Development of numerical simulation code for thermal striping phenomena in Japan sodium cooled fast reactor

Tanaka, Masaaki ; Murakami, Satoshi*; Oki, Hiroshi*; Ohshima, Hiroyuki

Strategy of the numerical estimation method development for the thermal fatigue in JSFR at JAEA is explained from the numerical simulation code development step to the application step for practical problems. Numerical simulation codes prepared for the study and outlines of the verification and validation study are briefly described. Numerical results in a T-junction piping system and typical numerical results around typical control rod channels and the blanket fuel subassemblies simulating the JSFR are shown as examples in recent progress.

Language	:	English
Journal	:	Proceedings of Joint International Conference of 7th Supercomputing in Nuclear Application and 3rd Monte Carlo (SNA + MC 2010) (USB Flash Drive)
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Pages	:	6 Pages
Publication Year/Month	:	2010/10
Meeting title	:	Joint International Conference of 7th Supercomputing in Nuclear Application and 3rd Monte Carlo (SNA + MC 2010)
Held date	:	2010/10
Location (city)	:	Tokyo
Location (country)	:	Japan
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DOI for research data	:
Keywords	:	no keyword
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Registration No. : BB20102403
JAEA Abstracts No. : 38001569
Paper Submission No. : 8237

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