Analytical evaluation of SFR SCCV in the hypothetical sodium leakage

Yamamoto, Tomohiko ; Kato, Atsushi ; Chikazawa, Yoshitaka ; Oya, Takeaki*; Iwasaki, Mikinori*; Akiyama, Yo*

Sodium-cooled Fast Reactor (SFR) is planning to adopt the steel-plate reinforced concrete containment vessel (SCCV). This presentation is the structural integrity and boundary evaluation of SCCV in the hypothetical sodium leakage for construction of safety design criteria (SDC).

Language	:	Japanese
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Meeting title	:	日本原子力学会2012年秋の大会
Held date	:	2012/09
Location (city)	:	東広島
Location (country)	:	日本
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Keywords	:	no keyword
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Cooperating Institute	:	経済産業省

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Registration No. : BB20120391
JAEA Abstracts No. :
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