Research reactor fuel technology continues developing high and very high density fuels, mainly to enable the conversion of more reactors from HEU to LEU fuels. These programs are mainly engaged with UMo dispersion fuels with densities from 6 to 8 gU/cm3 (high density fuel) and UMo monolithic fuel with density as high as 16 gU/cm3 (very high density fuel). The availability of these new high density fuels may allow other studies, such us: Economic and performance benefits for reactors already in operation, and the possibility to design new fuel elements. The utilization of U-Mo monolithic fuels with a Uranium density up to 16 g/cm3, will allow the conversion of High Performance Research Reactors, but it is not a proper alternative for most of the Low or Medium power Research Reactors, because this fuel will work in an optimal configuration using a more compact core than U3Si2 fuel, with a higher power density and will require a more demanding cooling system and engineering measures to improve the safety of the reactor. The reduction of the fuel volume can be used to improve the safety characteristic of the core, adding hydrogen to the fuel design; this concept can be used together with another characteristic of the monolithic fuel that is the necessity of a zirconium or silicon diffusion barrier between the Aluminum cladding and the UMo fuel, or a Zircaloy cladding instead of Aluminum cladding. This paper conceptually analyzes the possibility to design a new Fuel Element using Zirconium Hydride together with UMo fuel meat. Conceptual neutronic and thermal-hydraulic analyses were done to improve the neutronic behavior of a fuel design and to enhance significantly the isothermal and power feedback coefficients, making a safer option than the U3Si2 fuel type.