboratories. Membership in the SSDL network has now risen to about 50 laboratories, of which 36 are in developing countries

  7. Development of standard reference samples for diffractometry

    International Nuclear Information System (INIS)

    Galvao, Antonio de Sant'Ana

    2011-01-01

    In this work, samples of standard reference materials for diffractometry of polycrystals were developed. High-purity materials were submitted to mechanical and thermal treatments in order to present the adequate properties to be used as high-quality standard reference materials for powder diffraction, comparable to the internationally recognized produced by the USA National Institute of Standards and Technology NIST, but at lower costs. The characterization of the standard materials was performed by measurements in conventional X-ray diffraction diffractometers, high resolution neutron diffraction and high-resolution synchrotron diffraction. The lattice parameters were calculated by extrapolation of the values obtained from each X-ray reflection against cos 2 θ by the Least-Squares Method. The adjustments were compared to the values obtained by the Rietveld Method, using program GSAS. The materials thus obtained were the α-alumina, yttrium oxide, silicon, cerium oxide, lanthanum hexaboride and lithium fluoride. The standard reference materials produced present quality similar or, in some cases, superior to the standard reference materials produced and commercialized by the NIST. (author)

  8. Nuclear power development in Japan

    International Nuclear Information System (INIS)

    Mishiro, M.

    2000-01-01

    This article describes the advantages of nuclear energy for Japan. In 1997 the composition of the total primary energy supply (TPES) was oil 52.7%, coal 16.5%, nuclear 16.1% and natural gas 10.7%. Nuclear power has a significant role to play in contributing to 3 national interests: i) energy security, ii) economic growth and iii) environmental protection. Energy security is assured because a stable supply of uranium fuel can be reasonably expected in spite of dependence on import from abroad. Economic growth implies the reduction of energy costs. As nuclear power is capital intensive, the power generation cost is less affected by the fuel cost, therefore nuclear power can realize low cost by favoring high capacity utilization factor. Fossil fuels have substantial impacts on environment such as global warming and acid rain by releasing massive quantities of CO 2 , so nuclear power is a major option for meeting the Kyoto limitations. In Japan, in 2010 nuclear power is expected to reach 17% of TPES and 45% of electricity generated. (A.C.)

  9. Nuclear power and economic development: India

    International Nuclear Information System (INIS)

    Srinivasan, T.N.

    1983-01-01

    It is useful in discussing proliferation problems linked to nuclear power to examine the history of nuclear power in India and the development of her capacity to produce heavy water, fabricate fuel rods, and process spent fuel. The author presents the few published economic analyses of the role of nuclear energy in India's development, then discusses issues relating to the Non-Proliferation Treaty (NPT) from India's point of view. The chapter concludes with some proposals for making the NPT more attractive so that nonsignatories will reconsider their position. One step should be to instill greater confidence that scientists in nonweapons states will be able to pursue their research in nuclear physics and that their electricity planners will have access to nuclear technology if they find it economically viable. A dramatic step toward nuclear disarmament will be the voluntary renunciation of nuclear weapons by one or more of the weapons states. 18 references, 2 tables

  10. Nuclear power development in the Far East

    Energy Technology Data Exchange (ETDEWEB)

    Hsu, W C [Pacific Enegineers and Constructors Ltd., Taipei, Taiwan (China)

    1990-06-01

    The nuclear power development of selected Far Eastern countries is presented in this paper. This paper consists of three sections. Section 1 describes the current power/nuclear power status of Japan, South Korea, Taiwan and China. The first three countries already have operating nuclear power units, while mainland China will have a nuclear power commissioned this year according to their schedule. The power development plan for these countries is also presented. All of them have included nuclear power as part of their energy sources for the future. Section 2 briefly describes the nuclear power industry in these countries which basically covers design, manufacturing and R and D activities. Public Acceptance programs (PAPs) will play a significant role in the future of nuclear power. Section 3 discusses the PAPs of these countries. (author)

  11. Nuclear energy development and national economy

    International Nuclear Information System (INIS)

    Fukami, Hiroaki

    1982-01-01

    The utilization and development of nuclear power in Japan are now advanced on the basis of a fact that nuclear power generation has taken root in the country. The scale of nuclear power generation is currently a total of 22 power plants with aggregate capacity over 15,500 MW, 16% of the total power generation. There are still two alternate arguments: i.e. whether nuclear energy can be a complete substitute of petroleum or not, because the consumption of petroleum is necessary for the fuel cycle. Due to the rise of petroleum price, the nuclear power generation is now positively economical. On the other hand, the promotion of nuclear power can lead to the saving in foreign currency. While the economy in nuclear power is through the use of LWRs presently, the research and development efforts in ATRs, FBRs, etc. are essential for the future. (Mori, K.)

  12. Nuclear power development in the Far East

    International Nuclear Information System (INIS)

    Hsu, W.C.

    1990-01-01

    The nuclear power development of selected Far Eastern countries is presented in this paper. This paper consists of three sections. Section 1 describes the current power/nuclear power status of Japan, South Korea, Taiwan and China. The first three countries already have operating nuclear power units, while mainland China will have a nuclear power commissioned this year according to their schedule. The power development plan for these countries is also presented. All of them have included nuclear power as part of their energy sources for the future. Section 2 briefly describes the nuclear power industry in these countries which basically covers design, manufacturing and R and D activities. Public Acceptance programs (PAPs) will play a significant role in the future of nuclear power. Section 3 discusses the PAPs of these countries. (author)

  13. Engineering experiences through nuclear power development in Japan

    International Nuclear Information System (INIS)

    Uchida, Hideo

    2004-01-01

    This keynote paper deals with: energy issues and nuclear power development in Japan, problems of radiation protection, licensing and safety regulations, research on LOCA and ECCS, stress corrosion cracks related to pressure vessels, nuclear fuel failures, steam generators, incidents, waste management and fuel cycle facilities. In conclusion it is stated that: on order to cope with global matters vitally affecting the electricity generation, taking into consideration Japanese specific energy issues, the nuclear power development has been an indispensable policy of Japan. In order to proceed with further development of nuclear power plants, it is necessary to obtain proper understanding by the public, showing assurance of the safety and reliable operation of nuclear power plants through daily plant operation. The nuclear safety issues should be considered from a global point of view. It is necessary to establish common safety standards which could harmonize the safety level of nuclear power plants in the world. The safety goal concerning severe accidents should be established as an internationally agreeable one. Japan has accumulated highly technological experience in maintenance of nuclear power plants. It is believed that the cumulative experiences in Japan can contribute to the further improvement of safety of nuclear power plants throughout the world, and for this aim a mutual information exchange should be encouraged

  14. Impact of New Radiation Safety Standards on Licensing Requirements of Nuclear Power Plant

    International Nuclear Information System (INIS)

    Strohal, P.; Subasic, D.; Valcic, I.

    1996-01-01

    As the outcomes of the newly introduced safety philosophies, new and more strict safety design requirements for nuclear installation are expected to be introduced. New in-depth defence measures should be incorporated into the design and operation procedure for a nuclear installation, to compensate for potential failures in protection or safety measures. The new requirements will also apply to licensing of NPP's operation as well as to licensing of nuclear sites, especially for radioactive waste disposal sites. This paper intends to give an overview of possible impacts of new internationally agreed basic safety standards with respect to NPP and related technologies. Recently issued new basic safety standards for radiation protection are introducing some new safety principles which may have essential impact on future licensing requirements regarding nuclear power plants and radioactive waste installations. These new standards recognize exposures under normal conditions ('practices') and intervention conditions. The term interventions describes the human activities that seek to reduce the existing radiation exposure or existing likelihood of incurring exposure which is not part of a controlled practice. The other new development in safety standards is the introduction of so called potential exposure based on the experience gained from a number of radiation accidents. This exposure is not expected to be delivered with certainty but it may result from an accident at a source or owing to an event or sequence of events of a probabilistic nature, including equipment failures and operating errors. (author)

  15. Let nuclear technology create new brilliancy for china's sustainable development

    International Nuclear Information System (INIS)

    Du Xiangwan

    2008-01-01

    This paper summarizes the development and application directions of nuclear technology, including five aspects: nuclear technology and energy nuclear technology and medicine, nuclear anclear analysis technology, nuclear radiation technology, astronautics and voyage's nuclear power, etc. The paper discusses the importance of them to sustainable development and generalizes the development trilogy of nuclear science and technology and its prospect. (authors)

  16. Standards development for fiber optic spectroscopic components for adverse environments

    Science.gov (United States)

    Saggese, Steven J.; Greenwell, Roger A.

    1994-09-01

    Optical fiber sensors are finding wider use in all types of applications involving adverse environments, including exposure to radiation. In order to effectively characterize and evaluate the performance of a fiber sensor system for a radiation environment, such as within a nuclear power plant or in a radioactive waste storage/disposal facility, it is beneficial to develop standard test procedures. Science & Engineering Associates (SEA) has developed two such procedures for the American Society for Testing and Materials (ASTM) which address the testing of optical fibers for remote Raman spectroscopic and broadband sensor applications in a steady state radiation environment.

  17. Development of smart nuclear instrumentation for reactors

    International Nuclear Information System (INIS)

    Chaganty, S.P.; Das, D.; Bhatnagar, P.V.; Das, A.; Sreedharan, Preetha; Kataria, S.K.

    2001-01-01

    Variety of nuclear instruments are required for different applications in reactors such as reactor start-up, reactor protection and regulating system, area monitoring, failed fuel detection, stack monitoring etc. Attempts are made to develop a standardized microcomputer based hardware for configuring different types of instruments. PC architecture is chosen due to easy availability of components/boards and software. These instruments have dual redundant Network Interface Cards for connecting to a Primary Radiation Data LAN which in turn can be connected to Plant Information Bus through Gateways. These SMART instruments can be tested/calibrated through specific commands from remote computers connected over the LAN. This paper describes the various issues involved and the design details. (author)

  18. N. Sarkosy calls for a global development of civil nuclear

    International Nuclear Information System (INIS)

    Anon.

    2010-01-01

    The President Sarkosy called to develop the nuclear power and ask to international financing institutions to resolutely engage in financing nuclear energy power. Mister Yukiya Amano, chief of IAEA declared that:' nuclear power can make a major contribution to economic development and help mitigate climate change'. Mister Manuel Barroso, president of European Commission, said: 'We are confident that the new economy of the European Union will involve the decarbonization of our electricity supply and has announced an initiative to raise European safety standards and international safety and make them legally binding throughout the world '. Mister Daniel Poneman, U.S. Assistant Secretary of Energy said that the United States is working domestically to reinvigorate the nuclear industry and ensure that alongside all countries can have access to nuclear energy for peaceful purposes, in a manner that minimizes proliferation. (N.C.)

  19. Nuclear energy in a sustainable development perspective

    International Nuclear Information System (INIS)

    Bertel, E.; Wilmer, P.

    2001-01-01

    The characteristics of nuclear energy are reviewed and assessed from a sustainable development perspective highlighting key economic, environmental and social issues, challenges and opportunities relevant for energy policy making.. The analysis covers the potential role of nuclear energy in increasing the human and man-made capital assets of the world while preserving its natural and environmental resource assets as well as issues to be addressed in order to enhance the contribution of nuclear energy to sustainable development goals. (author)

  20. Promoting nuclear medicine in developing countries

    International Nuclear Information System (INIS)

    Ganatra, R.; Nofal, M.

    1986-01-01

    After a short review of the applications of nuclear medicine in diagnosis and treatment of diseases or in medical research the ways and the means of IAEA's support in helping developing countries to set up nuclear medicine capabilities in their hospitals are described. Some trends and new directions in the field of nuclear medicine and the problems related to the implementation of these techniques in developing countries are presented

  1. Current status of nuclear power development

    International Nuclear Information System (INIS)

    Dias, P.M.

    1994-01-01

    Nuclear power is not a viable energy source for Sri Lanka at present because of a number of reasons, the main reason being the non-availability of small and economically viable nuclear power plants. However several suppliers of nuclear power plants are in the process of developing small and medium power plants (SMPRs) which could be economically competitive with coal. The paper deals with past and future trends of nuclear power plants, their economics and safety. It also deals with environmental effects and public acceptance of nuclear power plants

  2. Nuclear program of Iran plans and development

    International Nuclear Information System (INIS)

    2016-01-01

    Described are the history of nuclear energy planning in Iran and the development of the Bushehr Nuclear Power Plant (BNPP-1) project and its impact on the competency building in national companies, nuclear safety infrastructure, training activities, public awareness and acceptance. The activities of Nuclear Engineering Department is also presented. In order to enhance technical support services to BNPP1 and also to use capabilities of other companies in the international arena and in line with safe and reliable operation of Bushehr Nuclear Power Plant, NPPD/TAVANA Company has attempted to make contact with many companies outside the country

  3. Principles and objectives for the operation and support of standard nuclear plants

    International Nuclear Information System (INIS)

    1994-08-01

    This publication provides the guiding principles and objectives for the operation and support of standard nuclear plants. They are the basis for designing the processes to operate and support the new plants and to estimate the staffing options. INPO has facilitated and coordinated the development of these principles and objectives under the industry's Strategic Plan for Building New Nuclear Power Plants. The industry's plan, first published in 1990, designates INPO as the lead in achieving the following goals: 1. Establish an institutional framework and approach to implement and maintain a model for life-cycle standardization of a family of plants. 2. Develop standardization objectives and selected standardized function and process descriptions to provide a basis for uniformity in appropriate aspects of the organizational structure; administrative controls; and construction, startup, operating, and maintenance practices. 3. Develop an approach to maintain the standard design and design intent as well as standardized operational approaches in all units within a family of plants over their lifetimes. This document supports these goals. Twelve guiding principles are followed by descriptions of four functions, and after that eight processes with their associated objectives

  4. Methodology to evaluate the site standard seismic motion to a nuclear facility

    International Nuclear Information System (INIS)

    Soares, W.A.

    1983-01-01

    For the seismic design of nuclear facilities, the input motion is normally defined by the predicted maximum ground horizontal acceleration and the free field ground response spectrum. This spectrum is computed on the basis of records of strong motion earthquakes. The pair maximum acceleration-response spectrum is called the site standard seismic motion. An overall view of the subjects involved in the determination of the site standard seismic motion to a nuclear facility is presented. The main topics discussed are: basic principles of seismic instrumentation; dynamic and spectral concepts; design earthquakes definitions; fundamentals of seismology; empirical curves developed from prior seismic data; available methodologies and recommended procedures to evaluate the site standard seismic motion. (Author) [pt

  5. Register of international standard NP on IT based wireless application in nuclear power plants

    International Nuclear Information System (INIS)

    Koo, I. S.; Hong, S. B.; Cho, I. W.; Choi, Y. S.; Lee, J. C.

    2011-04-01

    DC draft of standard technical report for wireless applications in NPP is developed, which is a Korean IT technologies. Wireless technologies are forwardwd to converging technologies nuclear and IT area. These technologies are supported to reduce vulnerability against cyber attacks and are forwarded to international standards which met with the nuclear environment requirements. DC draft of standard technical report is provided and circulated. Korean experts participate in Plenary meeting for IEC TC45/SC45A and intermediate meeting for IEC SC45A/WGA3 and 9. Korean expert takes the chair of wireless session at ANS winter conference. Visible light communication is experimented for feasibility study on reducing vulnerability against cyber attacks. VLC is capable of robust wireless communication against cyber attacks. This is suggested to describe a method for technical report. Issue DTR for wireless applications in NPP in 2012

  6. Sustainable development and nuclear power

    International Nuclear Information System (INIS)

    1997-11-01

    Although there is an awareness on both the technical and political levels of the advantages of nuclear power, it is not a globally favoured option in a sustainable energy future. A sizeable sector of public opinion remains hesitant or opposed to its increased use, some even to a continuation at present levels. With various groups calling for a role for nuclear power, there is a need openly and objectively to discuss the concerns that limit its acceptance: the perceived health effects, the consequences of severe accidents, the disposal of high level waste and nuclear proliferation. This brochure discusses these concerns, and also the distinct advantages of nuclear power. Extensive comparisons with other energy sources are made

  7. Sustainable development and nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-01

    Although there is an awareness on both the technical and political levels of the advantages of nuclear power, it is not a globally favoured option in a sustainable energy future. A sizeable sector of public opinion remains hesitant or opposed to its increased use, some even to a continuation at present levels. With various groups calling for a role for nuclear power, there is a need openly and objectively to discuss the concerns that limit its acceptance: the perceived health effects, the consequences of severe accidents, the disposal of high level waste and nuclear proliferation. This brochure discusses these concerns, and also the distinct advantages of nuclear power. Extensive comparisons with other energy sources are made. Figs, tabs.

  8. The third generation of nuclear power development

    International Nuclear Information System (INIS)

    Townsend, H.D.

    1987-01-01

    Developing nations use the nuclear plant option to satisfy important overall national development objectives, in addition to providing economical electric power. The relative importance of these two objectives changes as the nuclear program develops and the interim milestones are reached. This paper describes the three typical stages of nuclear power development programs. The first and the second generations are development phases with the third generation reaching self sufficiency. Examples are presented of European and Far East countries or regions which have reached of are about to step into the third generation phase of development. The paper concludes that to achieve the objective of a nuclear power self sufficiency, other than merely filling the need of economical electric power, a careful technology transfer plan must be followed which sets realistic and achievable goals and establishes the country as a reliable and technically competent member of the nuclear power industry. (author)

  9. Third generation of nuclear power development

    International Nuclear Information System (INIS)

    Townsend, H.D.

    1988-01-01

    Developing nations use the nuclear plant option to satisfy important overall national development objectives, in addition to providing economical electric power. The relative importance of these two objectives changes as the nuclear program develops and the interim milestones are reached. This paper describes the three typical stages of nuclear power development programs. The first and the second generations are development phases with the third generation reaching self sufficiency. Examples are presented of European and Far East countries or regions which have reached or are about to step into the third generation phase of development. The paper concludes that to achieve the objectives of a nuclear power self sufficiency, other than merely filling the need of economical electric power, a careful technology transfer plan must be followed which sets realistic and achievable goals and establishes the country as a reliable and technically competent member of the nuclear power industry

  10. BATAN Activities in Developing Nuclear Knowledge Management

    International Nuclear Information System (INIS)

    Darmawati, S.

    2016-01-01

    Full text: BATAN (National Atomic Energy Agency of Indonesia) was established in 1964, and after the issuance of Law 10 of 1997 it become National Nuclear Energy Agency. During the last seven years, BATAN has suffered the loss of many of its valuable human resources due to the zero-growth policy of the government in recruiting new staffs. The uncertain future of nuclear power programme in Indonesia has also reduced the interest of young generation to study nuclear related subjects, resulting in the closing of several departments in universities that once offered nuclear sciences as subject of studies. These situations triggered management of BATAN to develop various efforts to keep nuclear knowledge exist and disseminate among BATAN itself, university students, and public as a whole. BATAN has in recent years established higher school of nuclear technology and organized various nuclear related training programmes, and also in cooperation with other governmental organizations establish nuclear zones, nuclear information centres and nuclear corners in public as well as in high school areas throughout Indonesia. All these efforts are aimed to transfer and preserve nuclear knowledge for the better future of the applications of nuclear science and technology in Indonesia. (author

  11. Development of fire protection standards for the EPR project

    International Nuclear Information System (INIS)

    Frank, H.J.; Kaercher, M.; Wittmann, R.

