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.
