Consideration of acceptance level of gas bubbles entrained at free surface in reactor vessel of fast reactor

Tatsumi, Eisaku*; Takata, Takashi*; Yamaguchi, Akira*; Ohshima, Hiroyuki; Ito, Kei; Kamide, Hideki

In order to estimate inert gas behavior in a circulating system of a sodium-cooled fast reactor, the plant dynamics code called the VIBUL code has been employed. In this study, the VIBUL was used to evaluate the effect of gas entrainment phenomena at free surface in upper plenum on the void fraction at core inlet.

Language	:	Japanese
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Meeting title	:	日本原子力学会2008年春の年会
Held date	:	2008/03
Location (city)	:	吹田
Location (country)	:	日本
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Keywords	:	no keyword
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Article of JAEA R&D Review	:
Cooperating Institute	:	大阪大学

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Registration No. : BB20073383
JAEA Abstracts No. :
Paper Submission No. :

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