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[en] The projected increase in electricity demand, increased concern over emissions along with more stringent emission requirements, volatility of the gas and oil supplies and prices, and the convergence of favourable conditions and legislation make nuclear power a practical option for meeting future electricity base-load demands. (author)
Source
Jencic, I.; Lenosek, M. (Nuclear Society of Slovenia, Ljubljana (Slovenia)) (eds.); Nuclear Society of Slovenia, Ljubljana (Slovenia). Funding organisation: Agency for Radwaste Management, Ljubljana (Slovenia); AREVA, Framatome ANP, Paris (France); Atel AG, Olten (Switzerland); Atel Energija, Ljubljana (Slovenia); GEN energija, Krsko (Slovenia); Inst. of Metal Constructions, Ljubljana (Slovenia); INETEC-Inst. for Nuclear Technology, Zagreb (Croatia); Inst. Jozef Stefan, Ljubljana (Slovenia); Financial Fund for Decommissioning of Nuclear Power Plant Krsko, Krsko (Slovenia); Westinghouse Electric Europe, Brussels (Belgium); ANSYS, Canonsburg, PA (United States); Slovenian Research Agency, Ljubljana (Slovenia); Elmont, Krsko (Slovenia); IBE, Consulting Engineers Ljubljana (Slovenia); Inst. of Metals and Technology, Ljubljana (Slovenia); Pool for Insurance and Reinsurance of Nuclear Risk, Ljubljana (Slovenia); NUMIP Engineering, Construction, Maintenance and Production, Ljubljana (Slovenia); Slovenian Nuclear Safety Administration, Ljubljana (Slovenia); [831 p.]; ISBN 978-961-6207-28-7; 
; 2007; [8 p.]; International Conference Nuclear Energy for New Europe 2007; Portoroz (Slovenia); 10-13 Sep 2007; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (SI); 10 refs.
; 2007; [8 p.]; International Conference Nuclear Energy for New Europe 2007; Portoroz (Slovenia); 10-13 Sep 2007; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (SI); 10 refs.
[en] Operating experience is not new, in the most of the activities that we perform in our daily lives, we can find examples of how, using the knowledge that we acquired to develop a work and to solve problems, we can get an improvement or sounded benefit. (Author)
Journal
Nuclear Espana (1996); ISSN 1137-2885; ; v. 283; p. 25-28
; v. 283; p. 25-28
[en] The trip delay time that is determined by using RFSP-IST is applied to the Loss of Regulation (LOR) simulations of Wolsong-1, which is scheduled to undergo a major refurbishment project. The safety analyses required for licensing after refurbishment are currently being carried out using the update-to-date Canadian Industry Standard Toolset code suite. Since the POINTSIM program used in the past to calculate trip delay time is not included in IST, the RFSP-IST code is being mandatorily used in place of the POINTSIM functions. The CATHENA LOR simulation results obtained based upon the RFSP-IST determined trip delay times clearly justify the use of procedures that are developed to run *CERBERUS, *INTREP and *TRIP-TIME modules in the context of determining trip delay time. (author)
Source
Canadian Nuclear Society, Toronto, Ontario (Canada); 275 Megabytes; ISBN 0-919784-95-X; ; 2009; [9 p.]; 30. annual canadian nuclear society conference; Calgary, Alberta (Canada); 31 May - 3 Jun 2009; 33. CNS/CNA student conference; Calgary, Alberta (Canada); 31 May - 3 Jun 2009; Available from the Canadian Nuclear Society, Toronto, Ontario (Canada); 14 refs., 3 tabs., 3 figs.
; 2009; [9 p.]; 30. annual canadian nuclear society conference; Calgary, Alberta (Canada); 31 May - 3 Jun 2009; 33. CNS/CNA student conference; Calgary, Alberta (Canada); 31 May - 3 Jun 2009; Available from the Canadian Nuclear Society, Toronto, Ontario (Canada); 14 refs., 3 tabs., 3 figs.
[en] CNSC staff introduced a new Power Reactor Operating Licence (PROL) in order to strengthen the regulatory oversight of power reactor operation, while increasing regulatory effectiveness and efficiency by focusing on risk-significant issues and reducing purely administrative efforts. The PROLs have been simplified by incorporating a more risk-informed approach and by eliminating cascading references to working level licensee documentation and regulatory expectations. To ensure that there is a common understanding for each requirement specified in the PROL, CNSC staff prepared a Licence Conditions Handbook (LCH), which provides technical details and compliance verification criteria on how licence conditions are to be met. (author)
Source
Canadian Nuclear Society, Toronto, Ontario (Canada); 111 Megabytes; ISBN 978-1-926773-01-8; ; 2010; [5 p.]; 31. Annual Conference of the CNS; Montreal, Quebec (Canada); 24-27 May 2010; 34. Annual Student Conference of the CNS and CNA; Montreal, Quebec (Canada); 24-27 May 2010; Available from the Canadian Nuclear Society, Toronto, Ontario (Canada); 1 fig.
; 2010; [5 p.]; 31. Annual Conference of the CNS; Montreal, Quebec (Canada); 24-27 May 2010; 34. Annual Student Conference of the CNS and CNA; Montreal, Quebec (Canada); 24-27 May 2010; Available from the Canadian Nuclear Society, Toronto, Ontario (Canada); 1 fig.
[en] Advanced reactors are expected to be based on a concept of operations that is different from what is currently used in today's reactors. Therefore, regulatory staff may need new tools, developed from the best available technical bases, to support licensing evaluations. The areas in which new review guidance may be needed and the efforts underway to address the needs will be discussed. Our preliminary results focus on some of the technical issues to be addressed in three areas for which new guidance may be developed: automation and control, operations under degraded conditions, and new human factors engineering methods and tools. (authors)
Source
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States); 1430 p; ISBN 0-89448-051-0; ; 2006; p. 938-943; NPIC and HMIT 2006: 5. International Topical Meeting on Nuclear Plant Instrumentation Controls, and Human Machine Interface Technology; Albuquerque, NM (United States); 12-16 Nov 2006; Country of input: France; 4 refs.
; 2006; p. 938-943; NPIC and HMIT 2006: 5. International Topical Meeting on Nuclear Plant Instrumentation Controls, and Human Machine Interface Technology; Albuquerque, NM (United States); 12-16 Nov 2006; Country of input: France; 4 refs.
[en] The first experience on how a part of the ARAMIS methodology has contributed to demonstration of safety in the licensing process in Slovenia for a new Seveso II plant is described. There are two foci of this description: first, trustworthy of the methodology for evaluating safety, and second, the role of a land-use plan in issuing a construction permit for the new plant. In the context of the first focus, we present why has been safety report first rejected by the regulator, and later-on accepted after applying components of the ARAMIS methodology in its revised version. In the context of the second focus, we discuss a relationship between the land-use plan and the licensing process for the new plant. The outcomes of this Seveso II plant licensing case are that the ARAMIS approach, in spite it was still under development when applied, is more transparent and credible comparing to the others, which have also been applied. This is related to the demonstration of how safety management system and general safety behaviour is integrated into the overall management policy. The conclusions take into account regulator's response in the licensing process
Journal
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