Probabilistic risk assessment method development for high temperature gas-cooled reactors, 3; Development plan of seismic fragility analysis method

Itoi, Tatsuya*; Nishida, Akemi ; Takada, Tsuyoshi* ; Hida, Takenori*; Muramatsu, Ken*; Sato, Hiroyuki

In this paper, an overview of development plan for seismic PRA methodology for high temperature gas-cooled reactors (HTGRs) is discussed focusing on seismic fragility analysis. The developed seismic fragility analysis has the features as follows: (1) Appropriate treatment of uncertainty in seismic fragility analysis, (2) Utilization of ground motion simulation considering fault rupture process, (3) Utilization of detailed finite element models for seismic fragility analysis. It is also intended that seismic fragility analysis method to be developed is applicable to that of light water reactors.

Language	:	English
Journal	:	Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM)
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Number	:
Pages	:	5 Pages
Publication Year/Month	:	2017/04
Meeting title	:	2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017)
Held date	:	2017/04
Location (city)	:	Fukui/Kyoto
Location (country)	:	Japan
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DOI for research data	:
Keywords	:	no keyword
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Article of JAEA R&D Review	:
Cooperating Institute	:	東京都市大学; 東京大学

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Registration No. : BB20170180
JAEA Abstracts No. : 45001386
Paper Submission No. : 19612

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