2018 Annual Meeting

Presentation information

Oral presentation

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

[3B09-13] Light Water Reactor Safety Assessment

Wed. Mar 28, 2018 2:45 PM - 4:05 PM Room B (C1-311 -C1 Building)

Chair: Kenta Murakami (Nagaoka Univ. of Tech.)

3:15 PM - 3:30 PM

[3B11] Flood propagation analysis for internal flood PRA by using Apros code

(2)Results of flood propagation analysis for internal flood PRA

*Yoshikane Hamaguchi1, Tomomichi Itoh1, Tamio Koriyama1 (1. Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority(S/NRA/R))

Keywords:Probabilistic risk assessment, Apros, Internal flood, Flood propagation analysis

The flood propagation of internal flood PRA has been calculated by using Apros for a generic PWR plant. This calculation is focused on important flood sources and initiating events of internal event such as interfacing system LOCA, main feedwater piping rupture which are relatively high risk based on the internal flood PRA.