Development and application of seismic fragility analysis method for high temperature gas-cooled reactors

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

This research aims to establish a probabilistic risk assessment method for high temperature gas-cooled reactors fully utilizing their design and safety characteristics. In this presentation, an overview of development for seismic PRA methodology for high temperature gas-cooled reactors (HTGRs) is explained 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.