Perbandingan Kinerja FLiBe Dan FLiNaK sebagai Garam Bahan Bakar dalam Transmutasi Plutonium dan Aktinida Minor Pada MSR Berbasis Thorium

Abstract

The management of nuclear waste, particularly minor actinides (MAs), poses a significant challenge due to their long half-lives and high radiotoxicity. One promising solution is transmutation using advanced reactor systems such as the Molten Salt Reactor (MSR). MSRs operate with liquid fuel mixtures, offering enhanced neutron economy and efficient fuel utilization. In this study, the FUJI-12 type MSR is modeled using the Monte Carlo-based OpenMC simulation code to evaluate the impact of MA addition on reactor criticality 𝑘𝑒𝑓𝑓 and to assess the suitability of two fuel salt compositions FLiBe and FLiNaK for MA transmutation. The reactor is designed for a thermal power output of 350 MWth with a hexagonal core geometry and a burnup cycle of 5 years. The simulation results include variations in 𝑘𝑒𝑓𝑓, MA loading, fission product accumulation, and burnup performance. Analysis reveals that the addition of MAs significantly affects the neutron multiplication factor, and that plutonium-based fuel compositions demonstrate lower compatibility with effective MA burning. These findings contribute to the ongoing optimization of MSR fuel cycles for advanced nuclear waste management