Development of core damage evaluation technology (Level 2 PSA) for fast reactors, 13; Development of analytical code for ex-vessel phenomena; Improvement of sodium-concrete reaction model

Seino, Hiroshi ; Ishikawa, Hiroyasu ; Ohno, Shuji ; Kawaguchi, Munemichi ; Isozaki, Mikio; Miyahara, Shinya

As a part of development of the core damage evaluation technology (level 2 PSA), validation studies were carried out to improve the analytical accuracy for the sodium-concrete reaction model in CONTAIN/LMR.

Language	:	Japanese
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Meeting title	:	日本原子力学会2010年春の年会
Held date	:	2010/03
Location (city)	:	水戸
Location (country)	:	日本
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Keywords	:	no keyword
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Cooperating Institute	:	文部科学省

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Registration No. : BB20093177
JAEA Abstracts No. :
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