Production of Mo-99 using low-enriched uranium silicide

Technical Report · Thu Sep 01 04:00:00 EDT 1994

DOI:https://doi.org/10.2172/10184098· OSTI ID:10184098

Hutter, J. C.; Srinivasan, B.; Vicek, M.; Vandegrift, G. F.

Over the last several years, uranium silicide fuels have been under development as low-enriched uranium (LEU) targets for Mo-99. The use of LEU silicide is aimed at replacing the UAl{sub x} alloy in the highly-enriched uranium dissolution process. A process to recover Mo-99 from low-enriched uranium silicide is being developed at Argonne National Laboratory. The uranium silicide is dissolved in alkaline hydrogen peroxide. Experiments performed to determine the optimum dissolution procedure are discussed, and the results of dissolving a portion of a high-burnup (>40%) U{sub 3}Si{sub 2} miniplate are presented. Future work related to Mo-99 separation and waste disposal are also discussed.

• Research Organization: Argonne National Lab., IL (United States). Chemical Technology Div.
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10184098
• Report Number(s): ANL/CMT/CP--84245; CONF-9409107--1; ON: DE94019282
• Country of Publication: United States
• Language: English

Related Subjects

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY
400703
CHEMICAL REACTION KINETICS
DISSOLUTION
EXPERIMENTAL DATA
HIGHLY ENRICHED URANIUM
ISOTOPE PRODUCTION
ISOTOPE SEPARATION
MATERIAL SUBSTITUTION
MOLYBDENUM
MOLYBDENUM 99
PEROXIDES
RADIOACTIVE WASTE MANAGEMENT
RADIOISOTOPE PRODUCTION
SLIGHTLY ENRICHED URANIUM
URANIUM SILICIDES