[2G18-23] Technology developoment of advanced reactor

[2G19] Preliminary Study for the Seismic Design about the Reactor Vessel of Pool-type SFR

*Takayuki Miyagawa¹, Koji Dozaki¹, Yoshio Kamishima², Shigeki Okamura², Hiroki Hayafune³, Atsushi Katoh³ (1. Japan Atomic Power Company, 2. Mitsubishi FBR Systems INC., 3. Japan Atomic Energy Agency)

Keywords:Sodium-Cooled Fast Reactor (SFR), Reactor Vessel, Pool-Type Reactor , Seismic Design, Buckling Evaluation

Regarding the reactor vessel of pool-type SFR equivalent to 1500MW thermal power, seismic evaluation is conducted roughly by focusing on buckling of the cylindrical wall under the seismic conditions corresponded to LWR sites in Japan.