Development of LEU targets for {sup 99}Mo production and their chemical processing status 1993
Most of the world`s supply of {sup 99m}{Tc} for medical purposes is currently produced from {sup 99}Mo derived from the fastening of high enriched uranium (HEU). Substitution of low enriched uranium (LEU) silicide fuel for the HEU alloy and aluminide fuels used in current target designs will allow equivalent {sup 99}Mo yields with little change in target geometries. Substitution of uranium metal for uranium oxide films in other target designs will also allow the substitution of LEU for HEU. In 1993, DOE renewed funding that was terminated in 1990 for development of LEU targets for {sup 99}Mo production. During the past year, our efforts were to (1) renew contact with {sup 99}Mo producers, (2) define the means to test our process for recovering {sup 99}Mo from irradiated LEU-silicide targets, and (3) begin to test our process on spent LEU-silicide miniplates stored at ANL from past fuel development studies.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 10189026
- Report Number(s):
- ANL/CMT/CP-80812; CONF-9310185-2; ON: DE94001463; TRN: 94:000043
- Resource Relation:
- Conference: 16. international meeting on reduced enrichment for research and test reactors (RERTR),Ibaraki (Japan),3-7 Oct 1993; Other Information: PBD: [1993]
- Country of Publication:
- United States
- Language:
- English
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