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    • Neutronic Analysis On Molten Salt Reactor Fuji-12 Using 235U as Fissile Material In Lif-BEF2-UF4 Fuel 

      MABRURI, Ahmad Muzaki; SYARIFAH, Ratna Dewi; AJI, Indarta Kuncoro; HANIFAH, Zein; ARKUNDATO, Artoto; JATISUKAMTO, Gaguk (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 ...