2017 Annual Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 302-1 Advanced Reactor System

[2G18-23] Technology developoment of advanced reactor

Tue. Mar 28, 2017 4:55 PM - 6:30 PM Room G (16-207 Building No.16)

Chair: Kenta Ichikawa (MFBR)

5:10 PM - 5:25 PM

[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.