高速炉の重大事故防止対策有効性評価に関する検討,5; 崩壊熱除去機能喪失事象評価に用いる原子炉解析モデル

Study on effectiveness evaluations of countermeasures against severe accidents in fast reactor, 5; Validation of reactor analytical model for PLOHS events

森 健郎 ; 大平 博昭; 素都 益武 ; 深野 義隆  

Mori, Takero; Ohira, Hiroaki; Sotsu, Masutake; Fukano, Yoshitaka

高速炉における崩壊熱除去機能喪失時の炉心損傷防止対策であるナトリウム自然循環冷却の有効性を評価するために、炉心の全集合体毎の自然循環冷却挙動を解析する解析モデルについて、もんじゅの実機試験結果を用いて妥当性の確認を行い、崩壊熱除去機能喪失事象への適用性を確認した。

In order to evaluate the availability of the decay heat removal by natural circulation which is a measure for the Protected Loss of Heat Sink (PLOHS) in Fast Reactor, a whole core model which could simulate thermal hydraulics of each subassembly in a reactor was applied to Monju core. The Monju core model was validated by a test result of actual plant, MONJU. In addition, an analysis was conducted for PLOHS to investigate the applicability of this model.