Development of fast reactor containment safety analysis code, CONTAIN-LMR, 3; Development and validation of debris-related analysis models

Seino, Hiroshi ; Kawaguchi, Munemichi ; Izumi, Keitaro*

The CONTAIN-LMR code has been developed in the Japan Atomic Energy Agency to evaluate ex-vessel severe accident progression in a liquid metal fast reactor. As a part of several studies in JAEA, this paper mainly describes a state of the art of a debris-concrete interaction model.

Language	:	Japanese
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Meeting title	:	日本原子力学会2015年春の年会
Held date	:	2015/03
Location (city)	:	日立
Location (country)	:	日本
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Keywords	:	no keyword
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Registration No. : BB20143092
JAEA Abstracts No. :
Paper Submission No. :

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