[2O16-20] Design and Demand of Advanced Reactor

[2O20] A Conceptual Design Study on Pool-type Sodium-cooled Fast Reactor with Enhanced Anti-seismic Capability

(3) Steady State Thermal Hydraulic Analyses in Reactor Vessel

*Ichiyo Matoba¹, Junji Endo¹, Osamu Watanabe¹, Yoshitaka Chikazawa², Shigenobu Kubo², Hiroyuki Ohshima², Masato Uchita³ (1. Mitsubishi FBR Systems Inc., 2. Japan Atomic Energy Agency, 3. Japan Atomic Power Company)

Keywords:Pool-type Sodium-cooled Fast Reactor, Three dimensional thermal hydraulic analysis

タンク型のナトリウム冷却高速炉（SFR）の原子炉構造について、平板形状の新たなプレナム仕切構造にした定格運転時の３次元定常熱流動解析を実施し、プレナム仕切板の上下面の温度差低減効果を確認した。