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

[2J19] Preliminary Studies for Applicability related to the Large Reactor Vessel of Pool-type SFR

(3)Thermal Transient Evaluation

*Yoshitaka Chikazawa¹, Shigenobu Kubo¹, Takayuki Miyagawa², Masao eto³ (1. JAEA, 2. JAPC, 3. MFBR)

Keywords:sodium-cooled fast reactor, pool type reactor, thermal transient

Thermal stress on the reactor vessel at the sodium level has been evaluated. The reactor vessel structure has been improved considering severe seimic conditions. Using the improved design and taking into account sodium level transient during scram, creep fatigue and ratchet on the reactor vessel wall at the sodium level have been evalated.