Process for stripping uranium

Details Process for stripping uranium Process for stripping uranium

1984-02-28

1986-09-09

Miller, Edward A.

Chemistry of inorganic compounds

Treating mixture to obtain metal containing compound

Radioactive metal

C01G 4301, B01D 1104

Patent

active

046108521

ABSTRACT:
Uranium is stably stripped from an organic solvent containing a uranium-laden, amine-based extracting agent into an aqueous ammonium sulfate solution with a very high stripping efficiency in an emulsion-formable high pH range by mixing the organic solvent, the aqueous ammonium sulfate solution and an alkali as a pH-controlling agent, thereby forming a mixture having a pH of 4.5 to 6.0 and a temperature of 15.degree. to 50.degree. C., preferably 25.degree. to 40.degree. C., and subjecting the resulting mixture to an action of centrifugal force of 850 G or higher, thereby separating it into an organic solvent freed from the uranium and an aqueous ammonium sulfate solution containing the uranium.

REFERENCES:
Merritt, Robert C., The Extractive Metallurgy of Uranium, Colorado School of Mines Research Institute, 1971, pp. 196-199.
Perry, R. H. and C. H. Chilton, Chemical Engineers' Handbook, McGraw-Hill, NY, NY, 1973, p. 21-12.
Bennett et al., Practical Emulsions, vol. 1, Materials and Equipment Chemical Publishing Co. Inc. NY, 3rd. Ed., 1968, pp. 31-33.
Clayton, W., The Theory of Emulsions and Their Technical Treatment, P. Blackiston's Son & Co., Phila. Penna., 2nd Ed, 1928, pp. 202-203.

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