Extending OFFBEAT capabilities to modelling uranium hydride fuel for the AGR-like FHR reactor

This study evaluates the feasibility and performance of uranium-zirconium hydride (U-ZrH x ) fuel in a graphite-free AGR-like Fluoride Salt-Cooled High-Temperature Reactor (AGR-like FHR). This reactor concept combines the pin-type geometry of Advanced Gas-cooled Reactors (AGR) with the low-pressure, high-efficiency characteristics of molten salt coolants and Hastelloy-N as cladding, aiming to improve thermal efficiency and passive safety. While conventional UO 2 fuel has been previously consider