Published July 1993 | Version v1
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HEU and LEU MTR fuel elements as target materials for the production of fission molybdenum

  • 1. Nuclear Research Center Karlsruhe, Cyclotrone Lab., Karlsruhe (Germany)

Description

The processing of irradiated MTR-fuels for the production of fission nuclides for nuclear medicine presents a significantly increasing task in the field of chemical separation technology of high activity levels. By far the most required product is MO-99, the mother nuclide of Tc-99m which is used in over 90% of the organ function tests in nuclear medicine. Because of the short half life of Mo-99 (66 h) the separation has to be carried out from shortly cooled neutron irradiated U-targets. The needed product purity, the extremely high radiation level, the presence of fission gases like xenon-133 and of volatile toxic isotopes such as iodine-131 and its compounds in kCi-scale require a sophisticated process technology

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Part of:
Reduced enrichment for research and test reactors: Proceedings

Additional details

Publishing Information

Imprint Title
Reduced enrichment for research and test reactors: Proceedings
Imprint Pagination
376 p.
Journal Page Range
p. 313-333.
Report number
ANL--RERTR/TM-19

Conference

Title
1992 international meeting on reduced enrichment for research and test reactors.
Dates
27 Sep - 1 Oct 1992.
Place
Roskilde (Denmark).

Optional Information

Secondary number(s)
CONF-9209266--.