日本原子力学会 2014年春の年会

Presentation information

一般セッション

III. 核分裂工学 » 301-2 炉設計と炉型戦略,核変換技術

[K01-05] 超臨界圧軽水炉

Wed. Mar 26, 2014 10:00 AM - 11:15 AM K (1号館 12C)

座長:亀山高範(東海大)

[K03] Super Fast Reactor and Super LWR

(3) Safety analysis of a single flow pass Super Fast Reactor

Sutanto -1, Yoshiaki Oka1 (1.Waseda University)

Keywords:Super fast reactor, Single flow pass core, Safety analysis

A Safety analysis is conducted to evaluate the safety performance of the core design. The safety analysis includes non-LOCA and LOCA analyses. Safety analysis results show that the safety criteria are satisfied for all selected events.