4:00 PM - 4:15 PM
[3I11] Feasibility Study of Integral Molten Chloride Salt Fast Reactor
(4)Coupled Dynamics and Safety
Keywords:Molten Salt Fast Reactor, Neutronics-Thermalhydraulics coupling, Flowout of precursor, point-kinetics equation, Unprotected loss-of-flow, Inherent safety
In the molten salt fast reactor, the delayed neutron fraction is lost due to the outflow of delayed neutron precursor, and the delayed neutron fraction during normal operation is lowered compared to the conditions with no flow. Considering this fact, the point kinetics equation was discretized and the nuclear-thermalhydlaulics coupling analysis could be performed using the UDF of the FLUENT code. Also, in RELAP5-3D, it was made possible to analyze by applying appropriate values to the kinetic parameters.
The results of of the ULOF event simulated by two codes showed almost the same behavior. With all pumps stopped, a negative reactivity was applied due to the core temperature rise, and the reactor power decreased to the decay heat level without scrum. This shows the inherent safety of the reactor.
The results of of the ULOF event simulated by two codes showed almost the same behavior. With all pumps stopped, a negative reactivity was applied due to the core temperature rise, and the reactor power decreased to the decay heat level without scrum. This shows the inherent safety of the reactor.