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ArticleJ-GLOBAL ID:200902001912575401整理番号: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

著者:MEYDER R(Kernforschungszentrum Karlsruhe GmbH, Karlsruhe, DEU)
資料名:Nucl Eng Des 巻:100 号:3 ページ:307-314
発行年:1987年03月
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About J-GLOBAL

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The system enables searches of similar kinds of content through linkage with external sites.
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