Development of Super-COPD code for plant dynamics, 8; Development of Monju safety analytical model

Yamada, Fumiaki; Minami, Masaki*

A computational model to simulate integrated behaviors of a reactor core and the connected heat transport system was built and verified by trial calculations on a set of representative anomaly transient event, in order for application of the plant dynamics analysis code Super-COPD to evaluation of the cooling capability of Monju reactor core.

Language	:	Japanese
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Meeting title	:	日本原子力学会2010年秋の大会
Held date	:	2010/09
Location (city)	:	札幌
Location (country)	:	日本
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Registration No. : BB20100973
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