    2000-01-01

    In 1989 Framatome and Siemens decided by setting up their joint subsidiary NPI (Nuclear Power International) to co-operate in designing a new European Pressurised Water Reactor, the EPR. French and German utilities decided to participate in this project. In parallel to the co-operation on supplier's and utility's side, the French and German safety authorities and safety experts wanted to work closely together in order to harmonise and further develop the outstanding safety standards in France and Germany. An organisation has been set up to elaborate common codes related to the EPR design, at the level of the French design and construction rules (RCC) of the German KTA safety standards and DIN standards for nuclear technology, the so-called EPR technical codes (ETC). In this context the decision was made to develop a new fire protection code, the ETC-F, which should be harmonised between France and Germany. The article gives an insight in the developing process of the ETC-F and an outlook on existing and perhaps further national activities. (orig.) [de

  12. The role of food standards in development

    DEFF Research Database (Denmark)

    Trifkovic, Neda

    The thesis consists of three papers based on the original data collected through fieldwork in Mekong River Delta, Vietnam. It is focused on understanding the implications of modern agri-food sector restructuring for farmers in developing countries. The thesis particularly looks at (i) the impact...... — for Middle-Class Farmers, joint with Henrik Hansen, estimates the impact of food standards on farmers’ wellbeing using the data from the Vietnamese pangasius sector. In this paper we estimate both the average effect as well as the effects on poorer and richer farmers using the instrumental variable quantile...... regression. We find that large returns from food standards are possible but the gains are substantial only for the ‘middle-class’ farmers, occupying the range between 50% and 85% quantiles of the expenditure distribution. Overall, this result points to an exclusionary impact of food standards for the poorest...

  13. Future development of nuclear energy systems

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    Nuclear energy development in Japan has passed about 30 years, and reaches to a step to supply about 35 % of total electric power demand. However, together with globalization of economic and technical development, its future progressing method is required for its new efforts. Among such conditions, when considering a state of future type nuclear energy application, its contribution to further environmental conservation and international cooperation is essential, and it is required for adoption to such requirement how it is made an energy source with excellent economics.The Research Committee on 'Engineering Design on Nuclear Energy Systems' established under recognition in 1998 has been carried out some discussions on present and future status of nuclear energy development. And so forth under participation of outer specialists. Here were summarized on two year's committee actions containing them and viewpoints of nuclear industries, popularization of nuclear system technology, and so forth. (G.K.)

  14. Nuclear desalting potential for developing countries

    International Nuclear Information System (INIS)

    1969-01-01

    Nuclear power, having proved its success in large units, now poses problems for application in developing countries. Possible solutions for electricity supply, desalting systems and agricultural development are suggested by Joseph R. Wilson, of the Agency's Division of Nuclear Power and Reactors. His article is adapted from a lecture to students in Switzerland. (author)

  15. The Korean nuclear ODA policy development

    International Nuclear Information System (INIS)

    Lee, Seung Hyun; Min, Kim Yoo; Park, Young Il

    2012-01-01

    Korean nuclear Official Development Assistance (ODA) is established with support from institutes such as the Korea International Cooperation Agency (KOICA) and the Korea Atomic Energy Research Institute (KAERI). KOICA's grant aid mainly made through the activities including IAEA's training program, and KAERI currently runs the inter-regional education and training cooperation called Asian Network for Education in Nuclear Technology(ANENT) which aimed to achieve the goal of encouraging web based education training network via cooperation with IAEA. Yet now these programs are focusing more on assisting nuclear infrastructure rather than highlighting nuclear education and training. This paper aims to, first, do a self-evaluation about the Korean ODA policy; second, to study the transition of the international nuclear atmosphere; and third, by apprehending the trend of the subjects of Korean nuclear ODA policy, to discuss the overall appropriate trajectory of Korean nuclear ODA

  16. Technological development in the nuclear area: nuclear power production

    International Nuclear Information System (INIS)

    Lima, Jose Mendonca de.

    1991-01-01

    The factors and obstacles that influence the progress and regress of nuclear power presently are evaluated. The international policies of the industrial conglomerates and the hegemonic countries in the nuclear area are described. In the particular case of Brazil, it was tried to identify the obstacles which must be removed so that the country can reach development in this field. 35 refs., 9 figs., 9 tabs

  17. Draft CSA standard on environmental risk assessments at class I nuclear facilities and uranium mines and mills

    International Nuclear Information System (INIS)

    Hart, D.; Garisto, N.; Parker, R.; Kovacs, R.; Thompson, B.

    2012-01-01

    The Canadian Standards Association (CSA) is preparing a draft Standard on environmental risk assessments (ERAs) at Class I nuclear facilities and uranium mines and mills (CSA N288.6). It is being prepared by a technical subcommittee of the CSA N288 Technical Committee, including experts from across the nuclear industry, government and regulatory authorities, and environmental service providers, among others. It addresses the design, implementation, and management of environmental risk assessment programs, and is intended to standardize practice across the industry. This paper outlines the scope of the draft Standard and highlights key features. It is under development and subject to change. (author)

  18. Development of nuclear safety issues program

    Energy Technology Data Exchange (ETDEWEB)

    Cho, J. C.; Yoo, S. O.; Yoon, Y. K.; Kim, H. J.; Jeong, M. J.; Noh, K. W.; Kang, D. K

    2006-12-15

    The nuclear safety issues are defined as the cases which affect the design and operation safety of nuclear power plants and also require the resolution action. The nuclear safety issues program (NSIP) which deals with the overall procedural requirements for the nuclear safety issues management process is developed, in accordance with the request of the scientific resolution researches and the establishment/application of the nuclear safety issues management system for the nuclear power plants under design, construction or operation. The NSIP consists of the following 4 steps; - Step 1 : Collection of candidates for nuclear safety issues - Step 2 : Identification of nuclear safety issues - Step 3 : Categorization and resolution of nuclear safety issues - Step 4 : Implementation, verification and closure The NSIP will be applied to the management directives of KINS related to the nuclear safety issues. Through the identification of the nuclear safety issues which may be related to the potential for accident/incidents at operating nuclear power plants either directly or indirectly, followed by performance of regulatory researches to resolve the safety issues, it will be possible to prevent occurrence of accidents/incidents as well as to cope with unexpected accidents/incidents by analyzing the root causes timely and scientifically and by establishing the proper flow-up or remedied regulatory actions. Moreover, the identification and resolution of the safety issues related to the new nuclear power plants completed at the design stage are also expected to make the new reactor licensing reviews effective and efficient as well as to make the possibility of accidents/incidents occurrence minimize. Therefore, the NSIP developed in this study is expected to contribute for the enhancement of the safety of nuclear power plants.

  19. Development of nuclear safety issues program

    International Nuclear Information System (INIS)

    Cho, J. C.; Yoo, S. O.; Yoon, Y. K.; Kim, H. J.; Jeong, M. J.; Noh, K. W.; Kang, D. K.

    2006-12-01

    The nuclear safety issues are defined as the cases which affect the design and operation safety of nuclear power plants and also require the resolution action. The nuclear safety issues program (NSIP) which deals with the overall procedural requirements for the nuclear safety issues management process is developed, in accordance with the request of the scientific resolution researches and the establishment/application of the nuclear safety issues management system for the nuclear power plants under design, construction or operation. The NSIP consists of the following 4 steps; - Step 1 : Collection of candidates for nuclear safety issues - Step 2 : Identification of nuclear safety issues - Step 3 : Categorization and resolution of nuclear safety issues - Step 4 : Implementation, verification and closure The NSIP will be applied to the management directives of KINS related to the nuclear safety issues. Through the identification of the nuclear safety issues which may be related to the potential for accident/incidents at operating nuclear power plants either directly or indirectly, followed by performance of regulatory researches to resolve the safety issues, it will be possible to prevent occurrence of accidents/incidents as well as to cope with unexpected accidents/incidents by analyzing the root causes timely and scientifically and by establishing the proper flow-up or remedied regulatory actions. Moreover, the identification and resolution of the safety issues related to the new nuclear power plants completed at the design stage are also expected to make the new reactor licensing reviews effective and efficient as well as to make the possibility of accidents/incidents occurrence minimize. Therefore, the NSIP developed in this study is expected to contribute for the enhancement of the safety of nuclear power plants

  20. Nuclear Security, Disarmament and Development

    Science.gov (United States)

    Salam, Abdus

    The world's stock of nuclear weapons, which was three in 1945, has been growing ever since and is 50,OOOa in 1985. Nearly two trillion dollars of the public funds have been spent over the years to improve their destructive power, and the means of delivering them. One indicator of the awful power of these weapons is that the explosive yield of the nuclear weapons stockpiled today by the US, USSR, UK, France, and China is equivalent to one million Hiroshima bombs. Less than 1,000 of these 50,000 weapons could destroy USA and USSR. A thousand more in an all-out nuclear exchange could destroy the world as a habitable planet, ending life for the living and the prospects of life for those not yet born, sparing no nation, no region of the world…

  1. Development of radiation protection standards at EPA

    International Nuclear Information System (INIS)

    Meyers, S.

    1987-01-01

    Development of EPA radiation protection standards combines the elements of risk assessment and risk management. The process of risk assessment consists of technical evaluation of the source term, environmental transport mechanisms, and biological effects. Engineering evaluations provide data on control options and costs. The risk management process considers the scope of legal authorities and the balancing of costs and benefits of alternatives within the framework of national priorities. The regulatory process provides for substantial public participation and is subject to legal reviews

  2. 76 FR 14437 - Economic Simplified Boiling Water Reactor Standard Design: GE Hitachi Nuclear Energy; Issuance of...

    Science.gov (United States)

    2011-03-16

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0055] Economic Simplified Boiling Water Reactor Standard Design: GE Hitachi Nuclear Energy; Issuance of Final Design Approval The U.S. Nuclear Regulatory Commission has issued a final design approval (FDA) to GE Hitachi Nuclear Energy (GEH) for the economic...

  3. Review of international standards related to the design for control rooms on nuclear power plants

    International Nuclear Information System (INIS)

    Kitamura, Masashi; Yoshikawa, Hidekazu; Fujita, Yushi

    2005-01-01

    The improvement of Human-Machine Interface (HMI) design for control rooms on nuclear power plants (NPP) has been accomplished world wide, especially after the TMI-2 accident. The design process and guidelines are standardized in IEC60964 and supplemental standards as international standard. However, technological update is required due to the increased use of computerized control and monitoring equipment and systems in control rooms on NPP in recent years. Standards are becoming more important for computerized control rooms because there is more freedom to design than conventional hardware based system. For computerized control rooms, standards for hardware and software of HMI systems should be also considered. Standards and guidelines for computerized control rooms on NPP have been developed recently in each body such as IEC, ISO, and IEEE etc. Therefore, reviewing these standards and guidelines related to control rooms design of NPP can be useful not only for revision of the international standards such as IEC60964, but also for users of the standards and guidelines. In this paper, we reviewed the international standards related to the design for control rooms, in the two aspects of HMI design and hardware and software design, considering the undergoing revision work and their application. (author)

  4. A nuclear law in development

    International Nuclear Information System (INIS)

    Boudahrain, A.

    1991-01-01

    In this work the author demonstrates that the nuclear option for increasing the maghrebian capacities for electrical power production can not be conceived, from the ethic and humane point of view, for only one maghrebian country because of both external and internal constraints and difficulties which mortgage the future of destitute population and future generations. It is essential to lead intensive studies in this field by maghrebian research workers not accepting blindly foreign preconceptions. However, as a prelimenary, it is advisable to wonder about the ethical value of nuclear option, avoiding the multiform domination misdeeds (e.g. cultural and strategic) that such a choice involves for the maghrebis. 184 refs. (author)

  5. Development of Czechoslovak nuclear power complex

    International Nuclear Information System (INIS)

    Rajci, T.

    1986-01-01

    The research project ''Development of the Czechoslovak nuclear power complex'' was undertaken by several Czechoslovak institutions and was coordinated by the Research Institute of the Fuel and Power Complex in Bratislava. Involved in the project was a staff of 170 people. 274 reports were pulished and the cost approached 70 mill. Czechoslovak crowns. The results are characterized of all six partial tasks. Basic information was prepared for the forecast of the solution of fuel and power problems in Czechoslovakia up to the year 2000 and their prospects up to the year 2020. Program MORNAP was written for the development of nuclear power, which models the operation of a power generation and transmission system with a selectable number of nuclear power plants. Another partial task related to the fuel cycle of nuclear power plants with respect to long-term provision and management of nuclear fuel. Nuclear safety was split into three problem groups, viz.: system safety of nuclear power plant operation; radiation problems of nuclear power plant safety; quality assurance of nuclear power plant components. The two remaining tasks were devoted to nuclear power engineering and to civil engineering. (Z.M.). 3 tabs., 1 refs

  6. Application of Pressure Equipment Standard at nuclear power plants; Aplicacion del Reglamento de Equipos a Presion a las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Mostaza, J. M.

    2011-07-01

    Regarding with the paper presented on 9{sup t}h June 2011 referred to the Industrial Security standard in Nuclear Plants, it was about the application of Pressure Equipment standard to mentioned Nuclear Plants, this article is an extract of the paper going to be exposed. (Author)

  7. Development of web based performance analysis program for nuclear power plant turbine cycle

    International Nuclear Information System (INIS)

    Park, Hoon; Yu, Seung Kyu; Kim, Seong Kun; Ji, Moon Hak; Choi, Kwang Hee; Hong, Seong Ryeol

    2002-01-01

    Performance improvement of turbine cycle affects economic operation of nuclear power plant. We developed performance analysis system for nuclear power plant turbine cycle. The system is based on PTC (Performance Test Code), that is estimation standard of nuclear power plant performance. The system is developed using Java Web-Start and JSP(Java Server Page)

  8. Problems of nuclear power in developing countries

    International Nuclear Information System (INIS)

    Woite, G.

    1978-01-01

    The problems of nuclear power in developing countries are different in nature but not less severe than in industrialized countries. So far, only five developing countries with market economies (Argentina, India, Korea, Pakistan, Taiwan) have nuclear power plants in operation with a combined net output of 2.2 GWe. Nuclear projects with a total capacity of 15 GWe are under construction in these and four other developing countries in Asia and Latin America (Brazil, Iran, Mexico, Philippines). It is expected that most of the future nuclear power installed in developing countries of Asia, Africa and Latin America will be in these countries which have overcome some of the problems of nuclear power. (orig./RW) [de

  9. A prehistory of nuclear energy development

    International Nuclear Information System (INIS)

    Yoshikawa, Hideo

    2007-01-01

    Evolutionary progress of the LWR plants in the last half-century was reviewed in series. As a prehistory of nuclear energy development, this first lecture presented (1) discovery of nuclear energy and development of the atomic bomb and (2) development of the reactor system using nuclear energy for making electricity and for naval propulsion. The first nuclear reactor to produce electricity was the small Experimental Breeder Reactor (EBR-1) in Idaho, in the USA, which started up in December 1951. The Pressurized Water Reactor (PWR) for naval use was developed under Hyman Rickover in the USA. The Mark I prototype naval reactor started up in March 1953 in Idaho, and the first nuclear-powered submarine, NS Nautilus, with the Mark II reactor was put into service in January 1955. (T. Tanaka)

  10. Engineering development in nuclear power plant construction

    International Nuclear Information System (INIS)

    Guenther, P.

    1979-01-01

    Proceeding from the up-to-now experience in the erection of nuclear power stations, especially of the first and second unit of the Greifswald nuclear power plant, the following essential aspects of the development of constructional engineering are discussed: (1) constructional features and criteria, (2) organizational management, (3) current status and problems in prelimary operations, and (4) possibilities of further expenditure reductions in constructing nuclear power stations

  11. Design of nuclear spectroscopy electronics based on the EUROsystem standard

    International Nuclear Information System (INIS)

    Pahor, J.

    1987-11-01

    The development of modular nuclear instruments in the EUROcard system has been continued by the design of a staircase generator; such an instrument is needed for accurate testing of spectroscopy amplifiers. The generator provides very precisely defined steps with the period between them varying from 8 to 50 microseconds, the output voltage continuously variable from 2 to 5 V, and attenuated ion steps between 1 and 100. Great care was taken that individual steps exhibit no overshot, thus providing a very clean signal to the input of a tested amplifier. The circuitry is kept simple, and it can be easily constructed in any electronics laboratory. Figs

  12. Development of support system for nuclear power plant piping

    International Nuclear Information System (INIS)

    Horino, Satoshi

    1987-01-01

    Ishikawajima-Harima Heavy Industries Co., Ltd. has advanced the development of Integrated Nuclear Plant Piping System (INUPPS) for nuclear power plants since 1980, and continued its improvement up to now. This time as its component, a piping support system (PISUP) has been developed. The piping support system deals with the structures such as piping supports and the stands for maintenance and inspection, and as for standard supporting structures, it builds up automatically the structures including the selection of optimum members by utilizing the standard patterns in cooperation with the piping design system including piping stress analysis. As for the supporting structures deviating from the standard, by amending a part of the standard patterns in dialogue from, structures can be built up. By using the data produced in this way, this system draws up consistently a design book, production management data and so on. From the viewpoint of safety, particular consideration is given to the aseismatic capability of nuclear power plants, and piping is fundamentally designed regidly to avoid resonance. It is necessary to make piping supports so as to have sufficient strength and rigidity. The features of the design of piping supports for nuclear power plant, the basic concept of piping support system, the constitution of the software and hardware, the standard patterns and the structural patterns of piping support system and so on are described. (Kako, I.)

  13. Licensing procedure, nuclear codes and standards in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Schultheiss, G.F.

    1980-01-01

    The present paper deals with legal background of licensing in nuclear technology and atomic energy use, licensing procedures for nuclear power plants and with codes, standards and guidelines in the Federal Republic of Germany. (orig./RW)

  14. Principles and foundation: national standards on quantities and units in nuclear science field

    International Nuclear Information System (INIS)

    Chen Lishu

    1993-11-01

    The main contents of National Standards on Quantities and units of atomic and nuclear physics (GB 3102.9) and Quantities and Units of nuclear reactions and ionizing radiations (GB 310.10) are presented in which most important quantities with their symbols and definitions in the nuclear scientific field are given. The principles and foundation, including the International System of Units (SI) and its application to the nuclear scientific field, in the setting of the National Standards are explained

  15. Advantages and disadvantages of developing nuclear power

    International Nuclear Information System (INIS)

    Wang Zhixin

    1987-01-01

    To solve the problem of the shortage of electricity in China, an objective assessment of the advantages and disadvantages of generating electricity from different energy sources is necessary. Nuclear power is evaluated against hydro-, oil-, gas- and coal-power. It is proposed to develop nuclear power in a planned way as a sensible long term strategy

  16. Material development for India's nuclear power programme

    Indian Academy of Sciences (India)

    rials with emphasis on development of fabrication routes of zirconium alloys for .... nuclear power programme, which envisages design and construction of thermal breeder ... Production of Hf-free nuclear grade zirconium ..... Later on for pressure tubes specified limit for hydrogen content in the as manufactured condition.

  17. Nuclear Insurance Pools: Worldwide Practice and Development

    International Nuclear Information System (INIS)

    Reitsma, S. M. S.

