R&D for introducing silicon carbide materials to safety improvement of BWR's core, 3; Plant transient analysis with SiC cladding fuel for RIA accident

Horie, Hideki*; Takeuchi, Yutaka*; Kakiuchi, Kazuo*; Sato, Hisaki*; Shirasu, Noriko ; Saito, Hiroaki; Yamashita, Shinichiro ; Fukahori, Tokio

The problem in the accident tolerance fuel development was considered in comparison the fuel behavior of SiC/SiC composite cladding tube with current Zry cladding tube. In this study, Reactivity Initiated Accident (RIA) was evaluated using the plant excess security analysis code TRACTTM and the fuel performance code FEMAXI.

Language	:	Japanese
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Meeting title	:	日本原子力学会2018年秋の大会
Held date	:	2018/09
Location (city)	:	岡山
Location (country)	:	日本
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Keywords	:	事故耐性燃料; SiC; 反応度投入事故; TRACTTM; FEMAXI
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Article of JAEA R&D Review	:
Cooperating Institute	:	経済産業省資源エネルギー庁

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Registration No. : BB20180772
JAEA Abstracts No. :
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