Neutronic analysis of an inertial fusion energy breeder with SiC f/SiC

Abstract

Neutronic performance of a blanket driven ICF (Inertial confinement fusion) neutron based on SiC f/SiC composite material is investigated for fissile fuel breeding. The investigated blanket is fueled with ThO 2 and cooled with natural lithium or (LiF) 2BeF 2 or Li 17Pb 83 or 4He coolant. MCNP4B Code is used for calculations of neutronic data per DT neutron. Calculations have show that values of TBR (tritium breeding ratio) being one of the main neutronic paremeters of fusion reactors are greater than 1.05 in all type of coolant, and the breeder hybrid reactor is self-sufficient in the tritium required for the DT fusion driver. Calculations show that natural lithium coolant blanket has the highest TBR (1.298) and M (fusion energy multiplication) (2.235), Li 17Pb 83 coolant blanket has the highest FFBR (fissile fuel breeding ratio) (0.3489) and NNM (net neutron multiplication) (1.6337). 4He coolant blanket has also the best Γ (peek-to-average fission power density ratio) (1.711). Values of neutron leakage out of the blanket in all type of coolants are quite low due to SiC reflector and B 4C shielding.