Neutronic analysis on molten salt reactor FUJI-12 using 235U as fissile material in LiF-BeF2-UF4 fuel

Neutronic analysis on the Molten Salt Reactor FUJI-12 using fissile material 235U in LiF-BeF2-UF4 has been carried out. The problem faced use of thorium-based fuel is that amount 233U small and not available nature. was produced through 232Th breeding at a cost $46 million/kg. That very high price when compared to enrichment, which only $100/kg. MSR used this study generation IV reactor with mixture liquid salt LiF-BeF2-ThF4-UF4 (232Th+233U). In study, neutronic out by replacing uranium-based (235U+238U). performed OpenMC 0.13.0 code, Monte Carlo simulation-based neutron code. nuclear data library for calculations ENDF B-VII/1. molten three eutectic compositions: 1, 2, 3. Each composition optimized enriching UF4 3 % 8 %. optimization results show stability criticality value, main parameter so can operate specified time. 1 cannot reach its optimal state each variation enrichment. Fuel 2 conditions minimum enrichment 7 235U. distribution flux core reactions occur core. values shows fission chain reaction running perfectly. are more stable maintaining maximum center