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

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

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.

Language	:	Japanese
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Meeting title	:	日本原子力学会2017年春の年会
Held date	:	2017/03
Location (city)	:	平塚
Location (country)	:	日本
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Keywords	:	高速炉; 崩壊熱除去機能喪失; ナトリウム自然循環冷却; 原子炉原子炉モデル
Research Facility	:	もんじゅ(高速増殖炉原型炉)
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Registration No. : BB20161781
JAEA Abstracts No. :
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