Gunay, M.2024-08-042024-08-0420140932-3902https://doi.org/10.3139/124.110364https://hdl.handle.net/11616/96407In this study, the effect of spent fuel grade plutonium content on Pu259-243 was investigated in a designed hybrid reactor system. In this system, the fluids were composed of a molten salt, heavy metal mixture with increased mole fractions 99-95% Li20Sn80-1-5% SFG-Pu, 99-95% Li20Sn80-1-5% SFG-PuF4, 99-95% Li20Sn80-1-5% SFG-PuO2. Beryllium (Be) is a neutron multiplier by (n,2n) reactions. Thence, a Be zone of 3 cm thickness was used in order to contribute to fissile fuel breeding between the liquid first wall and a 9Cr2WVTa ferritic steel blanket which is used as structural material. The production of Pu238-242(n,gamma)Pu239-243 was calculated in liquid first wall, blanket and shielding zones. Three-dimensional nucleonic calculations were performed by using the most recent version MCNPX-2.7.0 Monte Carlo code and nuclear data library ENDF/B-VII.0.eninfo:eu-repo/semantics/closedAccess3-Dimensional Neutronic CalculationsPower Density ConceptsApex ReactorStructural MaterialRadiation-DamageArticle791586210.3139/124.1103642-s2.0-84898063579N/AWOS:000334145300008Q4