Alternative processes of comminution and colamination of uranium molybdenum alloys

• Published in: Progress in nuclear energy (New series) 2014-08, Vol.75, p.92-104
• Main Author: Pasqualini, Enrique E.
• Format: Article
• Language: English
• Subjects: Aluminum base alloys; Cladding; Colamination; Comminution; Fuels; Hydride; Molybdenum; Molybdenum base alloys; Nuclear power generation; Nuclear reactor components; Nuclear reactors; Uranium; Zircaloy-4; Zirconium base alloys
• ISSN: 0149-1970
• DOI: 10.1016/j.pnucene.2014.04.002

The high density uranium molybdenum (UMo) alloy is being qualified as a nuclear fuel for the conversion of high enriched uranium (HEU) to low enriched uranium (LEU) fuels in radioisotopes production and testing reactors. Misbehavior of the dispersed and monolithic UMo fuel in contact with the aluminum matrix or aluminum cladding, as well as differences in their thermo-mechanical properties have triggered several fuel development alternatives. Long term complete studies and experiments are presented that can contribute to incorporate new technologies in the processing of UMo fuels. The discovery of the uranium molybdenum hydride opened the way to develop the hydriding–milling–dehydriding process (HMD) to comminute the ductile UMo alloy for a scalable powder production. In the case of UMo monolithic fuel, a hot rolling colamination process with Zircaloy-4 (Zry-4) cladding has been developed and prototypes were irradiated with excellent results. •Novel gamma phase uranium molybdenum (U–Mo) hydride was obtained and characterized.•U–Mo powder was produced by hydriding, milling and dehydriding the alloy (HMD process).•Hot rolling colamination of monolithic U–Mo with Zircaloy (Zr4) cladding was successful.•U–Mo/Zr4 monolithic mini-plates were irradiated and PIE performed with excellent results.