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Taniguchi, T.
Effective nuclear regulatory systems: Facing safety and security challenges. Proceedings of an international conference
Effective nuclear regulatory systems: Facing safety and security challenges. Proceedings of an international conference
AbstractAbstract
[en] The paper describes the IAEA programmes and capabilities contributing to the peaceful uses of nuclear technology on a global scale. The IAEA has developed and continues to support a global nuclear safety regime that is comprised of several facets. The principal elements are binding and non-binding international legal instruments such as the various conventions and codes of conduct; a comprehensive suite of nuclear safety standards; a suite of international safety reviews and services, based on the safety standards; and the need to ensure strong national infrastructures and a global community of experts. These elements are described in some detail and the future challenges are outlined. (author)
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International Atomic Energy Agency, Department of Nuclear Safety and Security, Vienna (Austria); 344 p; ISBN 92-0-110606-8;
; Sep 2006; p. 97-103; International conference on effective nuclear regulatory systems: Facing safety and security challenges; Moscow (Russian Federation); 27 Feb - 3 Mar 2006; ISSN 0074-1884;
; Also available on-line: http://www-pub.iaea.org/MTCD/publications/PDF/Pub1272_web.pdf; For availability on CD-ROM, please contact IAEA, Sales and Promotion Unit: E-mail: sales.publications@iaea.org; Web site: http://www-pub.iaea.org/MTCD/publications/publications.asp; PowerPoint presentation included


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[en] The main objective of this paper is to provide on overview of the key safety issues and challenges addressed to the advanced light water reactor designs. (author)
Original Title
Aspkty bezpieczenstwa w nowoczesnej energetyce jadrowej
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Institute of Atomic Energy, Otwock-Swierk (Poland); 193 p; ISSN 1232-5317;
; 2007; p. 45-51; Materials Investigation for Power Industry. 14 Seminar; Zakopane (Poland); 20-22 Jun 2007; Available at Institute of Atomic Energy; 11 refs.

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AbstractAbstract
[en] The book is written with the awareness of safe work culture where success does not lie to compliance with the law only. Instead it is more of an excellent management based on the principle of self organization. Self arrangements in the management of occupational safety and health do not rest on the shoulders of the employer or the safety management and safety communities, but are committed together with the leadership of the employer. Self arrangements will be more meaningful and successful if those involved have knowledge about the philosophy and principles of why and how this management is done, and so the method can be practiced and eventually cultivated as a working system. (author)
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Pengaturan sendiri di dalam pengurusan keselamatan dan kesihatan pekerjaan
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2002; 424 p; McGraw-Hill; Kuala Lumpur (Malaysia); ISBN 983-9340-90-5;
; Available in Malaysian Nuclear Agency library; 13 refs. 17 chapters

