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高速炉の炉心損傷評価技術(レベル2PSA)の開発,12; 研究開発の総括

Development of core damage evaluation technology (Level 2 PSA) for fast reactors, 12; Overview of evaluation technology development

中井 良大 ; 鈴木 徹; 神山 健司  ; 小山 和也*; 守田 幸路*

Nakai, Ryodai; Suzuki, Toru; Kamiyama, Kenji; Koyama, Kazuya*; Morita, Koji*

ナトリウム冷却高速炉の炉心損傷評価技術(レベル2PSA)を開発するため、炉心物質再配置と格納容器内事象に関する評価手法を新たに開発するとともに、現象論的イベントツリーを構築するうえで必要な技術的根拠を整備した。

The core damage evaluation technology (Level 2 PSA) for sodium-cooled fast reactors was developed focusing on the material-relocation phase and the ex-vessel accident sequence. In addition, the technical basis to be efficiently utilized for the phenomenological event trees was compiled.

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