High uranium density dispersion fuel for the reduced enrichment of research and test reactors program

Abstract

This work describes the fabrication of a high uranium density fuel for the Reduced Enrichment of Research and Test Reactors Program. In an effort to decrease the use of high enriched uranium in research and test reactors around the world, new fuels with high uranium densities must be developed such that low enrichment fuel may be used in its place. Preliminary studies on uranium molybdenum alloys have shown promising results. A uranium molybdenum fuel phase dispersed in a zirconium matrix is proposed and examined in this thesis. Work described herein includes the successful fabrication of materials, preparation of samples, diffusion testing, fuel fabrication, and analysis of the resulting product. The fabrication results appear to be very good and all data collected indicates that this fuel type is fabricable and justifies irradiation testing.