Heated ion exchange process for the recovery of uranium

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

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423 6, C01G 4300, C22B 6002

Patent

active

044303084

ABSTRACT:
The present invention relates to an improved method for the recovery of uranium values from a uranium-containing lixiviant by passing the lixiviant through a heated ion exchange resin to cause the resin to retain uranium values. The uranium values are subsequently recovered from the ion-exchange resin.

REFERENCES:
patent: 3542525 (1970-11-01), Pigford et al.
Osborn, G. H., Synthetic Ion-Exchangers, Chapman and Hall Ltd., London, 1961, p. 45-46.
Nachod, F. C., Ed., Ion Exchange Theory and Application, Academic Press, New York, NY, 1949, p. 201-204.
Kunin, Robert, Ion Exchange Resins, Robert E. Krieger Pblshg. Co., Huntington, NY, 1972, p. 52, 69-71.
Dow Chemical, T. D. Index 100.01, 1971.
Merritt, Robert C. The Extractive Metallurgy of Uranium Colorado School of Mines Research Institute, 1971, pp. 138-156, 163, 164.

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