Development of Level-1 PSA method for sodium-cooled fast reactors, 6; Failure probability evaluation method of natural circulation heat removal function

Yamano, Hidemasa ; Sakai, Takaaki; Kurisaka, Kenichi

The characteristics of fast reactor safety is that it has passive safety function such as natural circulation heat removal. Hence, it is necessary to evaluate the reliability of the passive safety function and to estimate probability of the functional failure in order to perform level 1 PSA on a plant. This paper reports sensitivity analysis and failure probability evaluation in 2011 to construct failure probability evaluation methodology on natural circulation decay heat removal.

Language	:	Japanese
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Meeting title	:	日本原子力学会2012年秋の大会
Held date	:	2012/09
Location (city)	:	東広島
Location (country)	:	日本
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Keywords	:	no keyword
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Cooperating Institute	:	文部科学省

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Registration No. : BB20120380
JAEA Abstracts No. :
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