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    The effect on radiation damage of structural material in a hybrid system by using a Monte Carlo radiation transport code
    (Pergamon-Elsevier Science Ltd, 2014) Gunay, Mehtap; Sarer, Basar; Kasap, Hizir
    In this study, the molten salt-heavy metal mixtures 99-95% Li20Sn80-1-5% SFG-Pu, 99-95% Li20Sn80-1-5% SFG-PuF4, 99-95% Li20Sn80-1-5% SFG-PuO2 were used as fluids. The fluids were used in the liquid first-wall, blanket and shield zones of the designed hybrid reactor system. 9Cr2WVTa ferritic steel with the width of 4 cm was used as the structural material. The parameters of radiation damage are proton, deuterium, tritium, He-3 and He-4 gas production rates. In this study, the effects of the selected fluid on the radiation damage, in terms of individual as well as total isotopes in the structural material, were investigated for 30 full power years (FPYs). Three-dimensional analyses were performed using the most recent version of the MCNPX-2.7.0 Monte Carlo radiation transport code and the ENDF/B-VII.0 nuclear data library. Published by Elsevier Ltd.
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    Neutronic investigation of the application of certain plutonium-mixed fluids in a fusion-fission hybrid reactor
    (Pergamon-Elsevier Science Ltd, 2014) Gunay, Mehtap; Kasap, Hizir
    In this study, the fluids that were investigated were contained increased mole fractions of the mixtures molten salt 99-95% Li20Sn80 and, the heavy metals 1-5% SFG-Pu, SFG-PuF4, SFG-PuO2. The fluids were used in the liquid first wall, blanket and shield zones of the designed hybrid reactor system. Beryllium (Be) zone with the width of 3 cm was used for the neutron multiplicity between liquid first wall and blanket. Four centimeter thick 9Cr2WVTa ferritic steel was used as the structural material. The nuclear parameters of a fusion-fission hybrid reactor such as neutron flux, heating, fission reaction rate were investigated according to the mixture components, radial energy spectrum in the designed system. In this study, the effect of spent fuel-grade Pu content in the designed system on these nuclear parameters were calculated by using the three-dimensional Monte Carlo code MCNPX-2.7.0 and nuclear data library ENDF/B-VII.0. Crown Copyright (C) 2013 Published by Elsevier Ltd. All rights reserved.