2018 Fall Meeting

Presentation information

Oral presentation

IV. Nuclear Plant Technologies » 402-1 Nuclear Safety Engineering (Safety Design, Safety Assessment/Analysis, Management)

[2P10-17] Spent Fuel Pool

Thu. Sep 6, 2018 2:45 PM - 4:55 PM Room P (E21 -E Building)

Chair:Yamato Hayashi(TOSHIBA ESS)

3:45 PM - 4:00 PM

[2P14] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(24) Create a data base of BWR fuel temperature in SFP based on the steady-state heat transfer analyses

*Daisuke Goto1, Kensuke Kobayashi1, Masayuki Tojo1, Yoshiyuki Nemoto2, Yoshiyuki Kaji2 (1. GNF-J, 2. JAEA)

Keywords:BWR, SFP, Steady-state heat transfer analysis, Fuel cladding temperature

2016年秋の大会、2E21で報告した3次元定常熱伝達解析を用いて、様々なBWRラックの設計タイプ、設置条件、崩壊熱量、発熱分布などを考慮したパラメータサーベイを行い、ラック内の最高燃料温度を把握するためのデータベースを構築した。