Ion exchange resins of high loading capacity, high chloride tole

Chemistry of inorganic compounds – Treating mixture to obtain metal containing compound – Radioactive metal

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75101BE, 423 17, C22B 6002

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active

043128386

ABSTRACT:
Ion exchange process for the recovery of uranium from a pregnant carbonate lixiviant employed in uranium leaching operations in which the lixiviant is passed over a precipitation inducing anionic ion exchange resin under conditions to load the resin predominantly with non-exchangeable uranium. Non-exchangeable uranium is then recovered from the resin by eluting the resin with an aqueous acid solution having a pH no greater than 2. The process is useful in those applications in which the lixiviant contains chloride ions which inhibit the adsorption of uranyl ions.

REFERENCES:
patent: 2780514 (1957-02-01), Lutz
patent: 2841468 (1958-07-01), Wilson
Merritt, R. C., The Extractive Metallurgy of Uranium, Colo. School of Mines Research Inst., 1971, pp. 138-156.

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