    1998-01-01

    The development of nuclear installations to produce electricity led to the establishment of Nuclear Insurance Pools and the introduction of international Conventions on Third Party Liability. Nuclear Pools offer both Third Party Liability insurance, reflecting the Conventions' principles, and other insurance products. They are market-wide, providing a facility for participation by insurers who could not otherwise write the insurance for the particularly sensitive nuclear risk. All acceptances are for the net retention of each Member without recourse to individual reinsurance protection. Common account reinsurance is arranged with other Nuclear Pools all over the world. Thus, a transparency is created, which ensures the highest degree of reinsurance security and imposes a known finite limit to each participating insurer's commitment. Therefore, Pool-members are prepared to make a greater commitment to nuclear risks than would be case where they felt uncertain as regards their total exposure following a significant loss. (author)

  18. Development of Czechoslovak nuclear power engineering

    International Nuclear Information System (INIS)

    Keher, J.

    1985-01-01

    The output of Czechoslovak nuclear power plants is envisaged at 2200 MW by 1985, 4400 MW by 1990 and 10,280 MW by the year 2000. The operation so far is assessed of Bohunice V-1 and Bohunice V-2 power plants as is the construction of the Dukovany nuclear power plant. International cooperation in the fulfilment of the nuclear power programme is based on the General Agreement on Cooperation in the Prospective Development and Interlinkage of CMEA Power Systems to the year 1990, the Agreement on Multilateral International Specialization and Cooperation of Production and on Mutual Deliveries of Nuclear Power Plant Equipment. The most important factor in international cooperation is the Programme of Cooperation between the CSSR and the USSR. The primary target in the coming period is the Temelin nuclear power plant project and the establishment of unified control of the nuclear power complex. (M.D.)

  19. The evolution of IRRR nuclear standards from the single failure criterion and their impact on system design

    International Nuclear Information System (INIS)

    Clark, D.H.

    1978-01-01

    One of the first industry standards developed in the United States to meet regulatory agency criteria for the design and installation of nuclear power plant control and instrumentation systems was prepared by the Institute of Electrical and Electronics Engineers, Inc., abbreviated IEEE. This was IEEE Std. 279, first issued in 1968. It was subsequently revised and reissued as IEEE Std. 279-1971 ''IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations''. Not only has the implementation of this standard had a tremendous impact on nuclear power plant design in the United States, it has been the base document from which subsequent IEEE nuclear standards have been developed. Three major concepts which are addressed by IEEE 279, and which have had a major impact upon control and instrumentation systems in nuclear power plants are the following : 1) Single failure criterion. 2) Equipment qualification. 3) Channel independence. Each of these concepts has resulted in the development of subsequent IEEE Nuclear Standards. The impact of some of these on control and instrumentation systems are discussed. (author)

  20. Development of etched nuclear tracks

    International Nuclear Information System (INIS)

    Somogyi, G.

    1980-01-01

    The theoretical description of the evolution of etched tracks in solid state nuclear track detectors is considered for different initial conditions, for the cases of constant and varying track etch rates, isotropic and anisotropic bulk etching as well as for thick and thin detectors. It is summarized how one can calculate the main parameters of etch-pit geometry, the track length, the axes of a surface track opening, track profile and track contour. The application of the theory of etch-track evolution is demonstrated with selected practical problems. Attention is paid to certain questions related to the determination of unknown track parameters and calculation of surface track sizes. Finally, the theory is extended to the description of the perforation and etch-hole evolution process in thin detectors, which is of particular interest for track radiography and nuclear filter production. (orig.)

  1. Development of etched nuclear tracks

    International Nuclear Information System (INIS)

    Somogyi, G.

    1979-01-01

    The theoretical description of the evolution of etched tracks in solid state nuclear track detectors is considered for different initial conditions, for the cases of constant and varying track etch rates, isotopic and unisotropic bulk etching as well as for thick and thin detectors. It is summarized how the main parameters of etch-pit geometry, the track length, the axes of a surface track opening, the track profile and the track contour can be calculated. The application of the theory of etch-track evolution is demonstrated with selected practical problems. Attention is paid to certain questions related to the determination of unknown track parameters and calculation of surface track sizes. Finally, the theory is extended to the description of the perforation and etch-hole evolution process in thin detectors, which is of particular interest for track radiography and nuclear filter production. (author)

  2. The summary of the nuclear power development in Japan

    International Nuclear Information System (INIS)

    Mizoguchi, Kenzo; Hirose, Yasuo; Fukai, Yuzo; Hada, Mikio; Ogawa, Nagao.

    1980-01-01

    A quarter of century has elapsed since the development of atomic energy was started in Japan. At present, the scale of nuclear power generation reached the operation of 22 plants with about 15.12 million kW capacity, and 12% of the total installation capacity for power generation. Efforts have been exerted to bring up the domestic technologies gradually, while importing and digesting quickly the foreign technologies. Now in LWRs, the equipments of nearly 100% can be produced by the domestic technologies, moreover, the technologies have reached such level that they can be exported to foreign countries. In the last five years, the improvement and standardization of LWR technologies have been promoted. The development of the reactors of new types has been continued by the domestic technologies. According to the long term plan, the nuclear power generation of 53 million kW is expected by 1990, but various problems such as the location of nuclear power stations and nuclear fuel cycle remain, and considerable difficulty is expected in its materialization. The history of nuclear power generation in Japan, the features and progress of LWRs, the photographs and the main specifications of notable nuclear power plants, and the future perspectives of LWRs, the reactors of new types, nuclear fusion and nuclear fuel cycle are described. (Kako, I.)

  3. Career Development forWomen in Nuclear

    International Nuclear Information System (INIS)

    Boshielo, P.

    2015-01-01

    Nuclear technology is a highly specialised field that requires a variety of professionals. Nuclear engineers, statisticians, physicists, information technology professionals, analysts, policy makers, scientists and other professionals. Because of the variety of backgrounds, many young female professionals need training and professional development opportunities to become well rounded in these disciplines. There has been a rising awareness of the need for development of the women professionals across the international field of the nuclear industry. Due to growth and expansion of nuclear power worldwide, a strong community of skilled next generation women professionals is required. Developing women professionals to fill this challenging need can first be addressed by making university students and young female professionals already working in the industry aware of the nuclear community and the unique career opportunities it encompasses. Once the decision is made to pursue a career in the nuclear community, professional development opportunities are an essential building block to becoming a more effective member of the international nuclear community. Current opportunities available to be discussed include international training, internships and fellowships, graduate degrees and professional networks. Present needs and gaps in the current professional development offerings will be identified as well as suggested ways they can be filled. In conclusion, programmes still needed in support of the career development of the female professionals will be addressed. (author)

  4. Status of Recent Developments in the Technical Standards of Japan

    International Nuclear Information System (INIS)

    Ahn, Hyung-Joon; Ahn, Sang-Kyu; Koh, Jae-Dong; Kim, Chang-Bum

    2006-01-01

    Japan has systematically revamped its technical standards for nuclear reactor facilities by formulating various performance regulations. Being part of a trend toward deregulation, such efforts toward social regulation is aimed at effectively operating administrative procedural laws to keep pace with global trends and enhance the benefits of deregulation under the principle of self-responsibility. Based on the collection of public opinions in February and March 2005, the Nuclear and Industrial Safety Agency(NISA) presented its position that it was required to promptly perform a flexible assessment of the technical feasibility of formulated society and association standards. Current, pressing issues are summarized as an early revision of technical standards regarding nuclear facilities for power generation, use of society and association standards, and the overhaul of nuclear safety regulations subject to performance regulations. Subjecting technical standards to performance regulations means stipulating the qualitative aspects of performance and the targets that certain facilities must achieve, which are not specific standards, but general compulsory standards. This study examines the early revision of technical standards on nuclear facilities for power generation and the status of the use of society and association standards, as well as introducing the details of revisions in the concrete containment vessel standards as specific examples

  5. Present trends in nuclear energy development

    International Nuclear Information System (INIS)

    Rotaru, Ioan

    2006-01-01

    The paper presents the current trends of nuclear energy in Europe, the issue of radioactive waste management, the modern technical solutions for building new nuclear power plants and, also, the nuclear power long term prospects. The following trends and methods of reducing costs are addressed: - upgrading the availability of nuclear power units; since 1990 till now in Europe the availability factor has risen from 74 % to 84%; - extending the operation life of nuclear power plants from 30 - 40 years to 60 years; - stable reduction of the duration of annual planned outages necessary for maintenance and nuclear fuel re-loading; it is noteworthy the performance of Unit 2 Olkiluoto NPP, Finland, that was shutdown for annual outage and fuel re-loading for a 7 days only; - stable cuts of nuclear fuel cost by using advanced nuclear fuel and by increasing the fuel burnup; over the last years, nuclear fuel cost share in the operation costs has constantly decreased to values of about 0.5 USD cent/KWh e; - increase of the rated capacity of the existing in Europe nuclear power units, through upgrading programs that contribute to enhancing their efficiency. In the year 2002 Generation IV International Forum (GIF) finalized the technological strategy in the field, identifying the most promising nuclear power systems for which the research will continue. This strategy also identifies the main objectives that must by pursued within the research-development programs out of which one mentions the following: - identifying sustainable solution for generating electricity; - minimizing the radioactive waste and its management; - optimization of operation costs; - reducing the financial risk comparable to other energy solutions; - excellence in nuclear safety and reliability; - increasing resistance to proliferation; - ruling out the emergency solutions. Finally, the paper mentions the international engagement, representing a new approach in nuclear power, namely the transition to the use

  6. Standard Guide for Preparing Waste Management Plans for Decommissioning Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This guide addresses the development of waste management plans for potential waste streams resulting from decommissioning activities at nuclear facilities, including identifying, categorizing, and handling the waste from generation to final disposal. 1.2 This guide is applicable to potential waste streams anticipated from decommissioning activities of nuclear facilities whose operations were governed by the Nuclear Regulatory Commission (NRC) or Agreement State license, under Department of Energy (DOE) Orders, or Department of Defense (DoD) regulations. 1.3 This guide provides a description of the key elements of waste management plans that if followed will successfully allow for the characterization, packaging, transportation, and off-site treatment or disposal, or both, of conventional, hazardous, and radioactive waste streams. 1.4 This guide does not address the on-site treatment, long term storage, or on-site disposal of these potential waste streams. 1.5 This standard does not purport to address ...

  7. Will nuclear power plant standardization reduce the licensing impact on construction

    International Nuclear Information System (INIS)

    Allen, J.M.; Bingham, W.G.; Keith, D.G.

    1976-01-01

    The NRC and the nuclear industry have been pursuing standardization quite vigorously in an effort to reduce the cost and schedule for the design and construction of nuclear power plants. The NRC is currently reviewing standard plant applications submitted under each of four standardization options. In addition, the NRC has published Standard Review Plans and Standard Technical Specifications. Although problems exist in the implementation of standardization and in areas unaffected by standardization, each of these standardization methods has the potential to reduce the licensing impact on construction

  8. Standard Review Plan Update and Development Program

    International Nuclear Information System (INIS)

    1992-05-01

    This implementing procedures document (IPD) was prepared for use in implementing tasks under the standard review plan update and development program (SRP-UDP). The IPD provides comprehensive guidance and detailed procedures for SRP-UDP tasks. The IPD is mandatory for contractors performing work for the SRP-UDP. It is guidance for the staff. At the completion of the SRP-UDP, the IPD will be revised (to remove the UDP aspects) and will replace NRR Office Letter No. 800 as long-term maintenance procedures

  9. Standard Review Plan Update and Development Program

    Energy Technology Data Exchange (ETDEWEB)

    1992-05-01

    This implementing procedures document (IPD) was prepared for use in implementing tasks under the standard review plan update and development program (SRP-UDP). The IPD provides comprehensive guidance and detailed procedures for SRP-UDP tasks. The IPD is mandatory for contractors performing work for the SRP-UDP. It is guidance for the staff. At the completion of the SRP-UDP, the IPD will be revised (to remove the UDP aspects) and will replace NRR Office Letter No. 800 as long-term maintenance procedures.

  10. Developments of nuclear power in Russia

    International Nuclear Information System (INIS)

    Konowalow, V.; Tytschkow, J.; Terentjew, W.

    1994-01-01

    Since the disintegration of the Soviet Union the economy, and thus also the nuclear industry in Russia, which is supervised by the Ministry for Atomic Energy, is in a process of structural change. The process is to result in a diversification of the products manufactured for use in the power industry and the nuclear fuel cycle, and also in enhanced productivity. Science and research, which enjoy a high reputation worldwide, must be preserved and expanded. Nuclear technology in Russia is to be developed further in three stages. In the renewal phase up until 2000, older nuclear power stations will be phased out and a new generation of reactors will be developed, which will be built and connected to the power grid in the second stage, which will extend until 2010. In the third phase, after 2010, the installed capacity of the nuclear generating units equipped with new reactors is to rise to 30 or 40 million kW. (orig.) [de

  11. Development of nuclear material accountancy control system

    International Nuclear Information System (INIS)

    Hirosawa, Naonori; Kashima, Sadamitsu; Akiba, Mitsunori

    1992-01-01

    PNC is developing a wide area of nuclear fuel cycle. Therefore, much nuclear material with a various form exists at each facility in the Works, and the controls of the inventory changes and the physical inventories of nuclear material are important. Nuclear material accountancy is a basic measure in safeguards system based on Non-Proliferation Treaty (NPT). In the light of such importance of material accountancy, the data base of nuclear material control and the material accountancy report system for all facilities has been developed by using the computer. By this system, accountancy report to STA is being presented certainly and timely. Property management and rapid corresponding to various inquiries can be carried out by the data base system which has free item searching procedure. (author)

  12. Nuclear energy in Turkey. Recent developments

    International Nuclear Information System (INIS)

    Alper, Z.

    2014-01-01

    Full text : The global demand for electricity is rapidly increasing. There is growing uncertainty in regard to the supply and prices of oil and natural gas. These considerations have opened new prospects for the development of nuclear energy on a global state. Despite the negative impact of the Fukushima Daichi accident, still some countries are considering or have expressed interest in developing nuclear power programmes. As the country using nuclear technology is primarily responsible for safety and as operational safety cannot be out sourced, building of sound safety expertise and strong safety culture is an essential precondition for the country introducing nuclear technology. Turkey's energy policy is naturally focused on the security, sustainability and competitiveness of energy supply. It is designed to sustain targeted economic and social growth in the long run. Turkey remains resolutely committed to the goal of ensuring safe, secure and peaceful utilization of nuclear energy

  13. A preliminary study on the design in architecture of nuclear and radiation safety standard system

    International Nuclear Information System (INIS)

    Song Dahu; Zhang Chi; Yang Lili; Li Bin; Liu Yingwei; An Hongzhen; Gao Siyi; Liu Ting; Meng De

    2014-01-01

    The connotation and function of nuclear and radiation safety standards are analyzed, and their relationships with the relevant laws and regulations are discussed in the paper. Some suggestions and blue print of overall architecture to build nuclear and radiation safety standard system are proposed, on the basis of researching the application status quo, existing problems and needs for nuclear and radiation safety standards in China. This work is a beneficial exploration and attempt to establish China's nuclear and radiation safety standards. (authors)

  14. Organization and development of the Brazilian nuclear program

    International Nuclear Information System (INIS)

    Pinto, C. Syllus M.; Alves, R. Nazare; Lepecki, W.; Costa, H.M. da; Grinberg, M.; Grimberg, M.

    1977-01-01

    The paper presents the Brazilian Nuclear Energy Program: its development until the present stage, as well as the organizations and the distribution of responsibilities involved in its execution at the present time. The nuclear power policy is established at the Presidency of the Republic and is planned, executed and controlled through the Ministry of Mines and Energy. Directly subject to the Ministry is the Brazilian Nuclear Energy Commission (CNEN), which has regulatory, standardization, licensing, planning and surveillance functions. The nuclear fundamental research and manpower formation are also under CNEN responsibility. Also subject to the Ministry are two companies responsible for the execution of the Programme: the Centrais Eletricas Brasileiras S.A. - ELETROBRAS, which advises on the granting of permits for the construction and operation of nuclear power plants, and the Empresas Nucleares Brasileiras S.A. - NUCLEBRAS, which holds the monopoly of the nuclear fuel cycle in the country, designs and builds nuclear power plants and provides assistance to the electric utilities as well as promotes the participation of the Brazilian industry in the nuclear field. Besides describing the new distribution of regulatory functions given by law to the CNEN, this paper gives special emphasis to the large industrial complex which is in the process of being established with the setting-up of the many NUCLEBRAS subsidiaries in joint-venture with German firms in the nuclear field, as a consequence of the Industrial Cooperation between Brazil and the Federal Republic of Germany in the Field of the Peaceful Uses of Nuclear Energy signed between the two countries on June 27, 1975. The programs for these subsidiaries are presented and their participation in the Brazilian Nuclear Energy Programme is discussed. The technology transfer aspects of the industrial activities are also discussed, based on the Government's policy on the subject [es

  15. Nuclear energy for a sustainable development

    International Nuclear Information System (INIS)

    Guerrini, B.; Oriolo, F.

    2001-01-01

    Nuclear power currently produces over 628 M tep of the generated energy in 1997 avoiding about 1978 Mt of CO 2 emission and gives a significant contribution to reducing greenhouse gas emission. The competitive position of nuclear power might be strengthened, if market forces or government policy were able to give energy security and to control greenhouse gas, relying upon market mechanism and including environmental costs in economic analysis. In this case, taking into account the entire up-stream and down-stream chains for electricity generation, it can be seen that the greenhouse emission from nuclear plants, is lower than that of renewable energy chains. This paper investigates the potential role of nuclear power in global energy supply up to 2020 and analyzes the opportunities and the challenges for research, governments and nuclear industries of a broad nuclear power development in response to environmental concerns. The authors think that nuclear energy will have to compete in the same framework and under the same conditions as all other energy sources and so analyze the possibility of re-launching nuclear energy: it will have to couple nuclear safety and economic competitiveness [it

  16. Nuclear power for sustainable development

    International Nuclear Information System (INIS)

    Corpuz, Antonio T.

    1997-01-01

    The need for stable and reliable energy supply was clearly illustrated by the Philippine experience of the last five years where the bleak energy supply situation caused massive losses in productivity. Indigenous energy resources even if exploited to full capacity is not sufficient to support the progress needed to give our growing population the quality of life it deserves. Important too is the fact that world energy resources especially oil and natural gas is estimated to last up to the first half of the next century. Thus the entry of nuclear power as a vital contributor to a safe, reliable, competitive and cost effective source of energy supply become a necessity. (author)

  17. On nuclear manpower development in Vietnam

    International Nuclear Information System (INIS)

    Phung Van Duan

    2007-01-01

    Vietnam began to be interested in education and training on nuclear sciences and related subjects since the early 1960's. A department of Nuclear Physics and Engineering was established in 1970 at the Hanoi University of Technology (HUT), which is the biggest interdisciplinary technological education centre of the country. In Vietnam there are several institutions where exist programmes of education on nuclear sciences and nuclear engineering. But HUT has been being since 1970 the only institution that has underway programme of education on nuclear engineer degree. Although the Department was renamed and its education programme was adjusted, but the objectives of its education programme have been being followed without changes. These objectives are as follows: 1) To develop peaceful applications of atomic energy in Vietnam; 2) To train up engineers on nuclear instrumentation for supporting the first objective; and 3) To prepare initial manpower for introduction of Nuclear Power in Vietnam. Nuclear community of Vietnam is still not so large. Total number of its members increased until 1986, and then decreases up to now. Present average age of members of the community is of 45. In 15 coming years at least 500-700 young people must be educated on programmes on nuclear engineer degree and on nuclear bachelor degree. This is a very difficult task for a developing country such as Vietnam. From a point of view of development, the above-mentioned number is too small, and it must be much more. This makes the task much more difficult. In addition, education on nuclear engineering in the country at present is in a hard situation because of lacking in experienced people, as well as in teaching material and equipment, and, because of weakness of the education programme. So, it may be impossible to achieve success in realization of the task without a large and effective international cooperation in education on nuclear science and engineering. That is why the Asian Network for

  18. Nuclear power programmes in developing countries

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    The paper on ''Nuclear power programmes in developing countries'' is a report to the IAEA by a Senior Expert Group. A description is given of the requirements for a successful nuclear power programme, including the constraints that developing countries might face in the introduction and execution of the programme. The group attempted to identify the main issues affecting the financing of nuclear power projects and suggested specific actions that could be undertaken in order to reduce economic and financial risks. The various issues were discussed under the topic headings:-programme-project-related factors, investment climate, financing plan, export credits and creditworthiness. (U.K.)

