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DOI10.2172/6398077
报告编号SAND-89-1147
来源IDOSTI_ID: 6398077
Analysis of core damage frequency due to external events at the DOE (Department of Energy) N-Reactor
Lambright, J.A.; Bohn, M.P.; Daniel, S.L. (Sandia National Labs., Albuquerque, NM (USA)); Baxter, J.T. (Westinghouse Hanford Co., Richland, WA (USA)); Johnson, J.J.; Ravindra, M.K.; Hashimoto, P.O.; Mraz, M.J.; Tong, W.H.; Conoscente, J.P. (EQE, Inc., San Francisco, CA (USA)); Brosseau, D.A. (ERCE, Inc., Albuquerque, NM (USA))
英文摘要A complete external events probabilistic risk assessment has been performed for the N-Reactor power plant, making full use of all insights gained during the past ten years' developments in risk assessment methodologies. A detailed screening analysis was performed which showed that all external events had negligible contribution to core damage frequency except fires, seismic events, and external flooding. A limited scope analysis of the external flooding risk indicated that it is not a major risk contributor. Detailed analyses of the fire and seismic risks resulted in total (mean) core damage frequencies of 1.96E-5 and 4.60E-05 per reactor year, respectively. Detailed uncertainty analyses were performed for both fire and seismic risks. These results show that the core damage frequency profile for these events is comparable to that found for existing commercial power plants if proposed fixes are completed as part of the restart program. 108 refs., 85 figs., 80 tabs.
出版年1990
报告类型Technical Report
语种英语
国家美国
来源学科分类22 GENERAL STUDIES OF NUCLEAR REACTORS ; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS ; N-REACTOR ; REACTOR CORE DISRUPTION ; REACTOR CORES ; FAILURE MODE ANALYSIS ; FIRES ; FLOODS ; FREQUENCY ANALYSIS ; LOSS OF COOLANT ; REACTOR SAFETY ; RISK ASSESSMENT ; SEISMIC EFFECTS ; TORNADOES ; ACCIDENTS ; DISASTERS ; ENRICHED URANIUM REACTORS ; GRAPHITE MODERATED REACTORS ; LWGR TYPE REACTORS ; PLUTONIUM PRODUCTION REACTORS ; POWER REACTORS ; PRODUCTION REACTORS ; REACTOR ACCIDENTS ; REACTOR COMPONENTS ; REACTORS ; SAFETY ; STORMS ; SYSTEM FAILURE ANALYSIS ; SYSTEMS ANALYSIS ; WATER COOLED REACTORS ; WIND 220900* -- Nuclear Reactor Technology-- Reactor Safety ; 220600 -- Nuclear Reactor Technology-- Research, Test & Experimental Reactors
URLhttp://www.osti.gov/scitech/servlets/purl/6398077
资源类型科技报告
条目标识符http://119.78.100.177/qdio/handle/2XILL650/264356
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GB/T 7714
Lambright, J.A.,Bohn, M.P.,Daniel, S.L. ,et al. Analysis of core damage frequency due to external events at the DOE (Department of Energy) N-Reactor,1990.
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