Process for the elution of ion exchange resins in uranium recove

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

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423 15, C01G 4300

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active

042809851

ABSTRACT:
Process for the recovery of uranium from a pregnant lixiviant employed in uranium leaching operations in which the uranium is concentrated by ion exchange resin. The ion exchange resin is eluted with an eluant containing 0.05-0.5 molar ammonium carbonate. The eluant also contains a base such as ammonium hydroxide in an amount sufficient to increase the pH to a value within the range of 9.0-11.0, thus increasing the carbonate/bicarbonate ratio. This enables the use of a relatively small quantity of ammonium carbonate to provide the desired carbonate ion concentration during the elution step.

REFERENCES:
patent: 2811412 (1957-10-01), Poirier
patent: 3265471 (1966-08-01), Pottier et al.
patent: 3778498 (1973-12-01), Yano et al.
patent: 4092399 (1978-05-01), Narayan et al.
patent: 4155982 (1979-05-01), Hunkin et al.

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