2018 Annual Meeting

Presentation information

Oral presentation

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

[3B04-08] PRA 4

Wed. Mar 28, 2018 10:35 AM - 11:55 AM Room B (C1-311 -C1 Building)

Chair: Hitoshi Muta (Tokyo City Univ.)

11:20 AM - 11:35 AM

[3B07] KK-6,7 project Internal Event Operating Level 1 PRA Model Sophistication Progress Report

(6)Scope of LOCA outside PCV and internal flooding PRA

*Hiroaki Sonoyama1, Shohei Yamagishi1, Ryota Tomiyasu1, Shunsuke Tanno1, Teruyoshi Sato1, Toshiteru Saito1, Masayuki Hiraide2, Toshinobu Kita2 (1. TEPCO SYSTEMS CORPORATION, 2. Tokyo Electric Power Company Holdings, Inc.)

Keywords:PRA, Internal Flooding PRA, LOCA outside PCV

内的事象運転時レベル1PRA高度化では起因事象としてISLOCA及び高エネルギ配管破損(HELB)を抽出したが,これらは格納容器外LOCAであり溢水に伴う間接的な影響が発生しうる。このため,内的事象の格納容器外LOCAで取り扱う配管の評価範囲と内部溢水PRAにおける評価範囲について整理した。