[3K07-09] Fast Reactor Core & Fuel 1

[3K09] Development of transient behavior analysis code for metal fuel fast reactor during initiating phase of core disruptive accident

(1)Code modification based on experimental analysis of transient overpower tests

*Hirokazu Ohta¹, Kouji Kusumi¹, Hidemasa Yamano², Kazuya Ohgama², Satoshi Futagami², Sadae Shimada³, Yumi Yamada³ (1. CRIEPI, 2. JAEA, 3. MFBR)

Keywords:Fast reactor, Metal fuel, Core disruptive accident, Initiating phase , Core safety, Extrusion

The experimental analysis of transient overpower tests by TREAT reactor revealed some technical issues to be improved in a transient behavior analysis code for metal fuel fast reactor during initiating phase of core disruptive accident, CANIS. Modified CANIS for changes in the properties due to fuel constituent redistribution during irradiation and an increase in the thinning rate of cladding under high temperature conditions has made good predictions of the history of reactivity decrease due to molten fuel extrusion, the area of fuel melts and the cladding wall thinning after transient test.