  19. Sustainable development and peaceful use of nuclear energy in Romania

    International Nuclear Information System (INIS)

    Valeca, Serban Constantin; Popescu, Dan

    2004-01-01

    The concept of sustainable development was elaborated in the late 1980s and was defined as a development that fulfills the needs of the present without compromising the ability of future generations to meet their own needs. Sustainable development incorporates equity within and across countries as well as across generations, and integrates economic growth, environmental protection and social welfare. To analyze nuclear energy from a sustainable development perspective it is necessary to consider its economic, environmental and social impacts characteristics, both positive and negative. It is obvious that the development of nuclear energy broadens the natural resource base usable for energy production, and increases human and man-made capital. There are also many arguments in favor of nuclear energy as a reliable source such as: the large size of the nuclear power plants, their long periods of operation and the existent experience for operation. The risks associated with radiation are among the most extensively studied hazards known by man, but several factors are preserving public anxiety about radiation. Radiation is inaccessible to human senses, difficult to understand, and probabilistic in its effects, which to the public means uncertainty. Hence, radiological protection is essential to ensure that nuclear energy is compatible with sustainable development. Nuclear energy has, in normal operation, a low impact on health and environment. In order to meet the sustainable development goals, it is necessary to maintain its high standards of safety in spite of increasing competition in the electricity sector and reactors ageing in order to achieve a higher level of public acceptance. The complex technologies used by nuclear fuel cycle facilities are controlled and regulated by international and national institutions. A framework of regulatory, institutional and technical measures is already in place ensuring that the use of nuclear energy does not significantly modify

  20. Potential role of nuclear power in developing and transition economies

    International Nuclear Information System (INIS)

    Ganiage, D.; Dierstein, P.

    1995-01-01

    The potential role of nuclear power is different in developing or in transition economies; in developing countries such as China, the growth of electricity consumption is high and the construction of several standardized plants is economically justified; in transitional economies, such as Ukraine, the needs are uncertain, old and unsafe plants have to be decommissioned and uncompleted nuclear plants (due to financial problems) should be completed. Nuclear power may provide the developing and transition economies with several advantages such as energy independence and fuel supply security, minimal environmental pollution, support to local industry and employment. It also means the support of national authorities and the development of a suitable infrastructure for plant safety and waste management, financial help and local population acceptance

  1. Nuclear plant analyzer development at INEL

    International Nuclear Information System (INIS)

    Laats, E.T.; Russell, K.D.; Stewart, H.D.

    1983-01-01

    The Office of Nuclear Regulatory Research of the US Nuclear Regulatory Commission (NRC) has sponsored development of a software-hardware system called the Nuclear Plant Analyzer (NPA). This paper describes the status of the NPA project at the INEL after one year of development. When completed, the NPA will be an integrated network of analytical tools for performing reactor plant analyses. Development of the NPA in FY-1983 progressed along two parallel pathways; namely, conceptual planning and software development. Regarding NPA planning, and extensive effort was conducted to define the function requirements of the NPA, conceptual design, and hardware needs. Regarding software development conducted in FY-1983, all development was aimed toward demonstrating the basic concept and feasibility of the NPA. Nearly all software was developed and resides on the INEL twin Control Data Corporation 176 mainframe computers

  2. Nuclear Cryogenic Propulsion Stage Affordable Development Strategy

    Science.gov (United States)

    Doughty, Glen E.; Gerrish, H. P.; Kenny, R. J.

    2014-01-01

    The development of nuclear power for space use in nuclear thermal propulsion (NTP) systems will involve significant expenditures of funds and require major technology development efforts. The development effort must be economically viable yet sufficient to validate the systems designed. Efforts are underway within the National Aeronautics and Space Administration's (NASA) Nuclear Cryogenic Propulsion Stage Project (NCPS) to study what a viable program would entail. The study will produce an integrated schedule, cost estimate and technology development plan. This will include the evaluation of various options for test facilities, types of testing and use of the engine, components, and technology developed. A "Human Rating" approach will also be developed and factored into the schedule, budget and technology development approach.

  3. Some aspects of nuclear power development in Czechoslovakia

    International Nuclear Information System (INIS)

    Simandl, S.; Stefec, V.

    1986-01-01

    Some technical and economic aspects of the development of nuclear power in Czechoslovakia are discussed. Specific conditions include the high population density of the territory and related factors as well as the shortage of raw materials for the construction of technological equipment and for the construction of buildings. It is stated that projects of future nuclear power plants should use reserves, such as are available in the standard project of a WWER-1000 nuclear power plant now being used in Temelin, as against foreign nuclear power plants. This mainly includes a bigger built-up area per installed megawatt of power and a greater number of personnel for operation and maintenance. Also discussed is the world-wide growth of capital costs, of construction time and of the number of workers needed for the construction of nuclear power plants. With the exception of the V-2 nuclear power plant the construction time of Czechoslovak nuclear power plants does not exceed world average. The maximum number of workers required for construction, however, compares unfavourably with advanced capitalist countries. Operating costs in Czechoslovakia are more favourable for nuclear power plants than for coal burning power plants and pumped-storage hydroelectric plants. (Z.M.)

  4. Some nuclear track technologies developed recently for practical purposes

    International Nuclear Information System (INIS)

    Hao Xiuhong

    2000-01-01

    For practical purposes three kinds of nuclear track technologies developed recently are described. They are coloring of nuclear track, nuclear track sheet replication and molding of micro metallic cones from nuclear tracks

  5. A scheme for the audit of scientific and technological standards in clinical nuclear medicine

    International Nuclear Information System (INIS)

    Perkins, A.C.; Jarritt, P.H.

    2002-01-01

    Aim: Audit is the process whereby the quality of a service is monitored and optimised. It forms an essential component of the quality assurance process, whether by self-assessment or by external peer review. In the UK the British Nuclear Medicine Society (BNMS) has undertaken external organisational audit of departments providing clinical nuclear medicine services. This work aimed to develop a more thorough and service specific process for the audit of scientific and technological standards in nuclear medicine. Materials and Methods: The audit process has been implemented using written audit documents to facilitate the audit procedure. A questionnaire forms part of the formal documentation for audit of the scientific and technical standards of a clinical service. Scientific and technical standards were derived from a number of sources including legal requirements, regulatory obligations, notes for guidance, peer reviewed publications and accepted good clinical practice (GCP). Results: The audit process graded the standards of an individual department according to legal or safety requirements (Grade A), good practice (Grade B) and desirable aspects of service delivery (Grade C). The standards have been allocated into eight main categories. These are: Instrumentation; Software and data protection; Electrical Safety; Mechanical Safety; Workstation Safety; The Control of Substances Hazardous to Health (COSHH); Radiation Protection; Scientific and Technical staffing levels. During the audit visit a detailed inspection of clinical and laboratory areas and department written documentation is also necessary to validate the data obtained. Conclusion: The printed scheme now provides a means for external audit or self-assessment. There should be evidence of a well-organised and safe environment for both patients and staff. Health and Safety legislation requires written local rules and these records should be available to demonstrate the standard of service provision. Other

  6. Nuclear reactor development in Korea: It's history and status

    International Nuclear Information System (INIS)

    Cheong, J.; Kim, I.; Kim, D. S.

    2007-01-01

    Currently in Korea, 20 nuclear plants are in operation, generating some 18,000 MWe of electricity which is about 30% of the national electricity supply. Further 8 reactors, including innovative light water reactors developed with 30 years' experience in construction and operation with continuous technology development, are either under construction or being planned. Executing an energetic program of nuclear development, Korea is now the world's sixth-ranked nuclear nation. In this paper, at first, history of the nuclear reactor development in Korea will be discussed including technology self-reliance efforts of the nuclear industry, and future plan and prospects will also be presented. Secondly, the OPR1000 which is a Korean standard plant will be introduced in detail including its characteristics, design approach and features. Six OPR1000's are being operated with outstanding performance and 4 more units are under construction. The APR1400, an upgraded reactor of the OPR1000 in capacity and design, has been developed as a next generation reactor, and the contracts were signed for the first 2 units' construction in August 2006. Its development process and design features will be described. Finally, Korea's efforts for future nuclear power generation will be introduced. For future reliable energy supply, Korea has been actively participating in international cooperation such as Gen IV International Forum. In summary, this paper will introduce the history and status of the Korean nuclear reactor development with its past, present and future, which might be helpful to understand the Korean nuclear industry and find a way for international cooperation especially with European countries

  7. South Africa's nuclear hydrogen production development programme

    International Nuclear Information System (INIS)

    Van Ravenswaay, J.P.; Van Niekerk, F.; Kriek, R.J.; Blom, E.; Krieg, H.M.; Van Niekerk, W.M.K.; Van der Merwe, F.; Vosloo, H.C.M.

    2010-01-01

    In May 2007 the South African Cabinet approved a National Hydrogen and Fuel Cell Technologies R and D and Innovation Strategy. The strategy will focus on research, development and innovation for: i) wealth creation through high value-added manufacturing and developing platinum group metals catalysis; ii) building on the existing knowledge in high temperature gas-cooled reactors (HTGR) and coal gasification Fischer-Tropsch technology, to develop local cost-competitive hydrogen production solutions; iii) to promote equity and inclusion in the economic benefits from South Africa's natural resource base. As part of the roll-out strategy, the South African Department of Science and Technology (DST) created three Competence Centres (CC), including a Hydrogen Infrastructure Competence Centre hosted by the North-West University (NWU) and the Council for Scientific and Industrial Research (CSIR). The Hydrogen Infrastructure CC is tasked with developing hydrogen production, storage, distribution as well as codes and standards programmes within the framework of the DST strategic objectives to ensure strategic national innovation over the next fifteen years. One of the focus areas of the Hydrogen Infrastructure CC will be on large scale CO 2 free hydrogen production through thermochemical water-splitting using nuclear heat from a suitable heat source such as a HTGR and the subsequent use of the hydrogen in applications such as the coal-to-liquid process and the steel industry. This paper will report on the status of the programme for thermochemical water-splitting as well as the associated projects for component and technology development envisaged in the Hydrogen Infrastructure CC. The paper will further elaborate on current and future collaboration opportunities as well as expected outputs and deliverables. (authors)

  8. Qualification of Programmable Electronic System (PES) equipment based on international nuclear I and C standards

    International Nuclear Information System (INIS)

    De Grosbois, J.; Hepburn, G. A.; Olmstead, R.; Goble, W.; Kumar, V.

    2006-01-01

    Nuclear power plants (NPPs) are increasingly faced with the challenge of qualifying procured equipment, sub-components, and systems that contain digital programmed electronics for use in safety-related applications. Referred to as a 'programmable electronic system' (PES), such equipment typically contains both complex logic that is vulnerable to systematic design faults, and low voltage electronics hardware that is subject to random faults. Procured PES products or components are often only commercial grade, yet can offer reliable cost effective alternatives to custom-designed or nuclear qualified equipment, provided they can be shown to meet the quality assurance, functional safety, environmental, and reliability requirements of a particular application. The process of confirming this is referred to as application-specific product qualification (ASPQ) and can be challenging and costly. This paper provides an overview of an approach that has been developed at Atomic Energy Canada Limited (AECL) and successfully applied to PES equipment intended for use in domestic Candu R 6 nuclear power plants and special purpose reactors at Chalk River Laboratories. The approach has evolved over the past decade and has recently been adapted to be consistent with, and take advantage of new standards that are applicable to nuclear safety-related I and C systems. Also discussed are how recognized third-party safety-certifications of PES equipment to International Electrotechnical Commission (IEC) standards, and the assessment methods employed, may be used to reduce ASPQ effort. (authors)

  9. Legal status of minister's notices and technology standards of 'Korea institute of nuclear safety'(KINS) to regulate nuclear safety

    International Nuclear Information System (INIS)

    Jung, S. K.; Jung, M. M.; Kim, S. W.; Jang, K. H.; Oh, B. J.

    2003-01-01

    Concerning nuclear safety or technology standards, each of 'notices' issued by minister of science and technology(MOST) empowered by law of its regulation is obviously forceful as a law, if not all. But the standards made by the chief of Korea institute of nuclear safety(KINS) to meet the tasks entrusted to KINS by MOST is only conditionally forceful as a law, that is, on the condition that law or regulation empowered the chief of KINS to make nuclear safety and/or technology standards

  10. American National Standards and the DOE - A cooperative effort to promote nuclear criticality safety

    International Nuclear Information System (INIS)

    Rothleder, B.M.

    1996-01-01

    The U.S. Department of Energy's (DOE's) new criticality safety order, DOE Order 420.1 (open-quotes Facility Safety,close quotes October 13, 1995), Sec. 4.3 (open-quotes Nuclear Criticality Safetyclose quotes), invokes, as an integral part, 12 appropriate American National Standards Institute/American Nuclear Society (ANSI/ANS) Series-8 standards for nuclear criticality safety, but with modifications. (The order that 420.1/4.3 replaced also invoked some ANSI/ANS Series-8 standards.) These modifications include DOE operation-specific exceptions to the standards and elaborations on some of the wording in the standards

  11. Environmental monitoring standardization of effluent from nuclear fuel cycle facilities in China

    International Nuclear Information System (INIS)

    Gao Mili

    1993-01-01

    China has established some environmental monitoring standards of effluent from nuclear fuel cycle facilities. Up to date 33 standards have been issued; 10 to be issued; 11 in drafting. These standards cover sampling, gross activities measurement, analytical methods and management rules and so on. They involve with almost all nuclear fuel cycle facilities and have formed a complete standards system. By the end of the century, we attempt to draft a series of analytical and determination standards in various environmental various medium, they include 36 radionuclides from nuclear fuel cycle facilities. (3 tabs.)

  12. Restructuring of Canada's nuclear utilities: recent developments

    International Nuclear Information System (INIS)

    Guindon, S.

    1998-01-01

    Business decisions relating to the electric power sector are a provincial responsibility in Canada. The federal government looks to the three nuclear utilities to manage their nuclear assets and maintain them in a way that maximizes their reliability, efficiency and overall performance. A significant development in Canada's nuclear sector in the past year was the Ontario Hydro Nuclear Asset Optimization Plan. Structural change in the North American electricity market is a major impetus for decisions regarding nuclear assets by Canada's electric power utilities. The Ontario government is now taking steps to introduce competition in the Ontario Electricity market. The province of New Brunswick, which has one reactor at Point Lepreau which supplies one-third of the province's electricity, is also taking measures to introduce competition in its electricity market. (author)

  13. Development of nuclear battery using isotope sources

    International Nuclear Information System (INIS)

    Chang, Won Jun

    2004-02-01

    Until now, the development of the useful micro electromechanical systems has the problems because previous batteries (solar, chemical, etc) did not satisfy the requirements related to power supply. At this point of time, nuclear battery using isotope sources is rising the solution of this problem. Nuclear battery can provide superior out-put power and lifetime. So a new type of micro power source (nuclear battery) for micro electromechanical systems has been designed and analyzed. In this work, I designed the three parts, isotope source, conversion device, and shielding. I chose suitable sources, and designed semiconductor using the chosen isotope sources. Power is generated by radiation exciting electrons in the semiconductor depletion region. The efficiency of the nuclear battery depends upon the pn-junction. In this study the several conceptual nuclear batteries using radioactive materials are described with pn-junction. And for the safety, I designed the shielding to protect the environment by reducing the kinetic energy of beta particles

  14. Standards life cycle and a methodolgy and infrastructure for standards development and implementation

    CSIR Research Space (South Africa)

    Cooper, Antony K

    2006-02-01

    Full Text Available -practice methodology and infrastructure for selecting, developing, implementing and refining standards across Stats SA. The life cycle for standards in an organisation is also described...

  15. Ukrainian Nuclear Society International Conference 'Strategy of the nuclear power development: The choice of Ukraine'

    International Nuclear Information System (INIS)

    Vishnevskij, I.N.; Trofimenko, A.P.

    2001-01-01

    Abstracts of the papers presented at the International Conference of the Ukrainian Nuclear Society 'Strategy of the nuclear power development'. The following problems are considered: present situation with the nuclear power and its safety; nuclear fuel cycle development; waste and spent nuclear fuel management; reactors' decommissioning issues; modernization of the NPP with WWER reactors; future reactors; economics of nuclear power; safety culture; legal and regulatory framework, state nuclear regulatory control; PR in nuclear power industry; staff training

  16. The development and appraisal of nuclear power: Pt. 2

    International Nuclear Information System (INIS)

    Thomas, S.

    1988-01-01

    The process of technology development is examined, the importance of learning-by-doing, economies of scale and standardization is assessed, and strategies for research, development and demonstration and technology transfer and diffusion are compared. A pragmatic view is adopted of what can be considered a product or a technology. As in Part I of this series, the nuclear power programmes of the U.S.A., Canada, France and the Federal Republic of Germany are used to illustrate the arguments. (author)

  17. Topical opinion paper - Apparent Discrepancies Between Nuclear and Conventional Seismic Standards

    International Nuclear Information System (INIS)

    Donald, John; Smith, Ian

    2003-01-01

    The differences between nuclear and conventional seismic standards are considered and their potential significance discussed. The approach to the design of nuclear facilities is appropriately both more rigorous and conservative than that required by conventional seismic standards and codes. For nuclear seismic design the requirements can be presented as assessment principles, e.g., NII SAPs or a safety guide e.g. IAEA; Seismic Design and Qualification for Nuclear Power Plants. The adoption of novel methods or designs are required to be supported by appropriate research and development with the ability to cite a precedent within the industry being a powerful endorsement. The method adopted must reliably predict the seismic response of the item to be qualified, including the seismic response of attached or supported Structures, Systems and Components. (SSC's) The traditional method adopted for seismic qualification by analysis has been based on linear elastic analyses. This is justified on the basis that the response is reliably predicted and realistic, provided that the elements remain elastic. In contrast the benefit of ductile behaviour of conventional structures within the design envelope has long been recognised and used as the basis to justify significant reductions in the seismic demand. Provided the acceptance criteria are met, the SAPs do not preclude and the IAEA safety guide specifically permits non linear behaviour within the design envelope for category 1 items. Both the current nuclear practice and the current conventional seismic standards can be classified as 'force based'. The displacement based approach, also referred to as performance based engineering (PBE), has been developed as a powerful tool in the evaluation and seismic retrofit of existing structures. This approach could be equally valid to the design of new structures and can be used to represent elastic or non linear behaviour although the full benefit will only be realised in the latter

  18. Economic development and nuclear proliferation: an overview

    International Nuclear Information System (INIS)

    Smith, G.W.; Soligo, R.

