Natural Uranium Utilization in FUJI-U3 Molten Salt Reactor

Abstract

Abstract Molten Salt Reactor (MSR) is one of the next-generation nuclear power systems known as Generation IV. In this paper, the FUJI-U3 MSR type is designed for neutronic analysis that natural uranium is used as a fuel. The standard reactor core model is adopted due to the flux flattening effect in the active core, as reported from previous research. FLiBe eutectic is used both as the coolant salt and moderator in the reactor core. The neutronic calculation is performed using the SRAC 2006 program: PIJ for pin cell calculation and Citation for core calculation. JENDL 4.0 is used as a nuclear data library that provides the cross-section data of the nuclides. The neutronic parameter results, such as the effective multiplication factor, conversion ratio, neutron spectrum, and power density, are obtained from the calculation. The reactor can achieve the criticality condition with a minimum loading Uranium Tetrafluoride (UF4) of 3.6%mol for 2000 effective full power days (EFPD). The results calculation provide some parameter survey for the research and the future development of MSR.