2017 Annual Meeting

Presentation information

Oral presentation

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

[2M15-18] Safety Evaluation on Fast Reactor 2

Tue. Mar 28, 2017 4:05 PM - 5:10 PM Room M (16-504 Building No.16)

Chair: Hiroshi Endo (CRIEPI)

4:50 PM - 5:05 PM

[2M18] Availability evaluation of passive reactor shut-down system in partial load operating conditions of the next generation sodium-cooled fast reactor

*HIROYUKI SAITO1, YUMI YAMADA1, KAZUHIRO OYAMA1, SHOKO MATSUNAGA1, SHIGENOBU KUBO2, HIDEMASA YAMANO2 (1. MFBR, 2. JAEA)

Keywords:Safety evaluation, Self-actuated shutdown system, Next generation reactor, Sodium-cooled fast reactor

自己作動型炉停止機構(SASS)の応答特性の改善を目的に構造変更等を実施し、3次元熱流動解析にて応答時間を設定するとともに、部分負荷時の代表的なLOF型事象ATWSを対象にSASSの有効性を確認した。