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Malyshev, A.B.; Morozov, V.B.
International conference on the strengthening of nuclear safety in Eastern Europe. Keynote papers. Regulatory aspects of NPP safety, status of safety improvements, status of safety analysis report
International conference on the strengthening of nuclear safety in Eastern Europe. Keynote papers. Regulatory aspects of NPP safety, status of safety improvements, status of safety analysis report
AbstractAbstract
[en] Report presents the current state-of art in developing safety reports and probabilistic safety analyses for WWER NPPs operated in Russia. Development of these reports and implementation of PSA is done according to the requirements outlined in the basic document 'General Statement on Ensuring safety (OPB). At present submitting safety reports to the regulatory authority GAN RF is mandatory for licensing NPPs. Current state of safety reports for the operating WWER type NPPs meets generally the effective Russian standard engineering documents which are approaching the international standards. A mechanism ensuring correspondence of the safety documentation to the current state of operating units is determined. Modernization of the operating units is underway, it is aimed to eliminate existing deviations from requirements of the modern standards in the field of NPP safety
Original Title
Razrabotka otchetov po analizu bezopasnosti i VAB dlya ehkspluatiruyushchikhsya ehnergoblokov AEhS s WWEhR v Rossii
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International Atomic Energy Agency, Vienna (Austria); 1083 p; Jun 1999; p. 665-737; International conference on the strengthening of nuclear safety in Eastern Europe; Vienna (Austria); 14-18 Jun 1999; AVAILABLE FROM INIS IN ELECTRONIC FORM; Tabs.; This record replaces 30031424
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Report
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Conference
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AbstractAbstract
[en] Short communication
Original Title
Aktuelle Probleme bei Gefaehrdungsanalysen
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Bauer, K.G. (comp.); Deutsches Atomforum e.V., Bonn (Germany); Kerntechnische Gesellschaft e.V., Bonn (Germany); 734 p; ISSN 0720-9207;
; May 1996; p. 194-197; Inforum Verl; Bonn (Germany); Annual meeting on nuclear technology '96; Jahrestagung Kerntechnik (JK '96); Mannheim (Germany); 21-23 May 1996

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AbstractAbstract
[en] This article contains four lists of various documents relevant to nuclear safety as compiled by the editor. These lists are: (1) reactor operations-related reports of U.S. origin, (2) other books and reports, (3) regulatory guides, and (4) nuclear standards. Each list contains the documents in its category which were published (or became available) during the October 1995 through March 1996 reporting period. The availability and cost of the documents are noted in most instances
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Journal Article
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Bibliography
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McDonald, N.R.; Bastin, S.J.; Cameron, R.F.; Adams, A.
International symposium on research reactor utilization, safety and management. Book of extended synopses
International symposium on research reactor utilization, safety and management. Book of extended synopses
AbstractAbstract
No abstract available
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); Instituto Tecnologico e Nuclear, Sacavem (Portugal); 205 p; 1999; p. 51-52; International symposium on research reactor utilization, safety and management; Lisbon (Portugal); 6-10 Sep 1999; IAEA-SM--360/26
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[en] The cumulated experience on operating nuclear power plants and the progress of safety knowledge allow to conceive reactors with high standard of safety and with optimized building and operating costs. In this article we present the proceedings followed by electricity producers, the main western nuclear plant builders and safety authorities to warrant the required level of safety. The main safety characteristics of new PWR projects are reviewed. A comparison is made between EPR, SYSTEM 80+, APWR and AP600 projects. Safety is also based on the quality of building and the excellence of operating staff. (A.C.)
Original Title
Reacteurs du futur. Evolution de l'approche de surete
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Source
Fanet, H. (CEA, 75 - Paris (France)); Lefevre, J. (CEA, 75 - Paris (France). Cycle du Combustible); Livolant, M. (CEA Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire); Techniques de l'Ingenieur; v. B8II; [616 p.]; Oct 1998; p. BN3830.1-BN3830.8; Techniques de l'Ingenieur; Paris (France); 16 refs.
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Book
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Honda, T.; Okazaki, T.; Bartels, H.W.; Sugihara, M.; Uckan, N.A.; Seki, Y.
17. IAEA fusion energy conference. Extended synopses
17. IAEA fusion energy conference. Extended synopses
AbstractAbstract
No abstract available
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); 379 p; 1998; p. 189; 17. IAEA fusion energy conference; Vienna (Austria); 19-24 Oct 1998; ITERP--1/19; 3 refs
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AbstractAbstract
[en] The present note describes the basic principles for nuclear reactor safety which are followed, as a general feature, for all nuclear power plants. The text contains a description of safety features, including the concepts of redundancy, diversity and physical separation. Attention to multiple barriers and to the three levels of safety measures is given. The importance of the presence of the operator and the general approach known as probability safety analysis are outlined. After this general picture of the nuclear safety basic principles, most recent trends of safety design are examined, showing the evolution since the first generation of nuclear reactors. New design criteria are introduced and finally a proposal is advanced of a small, modular, multi-purpose reactor inherently safe, called MARS, and developed jointly at the University of Rome La Sapienza and the Italian National Agency ENEA. (author)
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Gandini, A. (ENEA, Rome (Italy)); Reffo, G. (ENEA, Bologna (Italy)) (eds.); International Centre for Theoretical Physics, Trieste (Italy); 1252 p; ISBN 981-02-2901-1;
; 1998; p. 898-920; Workshop on nuclear reaction data and nuclear reactors. Physics, design and safety; Trieste (Italy); 15 Apr - 17 May 1996; 11 figs

