Probabilistic Risk Assessment Method Development for High Temperature Gas-cooled Reactors

Tatsuya Itoi

Presentation information

Oral presentation

III. Fission Energy Engineering » 306-1 Nuclear Safety Engineering, Nuclear Installation Safety, PSA

[3M11-16] Probabilistic Risk Assessment

Wed. Mar 29, 2017 2:45 PM - 4:20 PM Room M (16-504 Building No.16)

Chair: Yasushi Okano (JAEA)

3:15 PM - 3:30 PM

[3M13] Probabilistic Risk Assessment Method Development for High Temperature Gas-cooled Reactors

(5)Development of Seismic Fragility Analysis Method

*Tatsuya Itoi¹, Tsuyoshi Takada¹, Akemi Nishida², Ryohei Tanaka¹, Takenori Hida¹ (1. The University of Tokyo, 2. Japan Atomic Energy Agency)

Keywords:High Temperature Gas-cooled Reactors, Seismic Risk, Seismic Fragility

An overview of development plan for seismic PRA methodology for high temperature gas-cooled reactors (HTGRs) is discussed focusing on seismic fragility analysis.