[3I01-06] Sodium-cooled Fast Reactor-related Evaluation and Technology Development

[3I01] Thermal transient evaluation of pool-type SFR

*Atsushi Kato¹, Yuichi Onoda¹, Takayuki Miyagawa², Jyunji Endo³, Koji Kubo³ (1. JAEA, 2. JAPC, 3. MFBR)

Keywords:sodium cooled fast reactor, pool type SFR, thermal transient analysis

JAEA, JAPC and MFBR are studying about conceptual design of a pool type sodium fast reactor (SFR). Since the reactor vessel of the pool type SFR includes the primary pump and the intermediate heat exchanger, dynamics of flow in the reactor vessel is different from the one of a loop type reactor. It is essential to grasp the flow dynamics of the pool type SFR for design improvement. This report introduces design measures to improve internal flow efficiency, and also reports thermal transient evaluation in the case of reactor trip. Structural intactness was assured based on these evaluations.