    1983-01-01

    The authors argue that the impact of nuclear-weapons programs on the development prospects of countries economically able to undertake such programs would likely be fairly small. The amounts involved and the backward linkages are usually sufficiently small that nuclear-weapons programs in most less-developed countries (LDCs) can be considered an enclave activity. On the other hand, economic development clearly facilitates bomb development. The chapter sets forth the main characteristics of economic growth that are likely to facilitate bomb development, then considers the ''bomb levy'' necessary for various types of countries to produce bombs on a scale considered appropriate for LDCs. It concludes that it will be policy-imposed costs rather than economic costs in themselves that will prevent determined LDC governments of moderate income and population from developing nuclear weapons. 16 references, 2 tables

  19. Applicability of ISO 9001: 2000 standard to design and research activities in nuclear objectives and installations

    International Nuclear Information System (INIS)

    Stamatopol, M.; Patticu, C.

    2001-01-01

    The ISO 9001: 2000 standard contains the results of the latest studies concerning the design and implementation of quality management systems. The continuous improvement of these systems required a new approach, namely, the process-based approach. A process-based model of quality management is presented in terms of client request, input data, management responsibility, resource management, product realisation, measurement / analysis and optimization, product, output data and client request fulfilment. Thus, the quality management system becomes an ensemble of interconnected or interacting processes. Consequently, to implement such a system the necessary processes have to be identified and their ISO 9001: 2000 standard based management ensured. Process based approach also allows better evidencing the input and output data specific to each process. Such an approach grants a wider applicability to the design and research activities in nuclear objectives and installations. This work aims at identifying additional requirements implied in design and research activities in nuclear field, as stipulated in the following standards / documents: - IAEA SG Q8 'Quality assurance in research and development'; - IAEA SG Q10 'Quality assurance in design'; - CAN / CSA N 286.2 - 00 'Design Quality Assurance for Nuclear Power Plants'; CAN 3 - CSA Z 299.1 'Quality Assurance Program - Category 1'; - NQA - 1, SUPPLEMENT 3S-1 'Supplementary requirements for design control'

  20. A common high standard for nuclear power plant exports: overview and analysis of the Nuclear Power Plant Exporters' Principles of Conduct

    International Nuclear Information System (INIS)

    Perkovich, George; Radzinsky, Brian

    2012-01-01

    At this time, there is no overarching global framework to regulate the development of the nuclear power industry. Laws concerning the export of nuclear technology vary across jurisdictions, and politically-binding arrangements such as the Nuclear Suppliers Group (NSG) help ensure that weapons-usable or dual-use technologies are not exported, but no single international regime or agreement manages the gamut of potential risks that may arise from the export of civilian nuclear power plants. Accordingly in 2008, the Carnegie Endowment for International Peace convened internationally-recognised experts in nuclear energy to begin a dialogue with nuclear power plant vendors about defining common criteria for the socially responsible export of nuclear power plants. The goal was to articulate a comprehensive set of principles and best practices that would raise the overall standard of practice for exports of nuclear power plants while enjoying widespread support and adherence. The outcome of this process is the Nuclear Power Plant Exporters' Principles of Conduct - an export-oriented code of conduct for nuclear power plant vendors. The Principles of Conduct help ensure that the participating companies will proceed with the sale of a new nuclear power plant only after a careful assessment of the legal, political, and technical contexts surrounding potential customers. It comprises six 'principles' that each address a major area of concern involved in the export of a nuclear power plant: safety, physical security, environmental protection and spent fuel management, systems of compensation for nuclear damage, non-proliferation and safeguards, and business ethics. The Principles of Conduct entail vendor responsibilities to apply specific standards or engage in certain practices before signing contracts and during the marketing and construction phases of a nuclear power plant export project. Conformity with the Principles of Conduct is voluntary and not-legally binding, but the

  1. Nuclear energy and its functions for development

    International Nuclear Information System (INIS)

    Nevskij, V.P.

    1980-01-01

    25 years have passed since the first nuclear power plant in the Soviet Union started operation and thus laid the foundations for the development of a fundamentally new branch of economy - nuclear industry. At present the following nuclear power plants are operated in the Soviet Union: Belojarsk, Kola, Bilibino, Armenia, Leningrad, Kursk, and Tschernobylj, the number of power plant units amounting to 19, the total electric power to 0.09 GW. In total the plants have generated 44.8 billion kWh in 1978; for 1979 a total generation of 54 billion kWh is expected. By the following five-year plans the construction of nuclear power plants is to be still essentially extended: about 20% of the total electric power is planned to be produced by nuclear power plants. In the course of this extension the new nuclear power plants are planned to achieve individual capacities between 4 and 6 GW, the nuclear heating power plants 2 GW. In addition there will be facilities for nuclear production of heat only with a thermal output of up to 1 GW. (orig./UA) [de

  2. Criteria, standards and policies regarding decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Detilleux, E.; Lennemann, W.

    1977-01-01

    The paper discusses the decontamination and decommissioning experiences encountered at the Eurochemic fuel reprocessing plant, their implications and the knowledge gained from these experiences. It includes the results of technical reviews made by the Nuclear Energy Agency of OECD and the International Atomic Energy Agency regarding decommissioning nuclear facilities. The conlusions which are presented should weigh heavily in the considerations of the national authorities involved in regulating nuclear power programmes. The paper notes the special planning that should be arranged between those responsible for the nuclear facility and competent public authorities who jointly should make a realistic determination of the eventual disposition of the nuclear facility, even before it is built. Recommendations cover the responsibilities of nuclear plant entrepreneurs, designers, operators, and public and regulatory authorities [fr

  3. PHITS code improvements by Regulatory Standard and Research Department Secretariat of Nuclear Regulation Authority

    International Nuclear Information System (INIS)

    Goko, Shinji

    2017-01-01

    As for the safety analysis to be carried out when a nuclear power company applies for installation permission of facility or equipment, business license, design approval etc., the Regulatory Standard and Research Department Secretariat of Nuclear Regulation Authority continuously conducts safety research for the introduction of various technologies and their improvement in order to evaluate the adequacy of this safety analysis. In the field of the shielding analysis of nuclear fuel transportation materials, this group improved the code to make PHITS applicable to this field, and has been promoting the improvement as a tool used for regulations since FY2013. This paper introduced the history and progress of this safety research. PHITS 2.88, which is the latest version as of November 2016, was equipped with the automatic generation function of variance reduction parameters [T-WWG] etc., and developed as the tool equipped with many effective functions in practical application to nuclear power regulations. In addition, this group conducted the verification analysis against nuclear fuel packages, which showed a good agreement with the analysis by MCNP, which is extensively used worldwide and abundant in actual results. It also shows a relatively good agreement with the measured values, when considering differences in analysis and measurement. (A.O.)

  4. A framework for regulatory requirements and industry standards for new nuclear power plants

    International Nuclear Information System (INIS)

    Duran, Felicia A.; Camp, Allen L.; Apostolakis, George E.; Golay, Michael W.

    2000-01-01

    This paper summarizes the development of a framework for risk-based regulation and design for new nuclear power plants. Probabilistic risk assessment methods and a rationalist approach to defense in depth are used to develop a framework that can be applied to identify systematically the regulations and standards required to maintain the desired level of safety and reliability. By implementing such a framework, it is expected that the resulting body of requirements will provide a regulatory environment that will ensure protection of the public, will eliminate the burden of requirements that do not contribute significantly to safety, and thereby will improve the market competitiveness of new plants. (author)

  5. Development of proliferation resistance assessment methodology based on international standard

    International Nuclear Information System (INIS)

    Ko, W. I.; Chang, H. L.; Lee, Y. D.; Lee, J. W.; Park, J. H.; Kim, Y. I.; Ryu, J. S.; Ko, H. S.; Lee, K. W.

    2012-04-01

    Nonproliferation is one of the main requirements to be satisfied by the advanced future nuclear energy systems that have been developed in the Generation IV and INPRO studies. The methodologies to evaluate proliferation resistance has been developed since 1980s, however, the systematic evaluation approach has begun from around 2000. Domestically a study to develop national method to evaluate proliferation resistance (PR) of advanced future nuclear energy systems has started in 2007 as one of the long-term nuclear R and D subjects in order to promote export and international credibility and transparency of national nuclear energy systems and nuclear fuel cycle technology development program. In the first phase (2007-2010) development and improvement of intrinsic evaluation parameters for the evaluation of proliferation resistance, quantification of evaluation parameters, development of evaluation models, and development of permissible ranges of evaluation parameters have been carried out. In the second phase (2010-2012) generic principle of to evaluate PR was established, and techincal guidelines, nuclear material diversion pathway analysis method, and a method to integrate evaluation parameters have been developed. which were applied to 5 alternative nuclear fuel cycles to estimate their appicability and objectivity. In addition, measures to enhance PR of advanced future nuclear energy systems and technical guidelines of PR assessment using intrinsic PR evaluation parameters were developed. Lastly, requlatory requirements to secure nonproliferation requirements of nuclear energy systems from the early design stage, operation and to decommissioning which will support the export of newly developed advanced future nuclear energy system

  6. 78 FR 37325 - License Renewal of Nuclear Power Plants; Generic Environmental Impact Statement and Standard...

    Science.gov (United States)

    2013-06-20

    ... Nuclear Power Plants; Generic Environmental Impact Statement and Standard Review Plans for Environmental... for Nuclear Power Plants, Supplement 1: Operating License Renewal'' (ESRP). The ESRP serves as a guide... published a final rule, ``Revisions to Environmental Review for Renewal of Nuclear Power Plant Operating...

  7. Software development for managing nuclear material database

    International Nuclear Information System (INIS)

    Tondin, Julio Benedito Marin

    2011-01-01

    In nuclear facilities, the nuclear material control is one of the most important activities. The Brazilian National Commission of Nuclear Energy (CNEN) and the International Atomic Energy Agency (IAEA), when inspecting routinely, regards the data provided as a major safety factor. Having a control system of nuclear material that allows the amount and location of the various items to be inspected, at any time, is a key factor today. The objective of this work was to enhance the existing system using a more friendly platform of development, through the VisualBasic programming language (Microsoft Corporation), to facilitate the operation team of the reactor IEA-R1 Reactor tasks, providing data that enable a better and prompter control of the IEA-R1 nuclear material. These data have allowed the development of papers presented at national and international conferences and the development of master's dissertations and doctorate theses. The software object of this study was designed to meet the requirements of the CNEN and the IAEA safeguard rules, but its functions may be expanded in accordance with future needs. The program developed can be used in other reactors to be built in the country, since it is very practical and allows an effective control of the nuclear material in the facilities. (author)

  8. Nuclear energy - overview of development trends

    International Nuclear Information System (INIS)

    1985-01-01

    Proceeding from the organizational structure of the IAEA selected activities of the IAEA in connection with power reactor safety are dealt with. Based on the IAEA's computerized Power Reactor Information System (PRIS) a survey is presented of the most recent statistical data concerning status and trends of nuclear power plant development throughout the world. The central role of the IAEA in assisting Member States in the utilization of nuclear energy for peaceful purposes is underscored. Finally, a brief account of the state-of-the-art of the USSR's nuclear power programme is given

  9. Development of nuclear energy in Armenia

    International Nuclear Information System (INIS)

    Gevorgyan, A.A.; Galstyan, A.A.

    2010-01-01

    This paper presents an attempt to depict the situation in the Armenian Nuclear Energy Sector with the particular focusing on its further development. Basing on the energy independence and national security strategy principles, the Government of Armenia made a decision to construct a new nuclear unit in the Republic to replace Unit 2 of the Armenian NPP after its decommissioning. The paper shows that the only acceptable way of electricity generation in Armenia is the combined operation of thermal power plants and new nuclear unit, with the use of domestic renewable energy sources. This will allow to cover the Republic's energy demand and to export the excess electricity to the neighboring countries

  10. Nuclear power development in China and India

    International Nuclear Information System (INIS)

    Hara, Taito

    2016-01-01

    China and India are expected to achieve the world's largest energy and electricity consumption because of population and economic growth. In the past, the two countries covered coal demand by domestic coal production, however, these countries have now turned to net importers. From the point of view of energy security improvement, the both countries are actively developing nuclear power. IEA expects that the nuclear power electricity ratio will be 10.4% in China and 6.5% in India in 2040. If it is converted to 1 GW class nuclear power plant, China and India must respectively start to operate 4.9 units and 1.2 units per year up to 2040. In the future, the two countries are expected to play the leading role of nuclear energy development. (author)

  11. Report from the research committee of digital imaging standardization in nuclear medicine

    International Nuclear Information System (INIS)

    Nakamura, Yutaka; Ise, Toshihide; Isetani, Osamu; Ichihara, Takashi; Ohya, Nobuyoshi; Kanaya, Shinichi; Fukuda, Toshio; Horii, Hitoshi.

    1994-01-01

    Since digital scintillation camera systems were developed in 1982, digital imaging is rapidly replacing analog imaging. During the first year, the research committee of digital imaging standardization has collected and analyzed basic data concerning digital examination equipment systems, display equipments, films, and hardware and software techniques to determine items required for the standardization of digital imaging. During the second year, it has done basic phantom studies to assess digital images and analyzed the results from both physical and visual viewpoints. On the basis of the outcome of the research committee's activities and the nationwide survey, the draft of digital imaging standardization in nuclear medicine has been presented. In this paper. the analytical data of the two-year survey, made by the research committee of digital imaging standardization, are presented. The descriptions are given under the following four items: (1) standardization digital examination techniques, (2) standardization of display techniques, (3) the count and pixel of digital images, and (4) standardization of digital imaging techniques. (N.K.)

  12. Nuclear energy and Ecuadorian agriculture development

    International Nuclear Information System (INIS)

    Molineros Andrade, J.

    1979-09-01

    The Ecuadorian Atomic Energy Commission has elaborated a plan for development of nuclear energy, the construction of a 1-3 MW Nuclear Reactor for Research and production of radioisotopes and of the related laboratories. Agriculture is a very important part of this plan, in the following areas: genetics, irrigation, plant and animal nutrition and metabolisms, and pest and disease control. Ecuadorian agriculture institutions have also been considered in this plan. (Author)

  13. Development of nuclear plant Operation Management System

    Energy Technology Data Exchange (ETDEWEB)

    Koide, I.; Okada, T.; Ishida, K. [Chubu Electric Power Co. Inc., Nagoya (Japan)

    1998-09-01

    Recently it has become more important to detect a change in operational characteristics and to take appropriate corrective actions before it deteriorates to an incident in nuclear power plants. Therefore, aiming at earlier detection of a tendency change, swifter corrective actions and more effective application of operational data, we have developed Operation Management System which automatically acquires, accumulates and observes operational data of Hamaoka Nuclear Power Station through cycles. (author)

  14. Development of nuclear plant Operation Management System

    International Nuclear Information System (INIS)

    Koide, I.; Okada, T.; Ishida, K.

    1998-01-01

    Recently it has become more important to detect a change in operational characteristics and to take appropriate corrective actions before it deteriorates to an incident in nuclear power plants. Therefore, aiming at earlier detection of a tendency change, swifter corrective actions and more effective application of operational data, we have developed Operation Management System which automatically acquires, accumulates and observes operational data of Hamaoka Nuclear Power Station through cycles. (author)

  15. Development of nuclear power in Sweden

    International Nuclear Information System (INIS)

    Sokolowski, E.

    1994-01-01

    The history and development of nuclear energetics in Sweden has been described. Up to now 12 units (9 BWR and 3 PWR nuclear reactors) with total 70 TWh electric power is being working in Sweden. If the same power will be installed as a coal-fired units the emissions of 65 million tons of CO 2 , 240,000 tons of SO 2 and 140 tons of NO x would be expected. 1 tab

  16. Scientific codes developed and used at GRS. Nuclear simulation chain

    Energy Technology Data Exchange (ETDEWEB)

    Schaffrath, Andreas; Sonnenkalb, Martin; Sievers, Juergen; Luther, Wolfgang; Velkov, Kiril [Gesellschaft fuer Anlagen und Reaktorsicherheit (GRS) gGmbH, Garching/Muenchen (Germany). Forschungszentrum

    2016-05-15

    Over 60 technical experts of the reactor safety research division of the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH are developing and validating reliable methods and computer codes - summarized under the term nuclear simulation chain - for the safety-related assessment for all types of nuclear power plants (NPP) and other nuclear facilities considering the current state of science and technology. This nuclear simulation chain has to be able to simulate and assess all relevant physical processes and phenomena for all operating states and (severe) accidents. In the present contribution, the nuclear simulation chain developed and applied by GRS as well as selected examples of its application are presented. The latter demonstrate impressively the width of its scope and its performance. The GRS codes can be passed on request to other (national as well as international) organizations. This contributes to a worldwide increase of the nuclear safety standards. The code transfer is especially important for developing and emerging countries lacking the financial means and/or the necessary know-how for this purpose. At the end of this contribution, the respective course of action is described.

  17. Status of nuclear power in developing countries

    International Nuclear Information System (INIS)

    Laue, H.J.

    1982-01-01

    In the context of the world-wide energy situation and the key position energy plays and will play for the economic and social development of any country, the energy demand situation up to the year 2000 is analysed. As a result, the world-wide energy demand will continue to increase, however, mainly in the developing world. Nuclear power is one of the important component in the energy mix of today and in the future. Status of nuclear power application in developing countries up to the end of the century. Any further growth of the peaceful use of nuclear power in developing countries is closely linked with the following requirements: - qualified manpower, - industrial infrastructure, - energy demand and supply assessments, - high investments, - assurance of supply of nuclear fuel and fuel cycle services, - availability of small and medium power reactors. The possible role of the IAEA in developing countries and international measures to remove some of the limitations for the peaceful use of nuclear energy in developing countries are discussed. (orig.)

  18. New trends in nuclear power engineering development

    International Nuclear Information System (INIS)

    Krasin, A.K.

