Target and method for the production of fission product molybden

Induced nuclear reactions: processes – systems – and elements – Nuclear transmutation – Irradiation capsule – holder – or support

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204 15, 252645, 376186, G21G 102, C25C 334, C25D 354, C25D 546

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active

048391336

ABSTRACT:
A target for the reduction of fission product Mo-99 is prepared from uranium of low U-235 enrichment by coating a structural support member with a preparatory coating of a substantially oxide-free substrate metal. Uranium metal is electrodeposited from a molten halide electrolytic bath onto a substrate metal. The electrodeposition is performed at a predetermined direct current rate or by using pulsed plating techniques which permit relaxation of accumulated uranium ion concentrations within the melt. Layers of as much as to 600 mg/cm.sup.2 of uranium can be prepared to provide a sufficient density to produce acceptable concentrations of fission product Mo-99.

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patent: 4596647 (1986-06-01), Miller et al.
patent: 4701308 (1987-10-01), Koehly et al.
Inman et al., "The Electrocrystallization of Chromium from Molten Salt LiKCl at 450.degree. C.", Proceedings of the Fourth Intern'l Symp. on Molten Salts, 163rd Electrochemical Society Meeting, May 1983, pp. 544-558.
Vandegrift et al., "Preliminary Investigations for the Technological Assessment of .sup.99 Mo Production from LEU Targets", presented at the 1986 International Meeting on Reduced Enrichment for Research and Test Reactors, Nov. 3-6, 1986.
Vandegrift et al., "Continuing Investigations For Technological Assessment of .sup.99 Mo Production from LEU Targets", Presented at the 1987 International Meeting of Reduced Enrichment for Research in in Test Reactors, Sep. 28-Oct. 2, 1987.

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