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AbstractAbstract
[en] This final report on the NKS/RAK-1.2 summarizes the main features of the PIFRAP PC-program and its intended implementation. Regardless of the preferred technical approach to LOCA frequency estimation, the analysis approach must include recognition of the following technical issues: a) Degradation and failure mechanisms potentially affecting piping systems within the reactor coolant pressure boundary (RCPB) and the potential consequences; b) In-service inspection practices and how they influence piping reliability; and c) The service experience with piping systems. The report consists of six sections and one appendix. A Nordic perspective on LOCA and nuclear safety is given. It includes summaries of results from research in material sciences and current regulatory philosophies regarding piping reliability. A summary of the LOCA concept is applied in Nordic PSA studies. It includes a discussion on deterministic and probabilistic views on LOCA. The R and D on piping reliability by SKI and the PIFRAP model is summarized. Next, Section 6 presents conclusion and recommendations. Finally, Appendix A contains a list of abbreviations and acronyms, together with a glossary of technical terms. (EG)
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Source
Dec 1997; 47 p; RSA-R--97-23; ISBN 87-7893-046-4;
; CONTRACT NKS/RAK-1; 16 refs.

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Report
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ACCIDENTS, CONTROL, DEVELOPED COUNTRIES, ENRICHED URANIUM REACTORS, EUROPE, JOINTS, POWER REACTORS, PWR TYPE REACTORS, REACTOR ACCIDENTS, REACTORS, SCANDINAVIA, SIMULATION, SYSTEM FAILURE ANALYSIS, SYSTEMS ANALYSIS, TESTING, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS, WESTERN EUROPE
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