Decay Heat Removal System Concept and Basic Operation of Pool-Type Sodium-Cooled Fast Reactor

Presentation information

Oral presentation

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

[3C01-05] Design and Inspection of Nuclear Power Plant

Wed. Mar 15, 2023 10:30 AM - 11:55 AM Room C (11 Bildg.2F 1106)

Chair:kazuhito asano(Toshiba ESS)

11:30 AM - 11:45 AM

*Kenta Ichikawa¹, Shuhei Nakata¹, Masato Ando², Yoshitaka Chikazawa², Atsushi Kato² (1. MFBR, 2. JAEA)

Keywords:Sodium-Cooled Fast Reactor, Decay Heat Removal System

タンク型ナトリウム冷却高速炉の概念検討において、自然循環除熱の活用や除熱方式の多様性確保等を考慮した崩壊熱除去系概念を構築し、原子炉トリップ後の基本的なプラント運用方針を策定した。