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AbstractAbstract
[en] Due to the recent Fukushima accident, the potential risks at one and only nuclear research reactor in the country, which is the PUSPATI TRIGA Reactor (RTP), has increasingly gain concerns and an attempt on the development of Level 1 Probabilistic Safety Assessment (PSA) for this reactor has been commenced. The preliminary scope of the PSA is to analyse the risk of core degradation during normal daily operation due to the random component failure and human error. SPAR-H and THERP method is used for quantifying human error probability (HEP). However, the scopes of this study only cover the qualitative parts that use interview/questionnaire method. The objectives of the questionnaire are to identify the main action for RTP operators when any undesired incident occurs during full power operation that might be caused by random component failures. From the questionnaires that have been conducted, the respondents consisted of 4 licensed operators and 9 trainee operators. All licensed operators have experience of operating reactor for more than 15 years while the trainee operator have been operate the reactor with experience of less than 10 years. Generally, in the event of an abnormal condition involving the reactor, an operator whether a licensed operator or the trainee does not have to ask permission in advance from the top individuals to carry out scram. This is to prevent the situation becoming increasingly severe if the reactor is still operating. With complete training and knowledge derived from the management, an operator can act efficiently in any emergency case. (author)
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2016; 6 p; R&D Seminar 2016: Research and Development Seminar 2016; Bangi (Malaysia); 8-10 Nov 2016; Also available in Malaysian Nuclear Agency Document Delivery Center by email: mohdhafizal@nuclearmalaysia.gov.my; Oral presentation
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ASIA, ATTITUDES, DEVELOPING COUNTRIES, ENGINEERING, ENRICHED URANIUM REACTORS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, MALAYSIAN ORGANIZATIONS, NATIONAL ORGANIZATIONS, REACTORS, RESEARCH AND TEST REACTORS, SOLID HOMOGENEOUS REACTORS, TRIGA TYPE REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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Johnston, Alan
Technical Meeting on Development of a TECDOC on Development and Application of a Safety Goals Framework for Nuclear Installations. Presentations
Technical Meeting on Development of a TECDOC on Development and Application of a Safety Goals Framework for Nuclear Installations. Presentations
AbstractAbstract
[en] Benefits: Overall site-wide safety goals, appropriately decomposed and apportioned, will provide an effective basis for grading the safety analysis effort, as permitted and encouraged by the CRL site licence.
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International Atomic Energy Agency, Department of Nuclear Safety and Security, Division of Nuclear Installation Safety, Safety Assessment Section, Vienna (Austria); vp; 2013; 17 p; Technical Meeting on Development of a TECDOC on Development and Application of a Safety Goals Framework for Nuclear Installations; Vienna (Austria); 8-12 Jul 2013; Also available on-line: https://nucleus.iaea.org/sites/gsan/act/tmsafetygoals2013/Shared%20Documents/P09_Canada_Safety_Goals_for_Muli_Facility_site.pdf
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AbstractAbstract
[en] The reliability of ventilation systems in nuclear installations is based on principles and conditions which are but one particular application among those that have been decided for the safety of installations. It rests on the presence of a person in charge of the installation who must have at his disposal a well designed plant and must operate it in accordance with clear and precise rules. The obligation that he is now under to present a detailed safety report, drawn up specially to highlight the guarantees assured with respect to the personnel and the environment, enables it to be analyzed by independent authorities
[fr]
La surete des systemes de ventilation des installations nucleaires repose sur des principes et des modalites qui ne sont qu'une application particuliere de ceux qui sont retenus pour la surete des installations; elle repose sur la presence d'un responsable de l'installation qui doit avoir a sa disposition un ensemble bien concu et l'exploiter selon des regles bien precises. L'obligation qui lui est faite maintenant de presenter un rapport de surete detaille, redige specialement dans l'optique de faire ressortir les garanties assurees vis-a-vis du personnel et de l'environnement, permet d'en faire effectuer l'analyse par des autorites independantesOriginal Title
Surete des systemes de ventilation
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Societe Francaise de Radioprotection, 92 - Fontenay-aux-Roses; 322 p; 1982; 21 p; Societe Francaise de Radioprotection; Fontenay-aux-Roses (France); Meeting on the ventilation of nuclear facilities; Pierrelatte (France); 22 - 26 Mar 1982
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Nachmilner, L.; Dlouhy, Z.; Konopaskova, S.; Kourim, V.
Minimization of formation, processing and disposal of radioactive wastes
Minimization of formation, processing and disposal of radioactive wastes
AbstractAbstract
[en] Requirements put on the preliminary and pre-operation safety reports on radioactive waste depositories, as following from Czechoslovak regulations No. 85/1976 and 67/1987, are commented on. Basic approaches to the compilation of the required documentation are described, and practical experience gained during its writing is discussed. (author). 18 refs
Original Title
Bezpecnostne technicka dokumentace ulozist radioaktivnich odpadu
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Neumann, L. (ed.); Ceska Vedeckotechnicka Spolecnost, Prague (Czechoslovakia). Komise pro Jadernou Techniku; Ceskoslovenska Komise pro Atomovou Energii, Prague (Czechoslovakia); Ustav Jaderneho Vyzkumu CSKAE, Rez (Czechoslovakia); 282 p; 1989; p. 192-196; Conference on minimization of formation, processing and disposal of radioactive wastes; Minimalizace tvorby, zpracovani a trvale ulozeni radioaktivnich odpadu; Marianske Lazne (Czechoslovakia); 3-7 Dec 1989
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AbstractAbstract
[en] Having defined safety and analysis of safety, the nature and significance of nuclear hazards are indicated, highlighting the importance of ventilation for safety. The authorization procedure for the creation and commissioning of an installation is also indicated. The list of safety organizations in France is given. Mention is then made of the general technical regulations, their aim and working out. To conclude, normalization and its application to the ventilation of nuclear installations is examined
[fr]
Apres avoir defini la surete et l'analyse de surete, on indique la nature et l'importance des risques nucleaires, en mettant l'accent sur l'importance de la ventilation pour la surete. On indique egalement la procedure d'autorisation pour la creation et la mise en service d'une installation. On donne la liste des organismes de surete en France. On aborde ensuite la reglementation technique generale, son objectif et son elaboration. enfin, on examine la normalisation et son application au cas de la ventilation des installations nucleairesOriginal Title
Ventilation des installations nucleaires. Organisation de la surete nucleaire en France
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Societe Francaise de Radioprotection, 92 - Fontenay-aux-Roses; 322 p; 1982; 32 p; Societe Francaise de Radioprotection; Fontenay-aux-Roses (France); Meeting on the ventilation of nuclear facilities; Pierrelatte (France); 22 - 26 Mar 1982
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AbstractAbstract
[en] Safety in the operation of electrostatic accelerators is discussed in terms of analyzing the hazards and devising accident prevention techniques. Some practical guidelines are suggested. The usefulness of making a detailed safety analysis is stressed
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Bair, J.K.; Jones, C.M. (comps.); Oak Ridge National Lab., TN (USA); p. 105-113; Jun 1979; p. 105-113; Symposium of northeastern accelerator personnel; Oak Ridge, TN, USA; 23 - 25 Oct 1978
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Aldenkamp, F.; Biesiot, W.; Geerts, H.M.; Nienhuys, K.; Soppe, W.
Rijksuniversiteit Groningen (Netherlands). Interfacultaire Vakgroep Energie en Milieukunde
Rijksuniversiteit Groningen (Netherlands). Interfacultaire Vakgroep Energie en Milieukunde
AbstractAbstract
[en] A survey is presented of the discussion on location sites for nuclear power plants in the Netherlands and the USA. It consists of two parts (A and B). This part (A) presents a summary of the discussion in the Netherlands. The name and contents of the reports which have been published are indicated briefly. Many of the Dutch reports refer to American studies on reactor safety. In order to obtain a good survey of these a description is presented of the development of the discussion in the USA after the publication of the well-known reactor safety study WASH-1400. After this survey of five important reports, an introduction is presented dealing with the background of the authors, the purposes, the main conclusions and the most salient points of criticism formulated by others. Under discussion are the reports of the IDCOR (nuclear power industry), ANS (American Nuclear Society), APS (American Physical Society), NRC (Nuclear Regulatory Commission) and UCS (Union of Concerned Scientists). 38 refs.; 5 figs.; 5 tabs
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Het debat over reactorveiligheid
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Jun 1986; 46 p
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