Nuclear and thermal design for high temperature gas-cooled reactor with SiC matrix fuel

Goto, Minoru ; Inaba, Yoshitomo ; Aihara, Jun ; Ueta, Shohei ; Tachibana, Yukio

JAEA has performed the research and development of the SiC matrix fuel, which is an oxidation resistant fuel against an air ingress accident, to establish the fundamental technologies. In this study, a nuclear thermal design was performed for the HTGR with the SiC matrix fuel.

Language	:	Japanese
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Meeting title	:	日本原子力学会2016年春の年会
Held date	:	2016/03
Location (city)	:	仙台
Location (country)	:	日本
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Keywords	:	高温ガス炉; 核熱設計; 空気侵入事故; 耐酸化燃料
Research Facility	:	HTTR(高温工学試験研究炉)
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Registration No. : BB20152809
JAEA Abstracts No. :
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