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

Authors : Mehtap DÜZ, Hilal BARDAKCİ

Pages : 96-101

View : 11 | Download : 5

Publication Date : 2018-08-06

Article Type : Research Paper

Abstract :In this study, a fusion–fission hybrid reactor system was designed by using V 4 Cr 4 Ti Ferritic steel structural material and the molten salt-heavy metal mixture 79,9 % Li 17 Pb 83 + 20% ThF 4 + 0,1% AmO 2 and 79,9 % Li 17 Pb 83 + 20% ThF 4 + 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 insert ignore into journalissuearticles values(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 insert ignore into journalissuearticles values( TBR ); , energy multiplication factor insert ignore into journalissuearticles values( 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