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Reduced Enrichment for Research and Test Reactors
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Abstracts and Available Papers Presented at the
1998 International RERTR Meeting

FULL-SCALE DEMONSTRATION OF THE CINTICHEM PROCESS FOR
THE PRODUCTION OF Mo-99 USING A LOW- ENRICHED TARGET

A. Mutalib, B. Purwadi, Adang H. G., Hotman L., Moeridoen, Kadarisman,
A. Sukmana, Sriyono, A. Suripto, H. Nasution, D. L. Amin,
A. Basiran, A. Gogo, D. Sunaryadi, and T. Taryo


Indonesian National Atomic Energy Agency
Serpong, Indonesia

G. F. Vandegrift, G. Hofman, C. Conner, J. Sedlet, D. Walker, R. A. Leonard,
E. L. Wood, T. C. Wiencek, and J. L. Snelgrove


Argonne National Laboratory
Argonne, Illinois, U.S.A.

Abstract

The irradiation, disassembly, and processing of two full-scale low-enriched uranium (LEU) targets were recently demonstrated by personnel in the BATAN PUSPIPTEK Facilities (Serpong, Indonesia). Targets were fabricated at Argonne National Laboratory (Argonne, IL, U.S.A.) and shipped to PUSPIPTEK. The processing was done by nearly the same procedure used for the production of 99Mo from high-enriched uranium (HEU) targets. The BATAN Radioisotope Production Centre produces 99Mo using the Cintichem process by first dissolving the uranium in an acid cocktail; three proprietary separation steps recover the 99Mo and purify it from other components of the irradiated uranium. Processing of LEU-metal targets is nearly identical to that used for HEU-oxide targets except (1) a separate dissolver is required and (2) the dissolution cocktail is nitric acid alone rather than a nitric/sulfuric acid mixture. The demonstrations went smoothly except for problems with sampling and gamma analysis to assess product purity. Foils could be removed from targets fabricated from zirconium and/or 304 stainless steel, and processing produced an equivalent yield of 99Mo/235U to that of the HEU target.


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Last modified on July 29, 2008 11:33 +0200