Validation of numerical simulation method for thermal stratification in reactor vessel upper plenum of fast reactor

Ohno, Shuji ; Oki, Hiroshi*; Sugahara, Akihiro*; Ohshima, Hiroyuki

Validation study of numerical simulation method is in progress for thermal stratification phenomena in a reactor vessel upper plenum of advanced sodium-cooled fast reactors. This paper describes the current status of the study using two kinds of thermal stratification experiments and commercial CFD codes STAR-CD, FLUENT, and an in-house code AQUA.

Language	:	English
Journal	:	Proceedings of 6th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-6) (USB Flash Drive)
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Pages	:	7 Pages
Publication Year/Month	:	2008/11
Meeting title	:	6th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-6)
Held date	:	2008/11
Location (city)	:	Nago
Location (country)	:	Japan
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Keywords	:	no keyword
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Registration No. : BB20082466
JAEA Abstracts No. : 37000086
Paper Submission No. : 5077

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