Development of fast reactor containment safety analysis code, CONTAIN-LMR; Validation study of sodium-concrete reaction model

Kawaguchi, Munemichi ; Yamamoto, Ikuo; Seino, Hiroshi

The CONTAIN-LMR code has been developed in Japan Atomic Energy Agency (JAEA) for the quantitative assessment of severe accident consequences in sodium-cooled fast reactor (SFR). We will present results of the development and validation for the sodium-concrete reaction model (SLAM) in this code.

Language	:	Japanese
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Meeting title	:	日本原子力学会2019年春の年会
Held date	:	2019/03
Location (city)	:	水戸
Location (country)	:	日本
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Keywords	:	高速炉; シビアアクシデント評価; 格納容器; ナトリウム-コンクリート反応; CONTAIN-LMR
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Registration No. : BB20181708
JAEA Abstracts No. :
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