[2F05-09] Fast Reactor Thermal Hydraulics 1

[2F09] Coupled Neutronics and Thermalhydraulics of Molten Salt Fast Reactor

*Hiroyasu MOCHIZUKI^1,3, Michio YAMAWAKI^2,3 (1. Tokyo Institute of Technology, 2. The University of Tokyo, 3. BERD)

Keywords:Molten Salt Fast Reactor, Loss of AC Power, Coupled Neutronics and Thermalhydraulics, Temperature Reactivity Coefficient, Inherent Safety

Molten salt fast reactors generally have negative temperature reactivity coefficients and void reactivity coefficients. It is simulated using two system codes incorporated with physical properties of fuel salt and reactivity coefficients how the molten salt fast reactor responds to a total blackout that triggered the Fukushima accident. Other large transients are also simulated. In the molten salt fast reactor of the analysis system, when a large transient is applied to the core, a negative reactivity is applied without control rod by raising the core temperature. This means that the reactor had an inherent safety. In order to make the evaluation results accurate in the future, it is necessary to obtain the accurate physical properties of the fluid and to change the physical properties of the code.