Art
J-GLOBAL ID:200902001912575401   Reference number:87A0261283

Modelling of transient fuel rod behaviour and core damage during loss of coolant accidents in a light water reactor.

軽水型原子炉(LWR)の冷却材喪失事故(LOCA)中の過渡燃料棒挙動と炉心損傷のモデル化
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Material:
Volume: 100  Issue:Page: 307-314  Publication year: Mar. 1987 
JST Material Number: E0189B  ISSN: 0029-5493  Document type: Article
Article type: 原著論文  Country of issue: Netherlands (NLD)  Language: ENGLISH (EN)
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Semi thesaurus term:
Thesaurus term/Semi thesaurus term
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Safety of watercooled reactors  ,  Fuel elements 

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