Three-dimensional neutronic calculations for a fusion breeder APEX reactor using some libraries

Abstract

The effects of evaluated nuclear data files on neutronics characteristics of a fusion–fission hybrid reactor have been analyzed; three-dimensional calculations have been made using the MCNP4C Monte Carlo Code for ENDF/B-VII T = 300 K, JEFF-3.0 T = 300 K, and CENDL-2 T = 300 K evaluated nuclear data files. The nuclear parameters of a fusion–fission hybrid reactor such as tritium breeding ratio, energy multiplication factor, fissile fuel breeding and nuclear heating in a first wall, blanket and shield have been investigated for the mixture components of 90% Flibe (Li 2BeF 4) and 10% UF 4 for a blanket layer thickness of 50 cm. The contributions of each isotope of Flibe ( 6Li, 7Li, 19F, 9Be) and UF 4 ( 235U, 238U) to the integrated parameter values were calculated. The neutron wall load is assumed to be 10 MW/m 2.