중대사고에서의 열적 연화를 고려한 원자로 하부구조의 유한요소 극한해석Finite Element Limit Analysis of a Nuclear Reactor Lower Head Considering Thermal Softening in Severe Accident

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dc.contributor.author김, 기풍-
dc.contributor.author허, 훈-
dc.contributor.author박, 재홍-
dc.contributor.author이, 종인-
dc.contributor.authorKim, K.P.-
dc.contributor.authorHuh, H.-
dc.contributor.authorPark, J.H.-
dc.contributor.authorLee, J.I.-
dc.date.accessioned2009-08-26T02:17:12Z-
dc.date.available2009-08-26T02:17:12Z-
dc.date.issued2001-
dc.identifier.citation대한기계학회 춘추학술대회, Vol.1, No.1, pp.782~787en
dc.identifier.urihttp://www.ksme.or.kr/-
dc.identifier.urihttp://hdl.handle.net/10203/10785-
dc.description.abstractThis paper is concerned with the global rupture of a nuclear reactor pressure vessel(RPV) in a severe accident. During the severe reactor accident of molten core, the temperature and the pressure in the nuclear reactor rise to a certain level depending on the initial and subsequent condition of a severe accident. While the rise of the temperature cause the thermal softening of RPV material, the rise of the internal pressure could cause failure of the RPV lower head. The global rupture of an RPV is simulated by finite element limit analysis for the collapse pressure and mode and this analysis results have been compared with a variation of the internal pressure of RPV. The finite element limit method is a systematic tool to secure the safety criteria of a nuclear reactor and to evaluate the in-vessel corium retention.en
dc.language.isokoen
dc.publisher대한기계학회en
dc.subjectNuclear Reactor Lower Headen
dc.subjectFinite Limit Analysisen
dc.subjectThermal Analysisen
dc.subjectThermal Softeningen
dc.subjectSevere Accidenten
dc.title중대사고에서의 열적 연화를 고려한 원자로 하부구조의 유한요소 극한해석en
dc.title.alternativeFinite Element Limit Analysis of a Nuclear Reactor Lower Head Considering Thermal Softening in Severe Accidenten
dc.typeArticleen
dc.language.Alternativeen_USen

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