Published October 1996 | Version v1
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Irradiation tests of 99Mo isotope production targets employing uranium metal foils

  • 1. Argonne National Laboratory, Argonne, Illinois 60439-4841 (United States)
  • 2. Badan Tenaga Atom National (Indonesia)

Description

Most of the world's supply of 99mTc for medical purposes is currently produced from the decay of 99Mo derived from the fissioning of high-enriched uranium (HEU). Substitution of low-enriched uranium (LEU) metal foils for the HEU UO2 used in current target designs will allow equivalent 99Mo yields with little change in target geometries. Substitution of uranium metal for uranium alloy and aluminide in other target designs will also allow the conversion of HEU to LEU. Several uranium-metal-foil targets have been fabricated at ANL and irradiated to prototypic burnup in the Indonesian RSG-GAS reactor. Postirradiation examination of the initial test indicated that design modifications were required to allow the irradiated foil to be removed for chemical processing. The latest test has shown good irradiation behavior, satisfactory dismantling and foil removal when the U-foil is separated from its containment by metallic, fission-recoil absorbing barriers. (author)

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Part of:
Abstracts and papers of the 1996 International RERTR Meeting

Additional details

Publishing Information

Imprint Title
Abstracts and papers of the 1996 International RERTR Meeting
Imprint Pagination
233 p.
Journal Page Range
[14 p.]
Report number
INIS-XA-C--008

Conference

Title
19. international meeting on Reduced Enrichment for Research and Test Reactors (RERTR)
Dates
6-10 Oct 1996
Place
Seoul (Korea, Republic of)

Optional Information

Notes
1 ref., 7 figs, 1 tab