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Report No.

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).



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