Great effort worldwide has been invested in replacing highly enriched uranium (HEU) fuel with lowenriched uranium (LEU) fuel in nuclear plants, in the frame of safeguarding nuclear material and promoting the proliferation resistance [1]. A monolithic U-Mo fuel type is being developed at Idaho National Laboratory for this purpose. This study focuses on the characterization of fresh and irradiated monolithic U-Mo fuel specimens to understand the effect of irradiation on the initial texture. Understanding, controlling and monitoring texture evolution under irradiation is important to evaluate material properties, as texture can affect up them up to 20-50% (e.g. Young's modulus, Poisson's ratio, strength ductility, toughness, thermal expansion, and magnetic-electrical properties) [2].