2018 Fall Meeting

Presentation information

Oral presentation

IV. Nuclear Plant Technologies » 401-3 Reactor Design, Construction and Examination of Nuclear Power Station, Aseismatic Design, Nuclear Ship

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

Thu. Sep 6, 2018 4:25 PM - 5:45 PM Room O (D25 -D Building)

Chair:Yoshihisa Nishi(CRIEPI)

5:25 PM - 5:40 PM

[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。