    1974-01-01

    The specific features are considered of three designs of nuclear power plants with fast reactors: three-circuit nuclear power plant with liquid sodium as primary and secondary coolant, in the third circuit water vapor being used as turbine working medium, dual cycle nuclear power plant with pressurized helium as primary coolant and water vapor as turbine working medium, direct cycle nuclear power plant with a dissociating gas (nitrogen tetroxide N 2 O 4 ) as reactor coolant and turbine working medium. The version of the direct cycle nuclear power plant with dissociating N 2 O 4 was proposed and being developed by the Institute of Nuclear Engineering of the Academy of Sciencies of the BSSR. The thermal and physical properties of the dissociating gas allow a high-power-density reactor core to be used with a hard neutron spectra resulting in a high breeding ratio and a short doubling time. The pressure range from 150 to 170 bar was proven for this coolant under laboratory conditions and structural materials were chosen that ensure all the components of the direct cycle nuclear power plant to be workable. At present it is difficult to say which of the three versions is the most advantageous. The further development of a full-scale prototypes of a commercial nuclear power plant with a fast reactor and investigation of their technical and economic parameters remain the problems of utmost importance. A possible use of nuclear reactors is shortly considered for process heat production, in ferrous metallurgy, for hydrogen and new isotope production, and for radiation chemistry as well

  19. Differences in Approach between Nuclear and Conventional Seismic Standards with regard to Hazard Definition - CSNI Integrity And Ageing Working Group

    International Nuclear Information System (INIS)

    Djaoudi, Ali; Labbe, Pierre; Murphy, Andrew; Kitada, Yoshio

    2008-01-01

    The Committee on the safety of Nuclear Installations (CSNI) of the OECD-NEA co-ordinates the NEA activities related to maintaining and advancing the scientific and technological knowledge base of the safety of nuclear installations. The Integrity and Ageing of Components and Structures Working Group of the CSNI is responsible for work related to the development and use of methods, data and information to assess the behaviour of materials and structures. It has three sub-groups, dealing with the integrity of metal components and structures, ageing of concrete structures, and the seismic behaviour of structures. The CSNI, at its meeting in June 2003, agreed to initiate an activity aimed to identify any difference between nuclear and non-nuclear conventional standards and their potential significance with regard to seismic hazards and design methods. There was a perception, mainly in some of the European countries that nuclear seismic hazard and design standards may be lagging behind developments in similar standards for conventional facilities. Adequate answer to such perception, need the examination of the following aspects and their significance on the seismic assessment of structures and components: - The safety philosophy behind the seismic nuclear and conventional standards. - The differences in approach regarding the seismic hazard definition. - The difference in approach regarding the design and the methods of analysis. These topics are examined in this report. Appendices A to H of this report contain a brief description of the conventional and the nuclear approaches in the NEA member countries: Belgium, Canada, Czech Republic, Germany, Japan, South Korea, Spain,and USA. The following general conclusions can be drawn: - The approach adopted by the nuclear seismic standards is more conservative and more reliable (in particular for meeting the continued operation criteria) than the recommended by the currently applicable force based conventional seismic codes

  20. Sustainable nuclear development and public confidence

    International Nuclear Information System (INIS)

    Gagarinski, A.

    2000-01-01

    This report discusses the objective preconditions, which would lead the world community to acceptance of nuclear energy. The following conditions deserve special emphasis: (a) Demographic growth, resulting in the increase of energy demand and promoting the understanding of the fact, that the world energy resources are limited and all possible energy sources, including nuclear ones, should be used. (b) Development of the 'third-world' countries, creating additional energy demand, which cannot be met without nuclear power. (c) Global (and influencing the plans of each country) need of availability and acceptable costs together with reliability and safety of energy supply, and, consequently, the interest to energy sources diversification in order to eliminate the dependence of fossil fuels import. The paper considers the ways to solve this strategic task. Its solution could take a long time (several decades) and should be properly perceived by the generation of specialists now starting their career in nuclear science and industry. Now it is a good time for the new generation of nuclear specialists to solve this problem - the large-scale NPP development is not yet needed, there is a large accumulated experience and perspective ideas, and there is enough time to analyze the problems in detail, propose and prepare the solutions and convince the general public, that these solutions are correct. And then the next phase of nuclear energy development would be based not only on correct technical solutions, but also on a favourable social environment. (authors)

  1. The role of the American Society for Testing and Materials (ASTM) in providing standards to support reliability technology for nuclear power plants

    International Nuclear Information System (INIS)

    Steele, L.E.

    1978-01-01

    ASTM is an international society for managing the development of standards on characteristics and performance of materials, products, systems and services and the promotion of related knowledge. This paper provides on overview of ASTM, emphasizing its contribution to nuclear systems reliability. In so doing, the author, from his perspective as chairman of ASTM committee E 10 on ''Nuclear Applications and the Measurement of Radiation Effects and the Committee on Standards'', illustrates ASTM contributions to the understanding and control of radiation embrittlement of light-water reactor pressure vessels. Four major related taks are summarized and pertinent standards identified. These include: (1) surveillance practice (5 standards), (2) neutron dosimetry (8 standards), (3) specification for steels for nuclear service (7 standards) and (4) basic guidelines for thermal annealing to correct radiation embrittlement (1 standard). This illustration, a specific accomplishment using ASTM standards, is cited within the context of the broader nuclear-related activities of ASTM. (author)

  2. Development of nuclear transmutation technology

    International Nuclear Information System (INIS)

    Park, Won Seok; Song, Tae Young; Yoo, Jae Kwon; Choi, Byung Ho; Shin, Hee Sung; Gil, Chung Sup; Kim, Jung Do.

    1997-08-01

    A basic characteristics and neutronic code development for accelerator driven subcritical reactor have been performed. In the field of basic characteristic study, the world-wide technical trends for a subcritical reactor has been investigated and some new directions for the subcritical system development were investigated. For the analysis of subcritical reactor core, a Montecarlo depletion code was developed by combining LAHET code with ORIGEN2 code. In addition, one-point kinetics equation for subcritical reactor programmed in order to analyze the dynamic behavior of subcritical core. (author). 26 tabs., 49 figs

  3. Criteria, standards and policies regarding decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Detilleux, E.; Lennemann, W.L.

    1977-01-01

    At the end of this century, there will probably be around 2500 operating nuclear power reactors, along with all the other nuclear fuel cycle facilities supporting their operation. Eventually these facilities, one by one, will be shut down and it will be necessary to dispose of them as with any redundant industrial facility or plant. Some parts of a nuclear fuel cycle facility can be dismantled by conventional methods, but those parts which have become contaminated with radioactive nuclear products or induced radioactivity must be subject to rigid controls and restrictions and handled by special dismantling and disposal procedures. In many cases, the resulting quantity of radioactive waste is likely to be relatively large and dismantling quite costly. Decommissioning nuclear facilities is a multifaceted problem involving planners, design engineers, operators, waste managers and regulatory authorities. Preparation for decommissioning should begin as early as site selection and plant design. The corner stone for the preparation of a decommissioning programme is the definition of its extent, meeting the requirements for public and environmental protection during the period that the radioactive material is of concern. The paper discusses the decontamination and decommissioning experience at the Eurochemic fuel reprocessing plant, the implications and the knowledge gained from this experience. It includes the results of technical reviews made by the Nuclear Energy Agency of OECD and the International Atomic Energy Agency regarding decommissioning nuclear facilities. The paper notes the special planning that should be arranged between those responsible for the nuclear facility and competent public authorities who should jointly make a realistic determination of the eventual disposition of the nuclear facility, even before it is built. Recommendations cover the responsibilities of nuclear plant entrepreneurs, designers, operators, and public and regulatory authorities

  4. Nuclear energy in a sustainable development perspective

    International Nuclear Information System (INIS)

    2000-01-01

    The concept of sustainable development, which emerged from the report of the 1987 World Commission on Environment and Development (the Brundtland report), is of increasing interest to policy makers and the public. In the energy sector, sustainable development policies need to rely on a comparative assessment of alternative options, taking into account their economic, health, environmental and social aspects, at local, regional and global levels. This publication by the OECD Nuclear Energy Agency investigates nuclear energy from a sustainable development perspective, and highlights the opportunities and challenges that lie ahead in this respect. It provides data and analyses that may help in making trades-off and choices in the energy and electricity sectors at the national level, taking into account country-specific circumstances and priorities. It will be of special interest to policy makers in the nuclear and energy fields

  5. Development and standardization of Indian aphasia battery

    Directory of Open Access Journals (Sweden)

    Harsimarpreet Kaur

    2017-01-01

    Full Text Available Background: Aphasia is a language disorder which may disrupt an individual's functioning. To plan a mode of therapeutic/rehabilitative work, it is important to assess problems from a neuropsychological perspective focused on remediation of the impaired processes or compensation through the intact processes or both. Aim: Due to the paucity of tests available for the assessment of aphasia in the Indian population with specific colloquial expression, the aim of the present study was to develop an aphasia test for Hindi-speaking population and to provide evidence with its reliability and validity. Methods: The conception of the test took place in two phases: Phase 1 was the development of Indian Aphasia Battery (IAB and Phase 2 was its standardization. IAB was administered along the Hindi adaptation of the Western Aphasia Battery (WAB-H on participants with aphasia, probable aphasia, and healthy volunteers. Outcomes and Results: Based on the results of this study, IAB has a high concurrent validity and test–retest reliability in comparison to WAB-H. The subtests are sensitive enough to contribute to global aphasia quotient as a functional measure of aphasia in Indian brain-damaged patients. Conclusion: IAB is a quick and easy to administer measure for assessment of aphasia in Hindi-speaking population with high reliability and validity.

  6. Developing Ethics and Standards in Action Research

    Directory of Open Access Journals (Sweden)

    Ben Boog

    2008-12-01

    Full Text Available In a globalizing world, what role can social science research – particularly action research – play in order to address the risks of exclusion, poverty, social and physical insecurity and environmental deprivation? More specifically, how can this type of research be conducted in a participatory, responsible, transparent and scientific way? In other words: what about the ethics and standards in action research? This was the main focus of the World Congress on Action Research and Action Learning (August 2006 organized by the University of Groningen and the Higher Education Group of the Northern Netherlands. We begin by discussing the core characteristics of action research with reference to theory and practice. Reflection and action are key constituents of the process through the enactment of action research. The middle section draws upon the research findings presented at the congress and published in a book [B. Boog, J. Preece, M. Slagter and J. Zeelen (Eds. (2008 Towards Quality Improvement of Action Research. Developing Ethics and Standards, Rotterdam/Taipei: Sense Publishers]. Citing authors who contributed chapters to the book mentioned above, we analyze four important subthemes: ‘participation, power and rapport’; ‘quality of research and quality management’; ‘learning to solve your own problems in complex responsive social systems, and ‘heuristics (rules of thumb for action research practice’. Finally, we comment on possible quality improvements for action research. Our remarks relate to the problems of implementing the concept of participation, the ambition of action research to contribute to both knowledge production and social change and the need for systematic reconstruction (scientific validation of action research.

  7. Nuclear energy and the developing world

    International Nuclear Information System (INIS)

    Mustafa, A.

    1982-01-01

    The importance of cooperation between the developed and developing countries with regard to nuclear power is discussed. Moves towards global interdependence were strengthened when OAPEC was set up with proposals for cooperation and depletion of world reserves of gas and oil will encourage this. Developing countries will increasingly look to nuclear power to meet their energy needs, particularly in the light of depleting oil and gas reserves, their increasing cost and the possible 'greenhouse effect' produced by fossil fuels. International cooperation concerning uranium reserves, reprocessing and technology transfer may need World Bank funding. (U.K.)

  8. Development of BC based nuclear instrument

    International Nuclear Information System (INIS)

    Nolida Yussup; Atsushi Birumachi; Kazuaki Shimizu

    2005-01-01

    This paper describes the development of a low-power portable dose rate meter with RS232 interface for data acquisition during 6 months course under MEXT Nuclear Researchers Exchange Program 2004 at JAERI, Japan. The development involved defining the system, selection of detector and components, designing the pre-amplifier, main amplifier, noise discriminator and testing. Software programming was developed on PC to acquire the data via RS232 and display the real-time data. This will allow a small nuclear instrument to have powerful data processing and bigger data storage capability. (Author)

  9. Improvement of the nuclear plant analyzer for Korean Standard Nuclear Power Plants

    International Nuclear Information System (INIS)

    Choi, Sung Soo; Han, Byoung Sub; Suh, Jae Seung; Son, Dae Seong

    2005-04-01

    Accurate analysis of the operating characteristics of Nuclear Power Plants provides valuable information for both norman and abnormal operation. The information can be used for the enhancement of plant performance and safety. Usually, such analysis is performed using computer codes used for plant design or simulators. However, their usages are limited because special expertise is required to use the computer codes and simulators are not portable. Therefore, it deemed necessary to develop an NPA which minimizes those limitations and can be used for the analysis and simulation of Nuclear Power Plants. The purpose of this study is to develop a real-time best-estimate NPA for the Korean Nuclear Power Plants(KSNP). The NPA is an interactive, high fidelity engineering simulator. NPA combines the process model simulating the plant behavior with the latest computer technology such as Graphical User Interface(GUI) and simulation executive for enhanced user interface. The process model includes models for a three-dimensional reactor core, the NSSS, secondary system including turbine and feedtrain, safety auxiliary systems, and various control systems. Through the verification and validation of the NPA, it was demonstrated that the NPA can realistically simulate the plant behaviors during transient and accident conditions

  10. Nuclear-safety institution in France: emergence and development

    International Nuclear Information System (INIS)

    Vallet, B.M.

    1986-01-01

    This research work examines the social construction of the nuclear-safety institution in France, and the concurrent increased focus on the nuclear-risk issue. Emphasis on risk and safety, as primarily technical issues, can partly be seen as a strategy. Employed by power elites in the nuclear technostructure, this diverts emphasis away from controversial and normative questions regarding the political and social consequences of technology to questions of technology that appear to be absolute to the technology itself. Nuclear safety, which started from a preoccupation with risk related to the nuclear energy research and development process, is examined using the analytic concept of field. As a social arena patterned to achieve specific tasks, this field is dominated by a body of state engineers recognized to have high-level scientific and administrative competences. It is structured by procedures and administrative hierarchies as well as by technical rules, norms, and standards. These are formalized and rationalized through technical, economic, political, and social needs; over time; they consolidate the field into an institution. The study documents the nuclear-safety institution as an integral part of the nuclear technostructure, which has historically used the specificity of its expertise as a buffer against outside interference

  11. Problems and solutions in application of IEEE standards at Savannah River Site, Department of Energy (DOE) nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Y.S.; Bowers, T.L.; Chopra, B.J.; Thompson, T.T.; Zimmerman, E.W.

    1993-01-01

    The Department of Energy (DOE) Nuclear Material Production Facilities at the Savannah River Site (SRS) were designed, constructed, and placed into operation in the early 1950's, based on existing industry codes/standards, design criteria, analytical procedures. Since that time, DOE has developed Orders and Polices for the planning, design and construction of DOE Nuclear Reactor Facilities which invoke or reference commercial nuclear reactor codes and standards. The application of IEEE reactor design requirements such as Equipment Qualification, Seismic Qualification, Single Failure Criteria, and Separation Requirement, to non-reactor facilities has been a problem since the IEEE reactor criteria do not directly confirm to the needs of non-reactor facilities. SRS Systems Engineering is developing a methodology for the application of IEEE Standards to non-reactor facilities at SRS

  12. Organization and development of the Brazilian nuclear programme

    International Nuclear Information System (INIS)

    Pinto, C.S.M.; Souza, J.A.M. de; Grinberg, M.; Alves, R.N.; Costa, H.M. da; Grimberg, M.

    1977-01-01

    The paper presents the Brazilian Nuclear Energy Programme, its development, the organizations and the distribution of responsibilities involved in its execution at the present time. The nuclear power policy is established at the Presidency of the Republic and is planned, executed and controlled through the Ministry of Mines and Energy. Directly subject to the Ministry is the Brazilian Nuclear Energy Commission (CNEN), which has regulatory, standardization, licensing, planning and surveillance functions. The nuclear fundamental research and manpower formation are also under CNEN responsibility. Also subject to the Ministry are two companies responsible for the execution of the Programme: the Centrais Eletricas Brasileiras S.A. - Eletrobras, which advises on the granting of permits for the construction and operation of nuclear power plants, and the Empresas Nucleares Brasileiras S.A. - Nuclebras, which holds the monopoly of the nuclear fuel cycle in the country, designs and builds nuclear power plants and provides assistance to the electric utilities and promotes the participation of Brazilian industry. Besides describing the new distribution of regulatory functions given by law to CNEN, the paper gives special emphasis to the large industrial complex in the process of being established through the setting-up of the many Nuclebras subsidiaries in joint venture with German firms under the Industrial Co-operation Agreement Between Brazil and the Federal Republic of Germany in the Field of the Peaceful Uses of Nuclear Energy. The programmes for these subsidiaries are presented and their participation in the Brazilian Nuclear Energy Programme is discussed. The technology transfer aspects of the industrial activities are also discussed. (author)

  13. Analysis of the Current Technical Issues on ASME Code and Standard for Nuclear Mechanical Design(2009)

    International Nuclear Information System (INIS)

    Koo, Gyeong Hoi; Lee, B. S.; Yoo, S. H.

    2009-11-01

    This report describes the analysis on the current revision movement related to the mechanical design issues of the U.S ASME nuclear code and standard. ASME nuclear mechanical design in this report is composed of the nuclear material, primary system, secondary system and high temperature reactor. This report includes the countermeasures based on the ASME Code meeting for current issues of each major field. KAMC(ASME Mirror Committee) of this project is willing to reflect a standpoint of the domestic nuclear industry on ASME nuclear mechanical design and play a technical bridge role for the domestic nuclear industry in ASME Codes application

  14. Report on the Current Technical Issues on ASME Nuclear Code and Standard

    International Nuclear Information System (INIS)

    Koo, Gyeong Hoi; Lee, B. S.; Yoo, S. H.

    2008-11-01

    This report describes the analysis on the current revision movement related to the mechanical design issues of the U.S ASME nuclear code and standard. ASME nuclear mechanical design in this report is composed of the nuclear material, primary system, secondary system and high temperature reactor. This report includes the countermeasures based on the ASME Code meeting for current issues of each major field. KAMC(ASME Mirror Committee) of this project is willing to reflect a standpoint of the domestic nuclear industry on ASME nuclear mechanical design and play a technical bridge role for the domestic nuclear industry in ASME Codes application

  15. Analysis of the Current Technical Issues on ASME Code and Standard for Nuclear Mechanical Design(2009)

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Gyeong Hoi; Lee, B. S.; Yoo, S. H.

    2009-11-15

    This report describes the analysis on the current revision movement related to the mechanical design issues of the U.S ASME nuclear code and standard. ASME nuclear mechanical design in this report is composed of the nuclear material, primary system, secondary system and high temperature reactor. This report includes the countermeasures based on the ASME Code meeting for current issues of each major field. KAMC(ASME Mirror Committee) of this project is willing to reflect a standpoint of the domestic nuclear industry on ASME nuclear mechanical design and play a technical bridge role for the domestic nuclear industry in ASME Codes application

  16. 24 CFR 598.615 - Economic development standards.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 3 2010-04-01 2010-04-01 false Economic development standards. 598... DESIGNATIONS Empowerment Zone Grants § 598.615 Economic development standards. (a) Economic development... the planned use of HUD EZ Grant Funds must meet one of the following economic development standards...

  17. Acceptance of nuclear energy in developed countries

    International Nuclear Information System (INIS)

    Sobajima, Makoto

    1999-03-01

    This paper focuses on the presence of problems, governmental efforts and the state of each people's awareness in accepting nuclear energy especially in developed countries and reviews the past circumstances and recent activities. Significant differences among countries in the popularity of nuclear power depend largely on the environment of the particular country such as energy circumstances and also on the execution of the energy policy. Also it is pointed out that the difference comes from the consciousness of the execution of the people in such a policy they establish and decide whether they accept or not. The analysis, that the French people traditionally believe they cannot control risks and give high degree of trust to their government and specialists, whereas Americans conversely intervene in administration to control risks by themselves and try to change specialist's Judgment, explains one side of polarization in popularity of nuclear energy in the world. Japanese have tended to not to believe the administration probably due to recent continuous scandals of officials and motivation to require disclosure of information and to dispute, which lays on the background of retard of nuclear energy. For resolving the global issues such as warming, it is becoming more important that at least specialists of nuclear technology recover the loosing trust owing to the accidents and scandals through steady activities, show the whole view of trust worthy development plan of nuclear energy and regain the confidence by the people. (author)

  18. Nuclear Medicine in a developing country

    International Nuclear Information System (INIS)

    Wenzel, K.S. von; Rubow, S.M.; Ellmann, A.; Ghoorun, S.