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[en] Westinghouse is developing advanced safety analysis technologies for both LOCA and Non-LOCA events. The Best-Estimate LOCA (BELOCA) technologies for cold leg injection and direct vessel injection have been licensed to support plant modifications which require significant PCT margin. The development of a BELOCA methodology for Upper Plenum Injection (UPI) plants has been completed and submitted to the US NRC. A Best-Estimate Small Break technology is also being developed. For Reactivity Insertion Accidents (RIA) and DNB limited events, Westinghouse is developing a three dimensional core kinetics methodology based on the extremely flexible EPRI codes, RETRAN and VIPRE. Studies have been completed to demonstrate the applicability of Westinghouse's existing methodologies to the developed RETRAN model. These advanced technologies will significantly enhance the reliability of the safety margin evaluations which are required to improve the plant operation economics.(author)
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Ravnik, M.; Jencic, I.; Zagar, T. (Nuclear Society of Slovenia, Ljubljana (Slovenia)) (eds.); Nuclear Society of Slovenia, Ljubljana (Slovenia). Funding organisation: European Nuclear Society (Switzerland); Nuclear Power Plant Krsko (Slovenia); Siemens Power Generation Group, Erlangen (Germany); Ministry of Science and Technology of Slovenia, Ljubljana (Slovenia); Institute Jozef Stefan (Slovenia); American Society of Mechanical Engineers (United States); ENCONET Consulting GmbH (Austria); SIAP d.o.o. Pesnica pri Mariboru (Slovenia); Institute for Metal Constructions (Slovenia); Agency for Radwaste management (Slovenia); Slovenian Nuclear Safety Administration (Slovenia); 519 p; ISBN 961-6027-10-5;
; 1998; p. 439-444; Nuclear Society of Slovenia; Ljubljana (Slovenia); Nuclear Energy in Central Europe 98; Terme Catez (Slovenia); 7-10 Sep 1998; Available from Nuclear Society of Slovenia, Jozef Stefan Institute, Jamova 39, Ljubljana (SI); 5 refs.

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Miscellaneous
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Laaksonen, J.
Energy Agency, Vilnius (Lithuania)
Energy Agency, Vilnius (Lithuania)
AbstractAbstract
[en] A leading internationally agreed principle is that the prime responsibility for nuclear safety rests with each user of nuclear energy. A proper regulatory regime is needed to ensure that this responsibility is met. In the first place it provides a verification that all relevant safety issues are understood and taken into account in the practical measures by the users but it is equally important that the regulatory regime supports the users in their strive to achieve an adequate level of safety (author)
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Journal Article
Journal
Energy News - Energy Agency of Lithuania; ISSN 1392-1479;
; (no.1); p. 13-14

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AbstractAbstract
No abstract available
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Yildirim, N. (Turkish Electricity Generation-Transmission Corporation, TEAS (Turkey)); 127 p; 1997; [14 p.]; Nuclear energy public information seminar; Ankara, Mersin (Turkey); 26-27 May 1997
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Miscellaneous
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