Transmutation and Breeding Performance Analysis of Molten Chloride Salt Fast Reactor Using a Fuel Management Code with Nodal Expansion Method

The transmutation of transuranic (TRU) elements produced by pressurized water reactors (PWRs) can effectively reduce their radioactive hazards. molten chloride salt fast reactor (MCSFR) is a type liquid-fueled (MSR) using fuel in the form salts. MCSFR utilizing neutron spectrum and high actinide fraction considered to be potential for TRU transmutation. An online refueling reprocessing scenario unique feature MSRs. On account this characteristic, new management code named ThorNEMFM with nodal expansion method (NEM) was developed validated breeder (MSBR) (MSFR) benchmarks. Then, breeding performances were simulated analyzed code. adopts as initial fissile loads feeding materials. results show that ratio reach 50%, 1.359. Moreover, has low radiotoxicity due lower buildup fission products (FPs).