Browsing LSP-Jurnal Ilmiah Dosen by Subject "uranium fluoride"
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Neutronic Analysis On Molten Salt Reactor Fuji-12 Using 235U as Fissile Material In Lif-BEF2-UF4 Fuel
(Eastern-European Journal of Enterprise Technologies, 2022-10-31)Neutronic analysis on the Molten Salt Reactor FUJI-12 using the fissile material 235U in LiFBeF2-UF4 has been carried out. The problem faced in the use of thorium-based fuel is that the amount of 233U is small and not ...