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Author Tzanos, C. P. ♦ Saltos, N. T.
Source United States Department of Energy Office of Scientific and Technical Information
Content type Text
Language English
Subject Keyword NUCLEAR REACTOR TECHNOLOGY ♦ NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS ♦ WATER COOLED REACTORS ♦ REACTOR SAFETY ♦ FAILURES ♦ PERFORMANCE ♦ PROBABILITY ♦ HYDRAULICS ♦ REACTOR CORES ♦ ENGINEERED SAFETY SYSTEMS
Abstract Advanced light water reactor (LWR) like AP600 and the simplified boiling water reactor use passive safety systems for accident prevention and mitigation. Because these systems rely on natural forces for their operation, their unavailability due to hardware failures and human error is significantly smaller than that of active systems. However, the coolant flows predicted to be delivered by these systems can be subject to significant uncertainties, which in turn can lead to a significant uncertainty in the predicted thermal-hydraulic performance of the plant under accident conditions. Because of these uncertainties, there is a probability that an accident sequence for which a best-estimate thermal-hydraulic analysis predicts no core damage (success sequence) may actually lead to core damage. For brevity, this probability will be called thermal-hydraulic unreliability. The assessment of this unreliability for all the success sequences requires very expensive computations. Moreover, the computational cost increases drastically as the required thermal-hydraulic reliability increases. The required computational effort can be greatly reduced if a bounding approach can be used that either eliminates the need to compute thermal-hydraulic unreliabilities, or it leads to the analysis of a few bounding sequences for which the required thermal-hydraulic reliability is relatively small. The objective of this paper is to present such an approach and determine the order of magnitude of the thermal-hydraulic unreliabilities that may have to be computed.
ISSN 0003018X
Educational Use Research
Learning Resource Type Article
Publisher Date 1995-12-31
Publisher Place United States
Journal Transactions of the American Nuclear Society
Volume Number 73
Technical Publication No. CONF-951006-


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