[2H01-05] Molten Salt Reactor 1

[2H02] Feasibility Study of Integral Molten Chloride Salt Fast Reactor (III)

(2) Safety in the event of transients

*Hiroyasu MOCHIZUKI¹ (1. Tokyo Tech)

Keywords:Molten salt fast reactor, Neutronics-thermalhydraulics coupling, Reactivity insertion, Inherent safety, FLUENT, RELAP5-3D, ATWS

Various transient events in a molten salt fast reactor without control rods were analyzed by coupled neutronics-thermalhydraulics analysis using the FLUENT code which is coupled nuclear kinetic models with UDF, and the RELAP5-3D code. As a result, it was clarified that the temperatures of the reactor transients were within the range of safe temperatures.