Development of uranium metal targets for {sup 99}Mo production

Conference · Fri Oct 01 00:00:00 EDT 1993

OSTI ID:10189292

Wiencek, T C; Hofman, G L

A substantial amount of high enriched uranium (HEU) is used for the production of medical-grade {sup 99}Mo. Promising methods of producing irradiation targets are being developed and may lead to the reduction or elimination of this HEU use. To substitute low enriched uranium (LEU) for HEU in the production of {sup 99}Mo, the target material may be changed to uranium metal foil. Methods of fabrication are being developed to simplify assembly and disassembly of the targets. Removal of the uranium foil after irradiation without dissolution of the cladding is a primary goal in order to reduce the amount of liquid radioactive waste material produced in the process. Proof-of-concept targets have been fabricated. Destructive testing indicates that acceptable contact between the uranium foil and the cladding can be achieved. Thermal annealing tests, which simulate the cladding/uranium diffusion conditions during irradiation, are underway. Plans are being made to irradiate test targets.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10189292
• Report Number(s): ANL/ET/CP-80968; CONF-9310185-1; ON: DE94001429; TRN: 94:000042
• Resource Relation: Conference: 16. international meeting on reduced enrichment for research and test reactors (RERTR),Ibaraki (Japan),3-7 Oct 1993; Other Information: PBD: Oct 1993
• Country of Publication: United States
• Language: English

Related Subjects

37 INORGANIC
ORGANIC
PHYSICAL AND ANALYTICAL CHEMISTRY
07 ISOTOPES AND RADIATION SOURCES
42 ENGINEERING
MOLYBDENUM 99
ISOTOPE PRODUCTION
DESIGN
URANIUM 235 TARGET
ENRICHED URANIUM
TESTING
NEUTRON REACTIONS
URANIUM OXIDES
400202
070100
420500
ISOTOPE EFFECTS, ISOTOPE EXCHANGE, AND ISOTOPE SEPARATION
PHYSICAL ISOTOPE SEPARATION
MATERIALS TESTING