High-density U-Mo fuel for research reactors

The effect of the content of the main alloying element (molybdenum in an amount of from 1.5 to 9 wt.%) and of additives of aluminum, silicon, and tin on the structure, phase composition, and properties of uranium alloys used as dispersion nuclear fuel in research reactors is studied. The heat treatment parameters ensuring a stable structure in the alloys are determined. Segregation of secondary phases in uranium alloys with molybdenum and molybdenum and tin additives is studied. Heat treatment parameters optimum for providing fine segregations of UAl2 and U5Sn4 particles in the matrix are determined. The results of the study are used to develop a composition for fabricating fuel grit and dispersion fuel for reactor tests.