Investigation of tritium breeding ratio using different coolant material in a fusion–fission hybrid reactor

Abstract

The aim of this study is to investigate tritium breeding ratio (TBR) and first wall material damage parameters such as displacement per atom (DPA), gas production of various coolants with Li2C2 tritium breeding material using the three different data libraries (ENDF/B.V, ENDF/B.VI and CLAW IV). Hence, FLiNaK, enriched (90% 6Li) natural lithium, lithium-lead eutectic alloy (Li17Pb83) and FLiBe (Li2BeF4) were used as a coolant (moderator) material for the calculation of the tritium breeding ratio and gas production parameters in a hybrid reactor. Neutronic calculations were performed by Monte Carlo Neutron-Particle Transport code MCNP5 version 1.40 under a neutron wall loud of 2.25 MW/m2 (1014 n/s) by full reactor power for one year. All examined coolant materials were achieved minimum required tritium breeding ratio (TBR > 1.05) and based on radiation damage limits. When the enriched (90%) lithium coolant with lithium carbide breeder used in fusion–fission (hybrid) reactor, vanadium alloy first wall will be replaced every 3.6 and 6.7 years for DPA and Helium production, respectively.