    2002-01-01

    Namibia is a country with 1,8 million inhabitants, of whom the majority has limited access to first world facilities. Nevertheless, medical services of high standard are offered. A Nuclear Medicine Department was established at Windhoek Central Hospital in 1982. A nuclear physician, two nuclear medicine radiographers and a nursing sister staff the department. Equipment includes a Siemens Orbiter and an Elscint Apex SPX Helix gamma camera. Radiopharmaceuticals are obtained from suppliers in South Africa. Investigations performed include musculoskeletal, liver, hepatobiliary, thyroid, renal studies, ventilation perfusion lung scans as well as the following Nuclear Cardiology studies: Gated blood pool scans, Tc-99m pyrophosphate hot spot scans, Tl-201 myocardial perfusion studies, Tc-99m MIBI myocardial perfusion studies and Tl-201 rest-redistribution studies. Problems experienced at the Windhoek Nuclear Medicine department include: Lack of funding and high cost of equipment and radiopharmaceuticals, lack of understanding of Nuclear Medicine by the hospital management and health administrators, and difficulties in procuring short-lived radiopharmaceuticals. Furthermore, the absence of company representatives and spare parts in Namibia leads to loss of time whenever equipment needs to be repaired. Working as the only nuclear medicine physician in a country also poses major problems. Careful management of resources and information drives have helped to sustain the Nuclear Medicine service despite economic problems in the country. Installation of a tele-link between the department in Windhoek Hospital and Tygerberg Hospital in South Africa has greatly assisted to overcome the problem of isolation and lack of back up from fellow specialists. The IAEA has equipped both departments with Hermes workstations (Nuclear Diagnostics) and a tele-link is maintained via modem. The current software provided with the Hermes system is ideally suited to processing of data such as gated

  19. Development of nuclear power plant Risk Monitor

    International Nuclear Information System (INIS)

    Yang Xiaoming; Sun Jinlong; Ma Chao; Wang Lin; Gu Xiaohui; Bao Zhenli; Qu Yong; Zheng Hao

    2014-01-01

    Risk Monitor is a tool to monitor the real-time risk of a nuclear power plant for risk management and comprehensive decision-making, which has been widely used all over the world. The nuclear power plant Risk Monitor applies the real-time risk model with low-complicacy that could reflect the plant's actual configuration, automatically reads the plant's configuration information from the engineering system through the developed interface, and efficiently analyzes the plant's risk Dy the intelligent parallel-computing method in order to provide the risk basement for the safety management of nuclear power plant. This paper generally introduces the background, architecture, functions and key technical features of a nuclear power plant Risk Monitor, and validates the risk result, which could well reflect the plant's risk information and has a significant practical value. (authors)

  20. Development of semiconductor ΔE-E detector chip using standard bipolar IC technology

    International Nuclear Information System (INIS)

    Mishra, Vijay; Kataria, S.K.

    2005-01-01

    A proposal has been made for developing silicon based AE-E detector chip which can be used as particle identifiers in nuclear physics experiments and also in several applications in nuclear industry scenario. The proposed development work employs standard bipolar IC fabrication technology of Bharat Electronics Ltd. and the deliverable products that emerge out will be very cost effective. The present paper discusses the concept, feasibility studies and systematic plan for fabrication, characterization and packaging of the proposed detectors. (author)

  1. The technical development on recycled aggregate concrete for nuclear facility

    International Nuclear Information System (INIS)

    Sukekiyo, M.; Saishu, S.; Ishikura, T.; Ishigure, K.

    2000-01-01

    The large amount of non-radioactive concrete waste generated by decommissioning has a very big impact on the final disposal site. Therefore, NUPEC has been developing technology which recovers at a high ratio the aggregate from the dismantling concrete with a quality which can be used to construct a new nuclear power plant. The developed high-quality recycled aggregate meets the quality standards of the natural aggregate stipulated by the Japanese architectural standard specifications for nuclear power plant facilities. As a result of these experiments, it was confirmed that the recycled concrete which used this high-quality recycled aggregate had a performance equal or better than ordinary concrete which used natural aggregate. (authors)

  2. Development of a Secondary Neutron Fluence Standard at GELINA

    International Nuclear Information System (INIS)

    Heyse, Jan; Eykens, Roger; Moens, Andre; Plompen, Arjan J.M.; Schillebeeckx, Peter; Wynants, Ruud; Anastasiou, Maria

    2013-06-01

    The MetroFission project, a Joint Research Project within the European Metrology Research Program, aims at addressing a number of metrological problems involved in the design of proposed Generation IV nuclear reactors. One of the objectives of this multidisciplinary project is the improvement of neutron cross section measurement techniques in order to arrive at uncertainties as required for the design and safety assessment of new generation power plants and fuel cycles. This objective is in line with the 'Uncertainty and target accuracy assessment for innovative systems using recent covariance data evaluations' published by a working party of the OECD Nuclear Energy Agency in 2008. These requests are often very challenging, being at or beyond the state-of-the-art in neutron measurements, which is set by self-normalizing methods and the neutron data standards used at laboratories where the data are measured. A secondary neutron fluence standard has been developed and calibrated at the neutron time-of-flight facility GELINA of the JRC's Institute for Reference Materials and Measurements (IRMM). It consists of a flux monitor, a reference ionization chamber containing a 10 B layer and a 235 U layer, and a parallel plate ionization chamber with 8 well characterized 235 U deposits. These devices are used to determine the neutron fluence, based on the well-known neutron induced fission reaction on 235 U. All deposits have been prepared and characterized at the IRMM target preparation lab. The secondary fluence standard at the GELINA facility can be used for reliable determination of the efficiency of fluence measurement devices used in neutron data measurements at IRMM and elsewhere. It is an essential tool to reliably calibrate fluence normalization devices used in neutron time-of-flight cross section measurements. (authors)

  3. Standard specification for nuclear-grade beryllium oxide powder

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    This specification defines the physical and chemical requirements of nuclear-grade beryllium oxide (BeO) powder to be used in fabricating nuclear components. This specification does not include requirements for health and safety. It recognizes the material as a Class B poison and suggests that producers and users become thoroughly familiar with and comply to applicable federal, state and local regulations and handling guidelines. Special tests and procedures are given

  4. Radiation protection standards in nuclear-fuel manufacturing

    International Nuclear Information System (INIS)

    Nilson, R.; Malody, C.W.

    1983-01-01

    The authors discuss principally the impact of changes in 10 CFR 20 on the commercial nuclear-fuel-fabrication industry, for which the impact appears to be the most severe, dwelling on the changes affecting occupational exposures. They conclude that the credibility of the nuclear industry as a comparably safe industry could be harmed by the continuing examination of apparent problem areas without establishing an overall perspective regarding employee safety. 21 references

  5. Intellectual property disclosure in standards development

    NARCIS (Netherlands)

    Bekkers, R.N.A.; Catalini, C.; Martinelli, A.; Simcoe, T.

    2012-01-01

    Firms often collaborate to produce inter-operability standards so that independently designed products can work together. When this process takes place in a Standard Setting Organization (SSO), participants are typically required to disclose any intellectual property rights (IP) that would be

  6. Developing people for the new nuclear generation

    International Nuclear Information System (INIS)

    Gordon, C.; Fluke, R.; Moya, R.

    2005-01-01

    The importance of having high-calibre people and the urgency in ensuring adequate numbers of knowledgeable staff has been recognized in the nuclear industry world wide. This paper describes how Nuclear Safety Solutions Limited is addressing these challenges by adopting a pro-active approach to training and development. This paper describes the integrated processes and tools used to ensure: adequate numbers of appropriately qualified staff to meet current and projected business needs, suitably qualified staff are assigned to projects for clients, and individual staff development. NSS uses a Qualification and Experience (Q and E) Registry to ensure the proper functioning of these processes. (author)

  7. A development approach for nuclear thermal propulsion

    International Nuclear Information System (INIS)

    Buden, D.

    1992-01-01

    The cost and time to develop nuclear thermal propulsion systems are very approach dependent. The objectives addressed are the development of an ''acceptable'' nuclear thermal propulsion system that can be used as part of the transportation system for people to explore Mars and the enhancement performance of other missions, within highly constrained budgets and schedules. To accomplish this, it was necessary to identify the cost drivers considering mission parameters, safety of the crew, mission success, facility availability and time and cost to construct new facilities, qualification criteria, status of technologies, management structure, and use of such system engineering techniques as concurrent engineering

  8. Robot development for nuclear material processing

    International Nuclear Information System (INIS)

    Pedrotti, L.R.; Armantrout, G.A.; Allen, D.C.; Sievers, R.H. Sr.

    1991-07-01

    The Department of Energy is seeking to modernize its special nuclear material (SNM) production facilities and concurrently reduce radiation exposures and process and incidental radioactive waste generated. As part of this program, Lawrence Livermore National Laboratory (LLNL) lead team is developing and adapting generic and specific applications of commercial robotic technologies to SNM pyrochemical processing and other operations. A working gantry robot within a sealed processing glove box and a telerobot control test bed are manifestations of this effort. This paper describes the development challenges and progress in adapting processing, robotic, and nuclear safety technologies to the application. 3 figs

  9. Development of compact nuclear simulator

    International Nuclear Information System (INIS)

    Ham, Chang Shik; Kwon, Kee Choon; Lyu, Sung Pil; Kim, Young Gil; Lee, Dong Young; Kim, Jung Taek; Jung, Chul Hwan; Hwang, In Gu; Kim, Jung Soo; Park, Won Man

    1987-12-01

    Everyone knows that the TMI accident resulted from the defect of the man-machine interface of main control room design and of the quality of the operators. So it is very important and urgent subject to improve the quality of the operators by training them to understand the dynamic transient phenomena in plant system. Therefore it is necessary to develop CNS which is very efficient to train operators, operation and maintenance supervisors, maintenance personnel and inspectors of regulation committee to understand the dynamic transient phenomena. (Author)

  10. Nuclear energy and sustainable development: recent trends

    International Nuclear Information System (INIS)

    Singh, B.P.

    2012-01-01

    During the last 50 years or so there is enormous development in various fields like agriculture, industry, medicine, etc. Further, the population on this globe has increased many folds. In order to cater to the needs of the present population there is an increasing demand of electricity in the society. Per capita electricity consumption also is an index of development in the country. Considering the facts like green house effect and global warming, nuclear energy is the better option. But at the same time there are some critical issues like nuclear waste management globally and availability of fissile material in the context of our country. Research and development are going on to take care of these issues where scientists and engineers are working on alternative fuel cycle and new reactor types, for example Accelerator Driven Subcritical (ADS) System is one of them. Since, ADS reactor is a subcritical system, safety related issues are in fact of low concern relative to existing critical reactors. As a matter of fact, the ADS system is the combination of a particle accelerator and a nuclear reactor. In this talk, a detailed description of the need of energy in our country, which can only be met if nuclear energy contributes a substantial energy requirement, will be presented. Further, how the nuclear waste management issues may be addressed, with the new ADS system will also be presented. (author)

  11. Nuclear energy an asset for sustainable development

    International Nuclear Information System (INIS)

    Anon.

    2007-01-01

    The energy issue is now a worldwide concern. It is showed that nuclear energy combined with renewable energies are the only efficient response to face the challenge of climate warming by cutting drastically the emission of greenhouse gases in the electricity production. The second asset of nuclear energy is to be able to meet the growing need for electric power of developing countries. Energy conservation is a good thing to do in western countries but it is far to be sufficient. The success of France's nuclear energy program has enabled the country to be independent from other countries concerning its electricity production, to produce electricity at moderate and stable costs even on the long term, and to develop nuclear industry operators that are world leaders. According to the 28 june 2006 bill that clarifies the management of radioactive wastes, the disposal of high-level radioactive wastes in deep geological layers, will be put into service in 2025. The law has let the possibility of recovering the waste containers during a certain period after their burial if new solutions will have emerged. In the context of an expected renaissance of nuclear energy, the EPR (European Pressurized Reactor) is a valuable offer that must be developed. The construction of an EPR unit on the Flamanville site is necessary to perfect its design. (A.C.)

  12. Safety policy for nuclear power development

    International Nuclear Information System (INIS)

    Uchida, Hideo

    1987-01-01

    The report discusses various aspects of the safety policy for nuclear power development in Japan. Nuclear power development over three decades in Japan has led to operating performance which is highly safe and reliable. This has been appreciated internationally. Discussed here is the Japanese basic safety policy for nuclear power development that is essential first to design, manufacture and construction using high technology. The current careful quality assurance and reliable operation management by skilled operators are relied upon, on the basis of the fact that measures to prevent abnormal events are given first priority rather than those to mitigate consequences of abnormal events or accidents. Lessons learned from accidents and failures within or outside Japan such as the TMI accident and Chernobyl accident have been reflected in the improvement of safety through careful and thorough examinations of them. For further improvement in nuclear safety, deliberate studies and investigations on severe accidents and probabilistic safety assessment are considered to be important. Such efforts are currently being promoted. For this purpose, it is important to advance international cooperation and continue technical exchanges, based on operation experience in nuclear power stations in Japan. (Nogami, K.)

  13. Core Technology Development of Nuclear spin polarization

    International Nuclear Information System (INIS)

    Yoo, Byung Duk; Gwon, Sung Ok; Kwon, Duck Hee; Lee, Sung Man

    2009-12-01

    In order to study nuclear spin polarization, we need several core technologies such as laser beam source to polarize the nuclear spin, low pressured helium cell development whose surface is essential to maintain polarization otherwise most of the polarized helium relaxed in short time, development of uniform magnetic field system which is essential for reducing relaxation, efficient vacuum system, development of polarization measuring system, and development of pressure raising system about 1000 times. The purpose of this study is to develop resonable power of laser system, that is at least 5 watt, 1083 nm, 4GHz tuneable. But the limitation of this research fund enforce to develop amplifying system into 5 watt with 1 watt system utilizing laser-diod which is already we have in stock. We succeeded in getting excellent specification of fiber laser system with power of 5 watts, 2 GHz linewidth, more than 80 GHz tuneable

  14. Nuclear generation cost and nuclear research development fund

    International Nuclear Information System (INIS)

    Kim, S. S.; Song, G. D.

    2000-01-01

    The main objective of this study is to analyze the effects of nuclear R and D fund to nuclear generation cost and to assess the adaptability of fund size through the comparison with the nuclear research fund in Japan. It was estimated that nuclear R and D fund increased the average annual unit cost of nuclear power generation by 1.14 won/kWh. When the size of nuclear R and D fund is compared with that in Japan, this study suggests that the current nuclear R and D fund should be largely increased taking into consideration the ratio of R and D fund to nuclear generation

  15. Search for adequate quality standards for neutron radiography of nuclear fuel

    International Nuclear Information System (INIS)

    Domanus, J.C.

    1983-01-01

    Unlike in other fields of industrial radiography, where standard methods and procedures are used to control the quality of the radiographic image, no such standard exists for neutron radiography of nuclear fuel. To fill that gap it was felt that standardization work ought to be started in that field, too. Accordingly in 1979 an Euratom Neutron Radiography Working Group was constituted, which initiated standardization work in the field of neutron radiography of nuclear fuel. Finding adequate standards for image quality of neutron radiographs and checking the accuracy of dimension measurements from them were given first priority. (Auth.)

  16. Developing countries' motivation to use nuclear technology

    International Nuclear Information System (INIS)

    Ratsch, U.

    1990-01-01

    Governments of various developing countries see nuclear energy as an important tool for at least three political goals: Firstly, the expected rise in future energy demand, so they argue, can only be met if nuclear electricity production in the Third World is expanded. Fossil sources are supposed to become increasingly scarce and expensive, and they are also seen to be ecologically damaging. Technologies to harness renewable energy sources are not yet mature and still too costly. Secondly, nuclear technology is seen as one of the most advanced technologies. Mastering of it might help to diminish the technological gap between the First and the Third World. Thirdly, scientific progress in developing countries is hoped to be accelerated by operating research reactors in these countries. All of these arguments ought to be taken as serious motivations. (orig./HSCH) [de

  17. Developments in emergency planning within Scottish nuclear

    International Nuclear Information System (INIS)

    Simpson, A.

    2000-01-01

    Scottish Nuclear has recently completed a major program of improvements to its nuclear emergency facilities. The improvements include the construction of a purpose built Off-Site Emergency Centre for each of its two power stations and the development of a computer based information management system to facilitate the rapid distribution of information on an emergency to local, regional and national agencies. A computer code has also been developed to allow the rapid assessment of the effects of any accidental release on the local population. The improvements to the emergency facilities have been coupled with changes in local and national arrangements for dealing with a civil nuclear emergency. The use of airborne surveying techniques for rapidly determining levels of deposited activity following an accident is also being examined and preliminary airborne surveys have been carried out. (author)

  18. Advanced LWR Nuclear Fuel Cladding Development

    International Nuclear Information System (INIS)

    Bragg-Sitton, S.; Griffith, G.

    2012-01-01

    The Advanced Light Water Reactor (LWR) Nuclear Fuel Development Research and Development (R and D) Pathway encompasses strategic research focused on improving reactor core economics and safety margins through the development of an advanced fuel cladding system. To achieve significant operating improvements while remaining within safety boundaries, significant steps beyond incremental improvements in the current generation of nuclear fuel are required. Fundamental enhancements are required in the areas of nuclear fuel composition, cladding integrity, and fuel/cladding interaction to allow improved fuel economy via power uprates and increased fuel burn-up allowance while potentially improving safety margin through the adoption of an 'accident tolerant' fuel system that would offer improved coping time under accident scenarios. In a staged development approach, the LWRS program will engage stakeholders throughout the development process to ensure commercial viability of the investigated technologies. Applying minimum performance criteria, several of the top-ranked materials and fabrication concepts will undergo a rigorous series of mechanical, thermal and chemical characterization tests to better define their properties and operating potential in a relatively low-cost, nonnuclear test series. A reduced number of options will be recommended for test rodlet fabrication and in-pile nuclear testing under steady-state, transient and accident conditions. (author)

  19. Remote tool development for nuclear dismantling operations

    International Nuclear Information System (INIS)

    Craig, G.; Ferlay, J.C.; Ieracitano, F.

    2003-01-01

    Remote tool systems to undertake nuclear dismantling operations require careful design and development not only to perform their given duty but to perform it safely within the constraints imposed by harsh environmental conditions. Framatome ANP NUCLEAR SERVICES has for a long time developed and qualified equipment to undertake specific maintenance operations of nuclear reactors. The tool development methodology from this activity has since been adapted to resolve some very challenging reactor dismantling operations which are demonstrated in this paper. Each nuclear decommissioning project is a unique case, technical characterisation data is generally incomplete. The development of the dismantling methodology and associated equipment is by and large an iterative process combining design and simulation with feasibility and validation testing. The first stage of the development process involves feasibility testing of industrial tools and examining adaptations necessary to control and deploy the tool remotely with respect to the chosen methodology and environmental constraints. This results in a prototype tool and deployment system to validate the basic process. The second stage involves detailed design which integrates any remaining technical and environmental constraints. At the end of this stage, tools and deployment systems, operators and operating procedures are qualified on full scale mock ups. (authors)

  20. Standard Specification for Nuclear Facility Transient Worker Records

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1995-01-01

    1.1 This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers. 1.2 This specification applies to records to be used for in-processing only. 1.3 This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications). 1.4 This specification does not reduce any regulatory requirement for records retention at a licensed nuclear facility. Note 1—Nuclear facilities operated by the U.S. Department of Energy (DOE) are not licensed by the U.S. Nuclear Regulatory Commission (NRC), nor are other nuclear facilities that may come under the control of the U.S. Department of Defense (DOD) or individual agreement states. The references in this specification to licensee, the U.S. NRC Regulatory Guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD...

