Development of level 1 PRA methodology for external vessel storage tank of Japan Sodium-cooled Fast Reactor (JSFR) in scheduled refueling

Naruto, Kenichi*; Sugino, Tetsu*; Yamano, Hidemasa ; Kurisaka, Kenichi ; Nishino, Hiroyuki ; Okano, Yasushi

For SFR, new fuel assembly and used that are stored in EVST having sodium pool. This study identified accident sequence induced core damage by function loss of decay heat removal at scheduled refueling in the EVST and developed methodology for calculation of fuel damage frequency.

Language	:	Japanese
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Meeting title	:	日本原子力学会2014年秋の大会
Held date	:	2014/09
Location (city)	:	京都
Location (country)	:	日本
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Keywords	:	no keyword
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Registration No. : BB20140649
JAEA Abstracts No. :
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