Processing of LEU targets for {sup 99}Mo production: Dissolution of U{sub 3}Si{sub 2} targets by alkaline hydrogen peroxide

Conference · Fri Sep 01 00:00:00 EDT 1995

OSTI ID:188657

Buchholz, B A; Vandegrift, G F

Low-enriched uranium silicide targets designed to recover fission product {sup 99}Mo were dissolved in alkaline hydrogen peroxide (H{sub 2}O{sub 2} plus NaOH) at about 90C. Sintering of matrix aluminum powder during irradiation and heat treatment retarded aluminum dissolution and prevented silicide particle dispersion. Gas evolved during dissolution is suspected to adhere to particles and block hydroxide ion contact with aluminum. Reduction of base concentrations from 5M to O.lM NaOH yielded similar silicide dissolution and peroxide destruction rates, simplifying later processing. Future work in particle dispersion enhancement, {sup 99}Mo separation, and waste disposal is also discussed.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 188657
• Report Number(s): ANL/CMT/CP-87721; CONF-9509253-8; ON: DE96004813; TRN: 96:006214
• Resource Relation: Conference: 18. international meeting on reduced enrichment for research and test reactors, Paris (France), 18-21 Sep 1995; Other Information: PBD: Sep 1995
• Country of Publication: United States
• Language: English

Related Subjects

40 CHEMISTRY
22 NUCLEAR REACTOR TECHNOLOGY
MOLYBDENUM 99
ISOTOPE PRODUCTION
URANIUM SILICIDES
DISSOLUTION
URANIUM 235 TARGET
PROCESSING
SLIGHTLY ENRICHED URANIUM