  1. Nuclear development in the United States

    International Nuclear Information System (INIS)

    Brewer, S.

    1983-01-01

    The history of the nuclear development in the United States has been one of international cooperation relations so far. The United States is to offer the technical information on atomic energy utilization to foreign countries in exchange for the guarantee that they never attempt to have or develop nuclear weapons. Actually, the United States has supplied the technologies on nuclear fuel cycle and other related fields to enable other countries to achieve economical and social progress. The Department of Energy clarified the public promise of the United States regarding the idea of international energy community. The ratio of nuclear power generation to total electric power supply in the United States exceeded 12%, and will exceed 20% by 1990. Since 1978, new nuclear power station has not been ordered, and some of the contracted power stations were canceled. The atomic energy industry in the United States prospered at the beginning of 1970s, but lost the spirit now, mainly due to the institutional problems rather than the technical ones. As the policy of the government to eliminate the obstacles, the improvement of the procedure for the permission and approval, the establishment of waste disposal capability, the verification of fast breeder reactor technology and the promotion of commercial fuel reprocessing were proposed. The re-establishment of the United States as the reliable supplier of atomic energy service is the final aim. (Kako, I.)

  2. Evaluation of post-LOCA long term cooling performance in Korean standard nuclear power plants

    International Nuclear Information System (INIS)

    Bang, Young Seok; Jung, Jae Won; Seul, Kwang Won; Kim, Hho Jung

    2001-01-01

    The post-LOCA long term cooling (LTC) performance of the Korean Standard Nuclear Power Plant (KSNPP) is analyzed for both small break loss-of-coolant accidents (LOCA) and large break LOCA at cold leg. The RELAP5/MOD3.2.2 beta code is used to calculate the LTC sequences based on the LTC plan of the Korean Standard Nuclear Power Plants (KSNPP). A standard input model is developed such that LOCA and the followed LTC sequence can be calculated in a single run for both small break LOCA and large break LOCA. A spectrum of small break LOCA ranging from 0.02 to 0.5 ft 2 of break area and a double-ended guillotine break are analyzed. Through the code calculations, the thermal-hydraulic behavior and the boron behavior are evaluated and the effect of the important action including the safety injection tank (SIT) isolation and the simultaneous injection in LTC procedure is investigated. As a result, it is found that the sufficient margin is available in avoiding the boron precipitation in the core. It is also found that a further specific condition for the SIT isolation action need to be setup and it is recommended that the early initiation of the simultaneous injection be taken for larger break LTC sequences. (author)

  3. Development of Australia's radiation protection standards

    International Nuclear Information System (INIS)

    Mason, G.C.; Lokan, K.H.

    1994-01-01

    Australia is revising its existing recommendations concerning radiation protection in the light of guidance from the International Commission on Radiological Protection's Publication 60 and the International Atomic Energy Agency's revision of its Basic Safety Standards. The paper discusses the major refinements of the ICRP's recommendations and the additional guidance on its practical implementation offered by the IAEA's new Basic Safety Standards. Following public comment, the revised Australian recommendations are expected to be adopted by the end of 1994. 15 refs

  4. Challenges for development and provision of metrological quality control tools in nuclear safeguards, nuclear forensics and nuclear security

    International Nuclear Information System (INIS)

    Aregbe, Y.; Richter, S.; Jakopic, R.; Bauwens, J.; Truyens, J.; Sturm, M.; Bujak, R.; Eykens, R.; Kehoe, F.; Kuehn, H.; Hennessy, C.

    2013-01-01

    Joint advancements in quality control tools and measurement sciences of international reference and safeguards laboratories include: -) successful integration of the Modified Total Evaporation technique (MTE) as a new tool for routine thermal ionization mass spectrometry in nuclear safeguards and security, -) research and feasibility studies for the development of new materials standard, particularly for nuclear forensics (Certified Reference Materials - CRMs for age-dating), -) quality control tools to support the additional protocol and nuclear security (particle CRMs, NUSIMEP (inter-laboratory comparisons for U particle analysis), and -) scientific/technical advice, training and knowledge transfer. The European Safeguards Research and Development Association (ESARDA), the Institute of Nuclear Materials Management (INMM) and the CETAMA Commission from the French Commission of Atomic Energy and Alternative Energies (CEA/CETAMA) and the International Atomic Energy Agency (IAEA) Technical Meetings are the platforms to exchange views on the needs and challenges for new Quality Control tools for nuclear safeguards and security. The paper is followed by the slides of the presentation

  5. States and tendencies of German standards in the field of nuclear filter technology

    International Nuclear Information System (INIS)

    Fichtner, N.; Sinhuber, D.

    1977-01-01

    The current situation in the Federal Republic of Germany with regard to standards and guidelines in the field of filter technology, as they apply to nuclear technology, is first presented. A detailed discussion follows of the results arrived at by the Nuclear Technology Standards Committee in its deliberations on the Standards' project DIN 25 414 'Ventilation equipment in nuclear power stations'. Particular attention is paid to the technical safety requirements for particulate filters, filter casings and filter housings, and methods of testing. The results so far obtained as regards filters in ventilation plant for pressurized water reactors are also dealt with

  6. Recent developments in nuclear data for ADS

    International Nuclear Information System (INIS)

    Talou, P.; Chadwick, M.B.; Young, P.G.

    2003-01-01

    Modern particle accelerators offer new opportunities to dramatically reshape the way we think about nuclear energy, and challenge some of the thorniest problems linked to its industrial use, e.g. nuclear waste. A powerful proton accelerator driving a sub-critical fission reactor could be used for producing energy more safely and burning up the extra spent fuel which so far has been stored in geological repositories. Although large R and D efforts are required to successfully implement such Accelerator Driven Systems (ADS), an important theoretical effort is also required to extend the nuclear data libraries, originally developed for existing nuclear reactors needs. The energies and isotopes involved in ADS do not necessarily overlap the range covered by the current nuclear reactors, and therefore there is a strong and urgent need to review and complement the nuclear cross sections databases to efficiently and safely build these ADS. In this workshop, we will review some of the strength and deficiencies in the existing nuclear data libraries, for applications to ADS projects. A major step forward to extend these libraries has been achieved recently by the release of the LA150 cross section library [M.B. Chadwick et al., NSE 131, 293 (1999)], evaluating reactions cross sections for different materials important for ADS, up to 150 MeV incident energies. We will devote a rather large fraction of theses lectures to present the latest developments in LA150. We will also present various numerical simulations performed in order to test and benchmark this new data library. Such evaluations rely on nuclear reaction calculations performed with the GNASH code, and on available experimental data. We will therefore briefly review the physical models used in these calculations and present their importance in the GNASH code. Another part in developing accurate nuclear data library consists in the evaluation of available experimental data, as an attempt to significantly reduce the

  7. Recent developments in nuclear data for ADS

    Energy Technology Data Exchange (ETDEWEB)

    Talou, P [T-16, Nuclear Physics Group, Theoretical Division, Los Alamos National Laboratory, Los Alamos (United States); Chadwick, M B [T-16, Nuclear Physics Group, Theoretical Division, Los Alamos National Laboratory, Los Alamos (United States); Young, P G [T-16, Nuclear Physics Group, Theoretical Division, Los Alamos National Laboratory, Los Alamos (United States)

    2003-06-15

    Modern particle accelerators offer new opportunities to dramatically reshape the way we think about nuclear energy, and challenge some of the thorniest problems linked to its industrial use, e.g. nuclear waste. A powerful proton accelerator driving a sub-critical fission reactor could be used for producing energy more safely and burning up the extra spent fuel which so far has been stored in geological repositories. Although large R and D efforts are required to successfully implement such Accelerator Driven Systems (ADS), an important theoretical effort is also required to extend the nuclear data libraries, originally developed for existing nuclear reactors needs. The energies and isotopes involved in ADS do not necessarily overlap the range covered by the current nuclear reactors, and therefore there is a strong and urgent need to review and complement the nuclear cross sections databases to efficiently and safely build these ADS. In this workshop, we will review some of the strength and deficiencies in the existing nuclear data libraries, for applications to ADS projects. A major step forward to extend these libraries has been achieved recently by the release of the LA150 cross section library [M.B. Chadwick et al., NSE 131, 293 (1999)], evaluating reactions cross sections for different materials important for ADS, up to 150 MeV incident energies. We will devote a rather large fraction of theses lectures to present the latest developments in LA150. We will also present various numerical simulations performed in order to test and benchmark this new data library. Such evaluations rely on nuclear reaction calculations performed with the GNASH code, and on available experimental data. We will therefore briefly review the physical models used in these calculations and present their importance in the GNASH code. Another part in developing accurate nuclear data library consists in the evaluation of available experimental data, as an attempt to significantly reduce the

  8. SU-F-J-100: Standardized Biodistribution Template for Nuclear Medicine Dosimetry Collection and Reporting

    Energy Technology Data Exchange (ETDEWEB)

    Kesner, A [University of Colorado, Anschutz Medical Campus, Aurora, Colorado (United States); Poli, G [International Atomic Energy Agency, Vienna, Vienna (Austria); Beykan, S; Lassman, M [University of Wuerzburg, Wuerzberg, Wuerzberg (Germany)

    2016-06-15

    Purpose: As the field of Nuclear Medicine moves forward with efforts to integrate radiation dosimetry into clinical practice we can identify the challenge posed by the lack of standardized dose calculation methods and protocols. All personalized internal dosimetry is derived by projecting biodistribution measurements into dosimetry calculations. In an effort to standardize organization of data and its reporting, we have developed, as a sequel to the EANM recommendation of “Good Dosimetry Reporting”, a freely available biodistribution template, which can be used to create a common point of reference for dosimetry data. It can be disseminated, interpreted, and used for method development widely across the field. Methods: A generalized biodistribution template was built in a comma delineated format (.csv) to be completed by users performing biodistribution measurements. The template is available for free download. The download site includes instructions and other usage details on the template. Results: This is a new resource developed for the community. It is our hope that users will consider integrating it into their dosimetry operations. Having biodistribution data available and easily accessible for all patients processed is a strategy for organizing large amounts of information. It may enable users to create their own databases that can be analyzed for multiple aspects of dosimetry operations. Furthermore, it enables population data to easily be reprocessed using different dosimetry methodologies. With respect to dosimetry-related research and publications, the biodistribution template can be included as supplementary material, and will allow others in the community to better compare calculations and results achieved. Conclusion: As dosimetry in nuclear medicine become more routinely applied in clinical applications, we, as a field, need to develop the infrastructure for handling large amounts of data. Our organ level biodistribution template can be used as a

  9. Standard Review Plan for the review of safety analysis reports for nuclear power plants, Revision No. 7 to Section 9

    International Nuclear Information System (INIS)

    1978-03-01

    Revision No. 1 to Section 9 of the Standard Review Plan incorporates changes that have been developed since the original issuance in September 1975, many of which are editorial in nature, to reflect current staff practice in the review of safety analysis reports for nuclear power plants

  10. Nuclear energy sustainable development and public awareness

    International Nuclear Information System (INIS)

    Murty, G.S.

    2001-01-01

    This paper provides the latest information about the importance of energy needs and its growth in the years to come, the role of the nuclear energy and the need for public awareness and acceptability of the programs to achieve sustainable development

  11. A complete analysis of a nuclear building to nuclear safety standards

    International Nuclear Information System (INIS)

    Bergeretto, G.; Giuliano, V.; Lazzeri, L.

    1975-01-01

    The nuclear standards impose on the designer the necessity of examining the loads, stresses and strains in a nuclear building even under extreme loading conditions, both due to plant malfunctions and environmental accidents. It is necessary then to generate, combine and examine a tremendous amount of data; really the lack of symmetry and general complication of the structures and the large number of loading combinations make an automatic analysis quite necessary. A largely automatized procedure is presented in view of solving the problem by a series of computer programs linked together as follows. After the seismic analysis has been performed by (SADE CODE) these data together with the data coming from thermal specifications, weight, accident descriptions etc. are fed into a finite element computer code (SAP4) for analysis. They are processed and combined by a computer code (COMBIN) according to the loading conditions (the usual list in Italy is given and briefly discussed), so that for each point (or each selected zone) under each loading condition the applied loads are listed. These data are fed to another computer code (DTP), which determines the amount of reinforcing bars necessary to accommodate the most severe of the loading conditions. The Aci 318/71 and Italian regulation procedures are followed; the characteristics of the program are briefly described and discussed. Some particular problems are discussed, e.g. the thermal stresses due to normal and accident conditions, the inelastic behavior of some frame elements (due to concrete cracking) is considered by means of an 'ad hoc' code. Typical examples are presented and the results are discussed showing a relatively large benefit in considering this inelastic effect

  12. Defining nuclear medical file formal based on DICOM standard

    International Nuclear Information System (INIS)

    He Bin; Jin Yongjie; Li Yulan

    2001-01-01

    With the wide application of computer technology in medical area, DICOM is becoming the standard of digital imaging and communication. The author discusses how to define medical imaging file formal based on DICOM standard. It also introduces the format of ANMIS system the authors defined the validity and integrality of this format

  13. Developing a standardized healthcare cost data warehouse.

    Science.gov (United States)

    Visscher, Sue L; Naessens, James M; Yawn, Barbara P; Reinalda, Megan S; Anderson, Stephanie S; Borah, Bijan J

    2017-06-12

    Research addressing value in healthcare requires a measure of cost. While there are many sources and types of cost data, each has strengths and weaknesses. Many researchers appear to create study-specific cost datasets, but the explanations of their costing methodologies are not always clear, causing their results to be difficult to interpret. Our solution, described in this paper, was to use widely accepted costing methodologies to create a service-level, standardized healthcare cost data warehouse from an institutional perspective that includes all professional and hospital-billed services for our patients. The warehouse is based on a National Institutes of Research-funded research infrastructure containing the linked health records and medical care administrative data of two healthcare providers and their affiliated hospitals. Since all patients are identified in the data warehouse, their costs can be linked to other systems and databases, such as electronic health records, tumor registries, and disease or treatment registries. We describe the two institutions' administrative source data; the reference files, which include Medicare fee schedules and cost reports; the process of creating standardized costs; and the warehouse structure. The costing algorithm can create inflation-adjusted standardized costs at the service line level for defined study cohorts on request. The resulting standardized costs contained in the data warehouse can be used to create detailed, bottom-up analyses of professional and facility costs of procedures, medical conditions, and patient care cycles without revealing business-sensitive information. After its creation, a standardized cost data warehouse is relatively easy to maintain and can be expanded to include data from other providers. Individual investigators who may not have sufficient knowledge about administrative data do not have to try to create their own standardized costs on a project-by-project basis because our data

  14. EURATOM work on standard defects and dimensional measurements in neutron radiography of nuclear fuel elements

    International Nuclear Information System (INIS)

    Domanus, J.C.

    1981-10-01

    In 1979 a working group on neutron radiography was formed at Euratom. The purpose of this group is the standardization of neutron radiographic methods in the field of nuclear fuel. First priority was given to the development of image quality indicators and standard objects for the determination of accuracy of dimensional measurements from neutron radiographs. For that purpose beam purity and sensitivity indicators as well as a calibration fuel pin were designed and fabricated at Risoe. All the Euratom neutron radiography centers have recieved the above items for comparative neutron radiography. The measuring results obtained, using various measuring apparatus, will form the basis to formulate conclusions about the best measuring methods and instruments to be used in that field. (author)

  15. Post-LOCA long term cooling performance in Korean standard nuclear power plants

    International Nuclear Information System (INIS)

    Bang, Young Seok; Jung, Jae Won; Seul, Kwang Won; Kim, Hho Jung

    1999-01-01

    The post-LOCA long term cooling (LTC) performance of the Korean Standard Nuclear Power Plant (KSNPP) is analyzed for both small break LOCA and large break LOCA. The RELAP5/MOD3.2.2 code is used to calculate the LTC sequences based on the LTC plan of the KSNPP. A standard input model is developed such that LOCA and the followed LTC sequence can be calculated in a single run for both small break LOCA and large break LOCA. A spectrum of small break LOCA ranging from 0.02 to 0.5 ft 2 of break area and a double-ended guillotine break are analyzed. Through the code calculations, the thermal-hydraulic behavior and the boron behavior are evaluated and the effect of the important manual action including the safety injection tank isolation in LTC procedure is investigated

  16. Development perspectives of nuclear energy in Morocco

    International Nuclear Information System (INIS)

    Mekki-Berrada, A.

    1987-01-01

    Morocco is on the way to developing and gaining access to advanced technologies which will allow it to take good advantage of its natural resources. Most of the fuels necessary for electricity production have to be imported. Nuclear energy appears a better alternative to imported oil or coal, mainly due to kWh price competitivness, great potential of uranium in phosphates and to the limitations placed on the coal option by harbour and transport infrastructure. The first nuclear power plant is planned to go into operation in the year 2000

  17. Transferring Nuclear Knowledge by NPP Simulators Developers

    International Nuclear Information System (INIS)

    Levchenko, A.; Duginov, O.; Levchenko, V.

    2016-01-01

    Full text: In relation to nuclear power, safety is closely linked with the human factor. Knowledge and skills of staff should more closely match the needs of the industry and employers. This can be achieved through more efficient training using simulators. Such simulators must be available at all stages of study and cover the needs of trainees with different levels of knowledge. Simulator developers can solve this problem by implement knowledge management in the using of simulators for practical training. Due to the nature of their activities, they have everything needed for this. This paper describes the solutions of Simulation Systems Ltd Company for nuclear power plants, universities and other parties. (author

  18. Nuclear energy research and development in France

    International Nuclear Information System (INIS)

    Patarin, L.

    1981-02-01

    Having described the general organization and main participants in charge of nuclear energy development in France, headed by the C.E.A. since the start of this activity at the end of World War II, the author gives a glimpse of the programmes shared out between four main headings: fundamental research, reactors, fuel cycle and nuclear safety. Two tables sum up the financial means of the C.E.A. in 1981 on the one hand and the personnel strengths on the other. A graph also shows the operational framework of the C.E.A. and its main subsidiaries and participations [fr

  19. Manpower training and development for nuclear power

    International Nuclear Information System (INIS)

    Bauer, E.

    1979-01-01

    Determination of the manpower required for implementation of a nuclear programme is a very important factor from the national viewpoint, as it is drawn from many sectors of industry. The author provides a case-study of manpower requirements in France. He is in favour of the establishment of a manpower programme within the educational system, involving schools and universities since technicians and engineers have an important role to play throughout the different stages of a nuclear programme. In this context, he describes the IAEA contribution to acquisition of know-how by means of training courses for developing countries. (NEA) [fr

  20. Nuclear power project construction quality acceptance standards Implementation and discussion

    International Nuclear Information System (INIS)

    Lai Shifu

    2013-01-01

    Project quality construction acceptance is an important element of nuclear power project quality management. Based on characteristics of NPP construction and refer to national construction quality acceptance code and industry regulation, this paper introduces and discusses NPP construction quality acceptance regulation improvement and implementation under current situation. (authors)