Numerical analysis of JOYO MK-II natural circulation test with plant dynamics code Super-COPD

Hiyama, Tomoyuki ; Doda, Norihiro ; Ohshima, Hiroyuki; Iwasaki, Takashi*

An analysis of JOYO MK-II natural circulation tests has been performed to evaluate the applicability of the fast reactor plant dynamics code Super-COPD. In this study, it is found that the predicted reactor vessel outlet coolant temperature showed good agreement with test results by setting appropriate threshold of Richardson number which determines the change of coolant mixing regime and temperature distribution in the upper plenum due to a decrease of primary flow rate after a reactor trip.

Language	:	Japanese
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Meeting title	:	日本原子力学会2011年秋の大会
Held date	:	2011/09
Location (city)	:	北九州
Location (country)	:	日本
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Registration No. : BB20111020
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