Development and Verification of In-Core Fuel Management Code Package for Uranium Zirconium Hydride Power Reactor

This paper introduces the in-core fuel management code package for uranium zirconium hy-dride power reactor developed on the basis of the assembly parameter and in-core fuel management calcula-tion methods for LWR.The code package is verified by the experimental data of Xi’an pulsed reactor and the design parameters of international interrelated study.The verification shows that the calculated values of thecode package are in good agreement with the experimental data and the physical design values.This code package can be used for the in-core fuel management for the uranium zirconium hydride power reactor.