On the Neutronic Performance of Hylife-Ii Reactor Fuelled With Carbide Fuels

Abstract

In this study, neutronic analysis of the HYLIFE-II reactor was investigated by inserting fuel rods containing UC or mixed ThC-UC into reflector zone partially. Four different coolants, namely, flibe, helium, natural lithium, and light water were considered in the fissile fuel breeding zone for comparison. Neutron transport calculations per incident (D,T) fusion neutron were performed by using the code Scale 4.3 under resonance-effect and resonance-free conditions. Numerical results pointed out that replacing the reflector zone by fissile fuel breeding zone even with a thickness of 14 cm improved the neutronic performance remarkably with respect to energy amplification and fissile fuel breeding.