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Jo, Y.G.; Sung, T.Y.; Park, C.K.
ANP'92 international conference on design and safety of advanced nuclear power plants1992
ANP'92 international conference on design and safety of advanced nuclear power plants1992
AbstractAbstract
[en] A Probabilistic Safety Assessment (PSA) was performed for the conceptual design of the Korean Nuclear District Heating Reactor (KNDHR). Only internal events were considered. Five core damage accident sequences, two for Pool Leakage (PL), one for Loss of Power (LOP), one for Loss of Secondary Flow (LOSF), and one for Sudden Control Rod Withdrawal (SCRW), were identified. Total core damage frequency was estimated to be 6.8 x 10-9/yr. The contributions of the initiating events to the total core damage frequency were, 50.2 % (PL), 38.4 % (LOP), 10.6 % (LOSF), and 0.8 % (SCRW), respectively. Based on the results, it was concluded that the KNDHR is much safer than the existing nuclear power plants considering the core damage frequency goal of the advanced light water reactor, which is 1 x 10-5/yr and that reactor trip and pool inventory make up are the most important safety functions. (author)
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Source
Oka, Y.; Koshizuka, S. (Tokyo Univ. (Japan)) (comps.); Atomic Energy Society of Japan, Tokyo (Japan); [2182 p.]; 1992; v. 4 p. 38.5/1-38.5/7; Atomic Energy Society of Japan; Tokyo (Japan); ANP'92: international conference on design and safety of advanced nuclear power plants; Tokyo (Japan); 25-29 Oct 1992
Record Type
Book
Literature Type
Conference
Country of publication
ACCIDENTS, ASIA, DEVELOPING COUNTRIES, ENRICHED URANIUM REACTORS, HEATING, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, NUCLEAR FACILITIES, POOL TYPE REACTORS, POWER PLANTS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, THERMAL POWER PLANTS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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