2017 Fall Meeting

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Oral presentation

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

[2C11-16] PRA 3

Thu. Sep 14, 2017 2:45 PM - 4:25 PM Room C (Open Hall - B1 Block)

Chair:Sunghyon Jang (Univ. of Tokyo)

2:45 PM - 3:00 PM

[2C11] Development of Internal Flood Level 1 PRA Model for Light Water Reactor

*Tamio Koriyama1, Kotaro Sakata1, Yoshikane Hamaguchi1, Tomomichi Itoh1 (1. S/NRA/R)

Keywords:PRA, flood scenario, evet tree, fault tree, core damage frequency

Internal flood level 1 PRA methodologies were investigated for 4 loop PWR and ABWR. The results showed that the evaluation methodologies to estimate core damage frequencies were developed precisely and significant flood sources were secondary side pipes for 4 loop PWR and fire protection systems in the control building for ABWR.