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加治 芳行; 勝山 仁哉; 山口 義仁; 根本 義之; 阿部 陽介; 永瀬 文久
no journal, ,
東京電力福島第一原子力発電所における過酷事故進展及び炉内状況の推定に役立てることを目的として、溶融燃料の落下に伴う原子炉圧力容器下部ヘッドの破損挙動を評価するための研究を進めている。本講演では、解析に必要な原子炉圧力容器構成材料の高温引張・クリープデータ等の材料特性データや熱流動解析及び熱流動・構造連成解析に用いる下部ヘッド詳細解析モデルについて説明するとともに、種々の事故シナリオにおける熱流動・構造連成解析を行い過酷事故時の原子炉圧力容器下部ヘッドの破損挙動を評価した結果について発表する。
佐藤 拓未; 山下 拓哉; 下村 健太; 永江 勇二
no journal, ,
The reaction between the molten metallic debris pool and the structural materials of reactor pressure vessels (RPV) is important in understanding the RPV failure behavior. In this study, the ELSA (Experiment on Late In-vessel Severe Accident Phenomena)-1 test, which focuses on the damage caused by the eutectic melting of the liquid metal pool and control rod drive (CRD) structures, was conducted. A test sample simulating the CRD structure at the lower head was fabricated and loaded with Fe-Zr alloy as the simulated metal debris. The sample was gradually heated to about 1400 C using the LIESAN test facility, and in-situ observation was performed using a video camera. The test results showed that the CRD structural material reacted with the metal debris and melted at about 1050-1250
C, which was lower than the melting point of the CRD itself. It was also observed that the molten material flowed into the CRD, suggesting that the CRD structure was preferentially damaged during the severe accident.