Silicon Carbide Ceramic as Fast Neutron Detector of Fission and Fusion Reactions in Fusion-Fission Hybrid Reactors

Fast neutron (flow) response measurement with silicon carbide (SiC) is investigated in a typical fusion-fission hybrid reactor, using the most current Monte Carlo transport code (MCNPX2.7.0). Silicon carbide is used as the clad of the fissile fuel assemblies. The elastic scattering of Si-28(n,p)(28)A1, Si-28(n,alpha)Mg-25, C-12(n,alpha)Be-9, C-12(n,n ')3 alpha, Si-28(n, n ')Si-28, and C-12(n,n ')C-12 was calculated, and the results were validated using ENDF reaction cross sections. The results showed that the SiC layer of fuel assembly can be used as a detector for proton, alpha, and elastic scattering in fuel assemblies.

Automated summary

The study demonstrates that silicon carbide can be used as the cladding of fissile fuel assemblies in a fusion-fission hybrid reactor for fast neutron response measurements. The SiC layer can serve as a detector for proton, alpha, and elastic scattering in fuel assemblies.