“…Furthermore, a thorough investigation of zirconium hydride was performed for application as a moderator in a maritime carbon-dioxide-cooled reactor using a closed-cycle gas turbine [Mueller 1968a]. However, perhaps most importantly, a dispersion of enriched uranium in a matrix of zirconium hydride has been developed and used as the fuel for the General Atomics TRIGA research reactor (a mature and popular product worldwide) for over 40 years [Simnad 1981]. Therefore, considerable information on the thermodynamic, transport, mechanical, and irradiation properties of zirconium hydride is available in the literature.…”