Radiation damage on low activation materials used in a hybrid reactor

Structural material selection in design of fusion-fission (hybrid) reactors is very crucial to enhance the neutronic performance. Low activation materials have important potential to be used in fusion or hybrid reactors. This study presents radiation damage behavior of the primary low activation materials namely, ferritic steel (9Cr-2VWTa), vanadium alloy (V-4Cr-4Ti) and SiCf/SiC composite used as first wall and fuel clad structural material in a (DT) fusion driven hybrid reactor under a NWL of 2 MW/m2 for a plant operation of 1 year. Calculations were performed by using the code, SCALE4.3 solving the Boltzmann neutron transport equation. Among the investigated materials V-4Cr-4Ti showed the best performance with respect to radiation damage