[2J15-19] Pump and Reactor Vessel of Na-cooled Reactor

[2J17] Preliminary Studies for Applicability related to the Large Reactor Vessel of Pool-type SFR

(1)Seismic Evaluation

*Masato Uchita¹, Koji Dozaki¹, Tetsuji Suzuno², Tsuyoshi Fukasawa², Hiroki Hayafune³, Atsushi Katoh³ (1. Japan Atomic Power Company , 2. Mitsubishi FBR Systems Inc., 3. Japan Atomic Energy Agency)

Keywords:Pool-Type Reactor, Reactor Vessel, Buckling Evaluation, Vertical Seismic Isolation System

Regarding the reactor vessel of pool-type SFR, seismic evaluation is conducted under the seismic conditions taking account of LWR sites in Japan. As the result, it is cleared the minimum wall thickness of the reactor vessel with larger size against buckling and the seismic feasibility on the difference between the horizontal seismic isolation system and the vertical seismic isolation system.