Gunay, M.Sarer, B.Kasap, H.2024-08-042024-08-0420140973-14580974-9845https://doi.org/10.1007/s12648-014-0496-4https://hdl.handle.net/11616/96489In the present investigation, a fusion-fission hybrid reactor system was designed by using 9Cr2WVTa ferritic steel structural material and 99-95 % Li20Sn80-1-5 % SFG-Pu, 99-95 % Li20Sn80-1-5 % SFG-PuF4, 99-95 % Li20Sn80-1-5 % SFG-PuO2 the molten salt-heavy metal mixtures, as fluids. The fluids were used in the liquid first wall, blanket and shield zones of a fusion-fission hybrid reactor system. Beryllium zone with the width of 3 cm was used for the neutron multiplicity between liquid first wall and blanket. The contributions of each isotope in fluids on the nuclear parameters of a fusion-fission hybrid reactor such as tritium breeding ratio, energy multiplication factor, heat deposition rate were computed in liquid first wall, blanket and shield zones. Three-dimensional analyses were performed by using Monte Carlo code MCNPX-2.7.0 and nuclear data library ENDF/B-VII.0.eninfo:eu-repo/semantics/closedAccessHybrid reactorTritium breeding ratioHeat deposition rateMCNPX-2.7.0Article88886186610.1007/s12648-014-0496-42-s2.0-84903625193Q3WOS:000344777800012Q2