Probabilistic risk assessment method development for high temperature gas-cooled reactors

Sato, Hiroyuki ; Nishida, Akemi ; Furuya, Osamu*; Muramatsu, Ken*; Itoi, Tatsuya*; Takada, Tsuyoshi* ; Tanabe, Masayuki*; Yamamoto, Tsuyoshi*

The proposed research aims to establish a probabilistic risk assessment method for high temperature gas-cooled reactors fully utilizing their design and safety characteristics. The method will be developed for the incorporation of a graded approach as well as a component failure evaluation model using the operation and maintenance experience in the high temperature engineering test reactor into an accident frequency analysis. In addition, a source term evaluation method considering failures in core graphite components will be developed.

Language	:	Japanese
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Meeting title	:	日本原子力学会2016年春の年会
Held date	:	2016/03
Location (city)	:	仙台
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. : BB20152405
JAEA Abstracts No. :
Paper Submission No. :

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