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Reduced Enrichment for Research and Test Reactors
Nuclear Engineering Division at Argonne
U.S. Department of Energy

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Abstracts and Available Papers Presented at the
2002 International RERTR Meeting

LABORATORY RESEARCH ON BACK END ISSUES OF THE Mo-99 PRODUCTION

Falcon, M. : Russo, A. ; Schickendantz, F. ; Vaccaro, J.

Unidad de Actividad Materiales y Combustibles Nucleares - CAE – CNEA

ABSTRACT

The Argentinean National Atomic Energy Commission (CNEA) is now beginning to produce fission 99Mo (parent of the radionuclide 99mTc, widely used in medicine) by irradiation of targets containing 20% enriched uranium. The reduction from the previously employed enrichment of 90% implies an increase in the mass of uranium necessary to produce the same 99Mo activity. This, and the fact that the irradiated uranium has a very low burn-up, led to the decision of studying the feasibility of a method for the recovery (and later reuse) of the irradiated uranium, in order to reduce purchase and post-irradiation storage costs. This task is part of a project for to improving several aspects of the 99Mo production process (including the recovery and purification of other valuable fission products, such as 137Cs, 90Sr and 133Xe).


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Contact:
Ms. Analía V. Russo

Development Engineer
CNEA–CAE 
Avda. del Libertador 8250
C1429BNO BuenosAires, Argentina
Phone: (54 11) 4379 8221
Fax: (54 11) 4379 8293
E-mail: russo@cae.cnea.gov.ar

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Last modified on July 29, 2008 11:34 +0200