The Comparison of Effect on Neutronic Calculations of ENDF/B-VIII.0 Nuclear Library and Am-Cm Additive Fluids in a Hybrid Reactor System

Abstract

In this study, a fusion–fission hybrid reactor system was designed by using V₄Cr₄Ti Ferritic steel structural material and the molten salt-heavy metal mixture 79,9% Li₁₇Pb₈₃ + 20% ThF₄ + 0,1% AmO₂ and 79,9% Li₁₇Pb₈₃ + 20% ThF₄ + 0,1% CmO_2, as fluids. The fluids were used in the liquid first wall, blanket and shield zones of a fusion–fission hybrid reactor system. Beryllium (Be) zone with the width of 3 cm was used for the neutron multiplication between the liquid first wall and blanket. In this study was investigated the nuclear parameters such as tritium breeding ratio (TBR), energy multiplication factor (M), heat deposition rate, fission reaction rate in liquid first wall, blanket and shield zones. Three-dimensional analyses were performed by using the Monte Carlo code MCNPX-2.7.0, NJOY and ENDF/B-VIII.0 nuclear data library.

Keywords

• Nuclear Library,Hybrid Reactor,Fluids

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