R&D of the next generation safety analysis methods for fast reactors with new computational science and technology, 4; Verification plan

Tobita, Yoshiharu; Yamano, Hidemasa ; Morita, Koji*

A basic verification plan has been developed to assess the applicability of the COMPASS code to basic phenomena of heat transfer, dynamic flow, phase change etc. which are involved in complex phenomena in core disruptive accidents of fast reactors. The subsequent integral verification plan has also been defined with considering appropriate existing tests for the code verification as well as with extracting several issues on present core disruptive accident analyses.

Language	:	Japanese
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Meeting title	:	日本原子力学会2007年春の年会
Held date	:	2007/03
Location (city)	:	名古屋
Location (country)	:	日本
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Keywords	:	no keyword
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Cooperating Institute	:	東京大学

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Registration No. : BB20062689
JAEA Abstracts No. :
Paper Submission No. :

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