Development and processing of LEU targets for {sup 99}Mo production-overview of the ANL program

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Most of the world`s supply of {sup 99m}Tc for medical purposes is currently produced from the decay of {sup 99}Mo derived from the fissioning of high-enriched uranium (HEU). Substitution of low-enriched uranium (LEU) silicide fuel for the HEU alloy and aluminide fuels used in most 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. During 1995, we have continued to study the modification of current targets and processes to allow the conversion from ... continued below

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10 p.

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Snelgrove, J.L.; Hofman, G.L. & Wiencek, T.C. September 1, 1995.

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Most of the world`s supply of {sup 99m}Tc for medical purposes is currently produced from the decay of {sup 99}Mo derived from the fissioning of high-enriched uranium (HEU). Substitution of low-enriched uranium (LEU) silicide fuel for the HEU alloy and aluminide fuels used in most 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. During 1995, we have continued to study the modification of current targets and processes to allow the conversion from HEU to LEU. A uranium-metal-foil target was fabricated at ANL and irradiated to prototypic burnup in the Indonesian RSG-GAS reactor. Postirradiation examination indicated that minor design modifications will be required to allow the irradiated foil to be removed for chemical processing. Means to dissolve and process LEU foil have been developed, and a mock LEU foil target was processed in Indonesia. We have also developed means to dissolve the LEU foil in alkaline peroxide, where it can be used to replace HEU targets that are currently dissolved in base before recovering and purifying the {sup 99}Mo. We have also continued work on the dissolution of U{sub 3}Si{sub 2} and have a firm foundation on dissolving these targets in alkaline peroxide. The technology-exchange agreement with Indonesia is well underway, and we hope to expand our international cooperations in 1996.

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10 p.

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INIS; OSTI as DE96002767

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  • 18. international meeting on reduced enrichment for research and test reactors, Paris (France), 18-21 Sep 1995

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  • Other: DE96002767
  • Report No.: ANL/TD/CP--88125
  • Report No.: CONF-9509253--2
  • Grant Number: W-31-109-ENG-38
  • Office of Scientific & Technical Information Report Number: 146775
  • Archival Resource Key: ark:/67531/metadc619155

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • September 1, 1995

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  • June 16, 2015, 7:43 a.m.

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  • Dec. 11, 2015, 4:56 p.m.

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Snelgrove, J.L.; Hofman, G.L. & Wiencek, T.C. Development and processing of LEU targets for {sup 99}Mo production-overview of the ANL program, article, September 1, 1995; Illinois. (digital.library.unt.edu/ark:/67531/metadc619155/: accessed November 19, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.