Tsunami PRA for Japan sodium-cooled fast reactor

JSFRを対象とした津波PRA

西野 裕之  ; 栗坂 健一 ; 山野 秀将   ; 岡野 靖; 堺 公明

Nishino, Hiroyuki; Kurisaka, Kenichi; Yamano, Hidemasa; Okano, Yasushi; Sakai, Takaaki

This study implemented the Tsunami PRA for Japan sodium-cooled fast reactor (JSFR) and assessed effectiveness of the watertight structures by comparison between state having a water tight door and state without those from the view point of the CDF, quantitatively. For this assessment, this study identified initiating events and analyzed accident scenarios after researching important structures and components related to decay heat removal system. And this study calculated the CDF and identified dominant sequence contributing the CDF. The CDF in state having the watertight structures was approximately 1/10 times smaller than that in state without those. From the result, this study showed effectiveness about watertight on the reactor building, quantitatively.