Removal of uranium from sulphate solutions containing molybdenum

Details Removal of uranium from sulphate solutions containing molybdenum Removal of uranium from sulphate solutions containing molybdenum

1980-10-01

1983-09-20

Kyle, Deborah L.

Chemistry of inorganic compounds

Treating mixture to obtain metal containing compound

Radioactive metal

423 11, 423 18, 423 20, 423 54, 423 55, C01G 4300, C01G 3900, C01G 3906

Patent

active

044055668

ABSTRACT:
A process for recovering uranium values from a sulphate solution containing dissolved uranium and molybdenum and with a pH not exceeding about 5.5, includes reacting the solution with ammonia at a pH in the range of from about 8 to about 10, without the solution existing for any significant time at a pH of around 7, with resultant precipitation of uranium values relatively uncontaminated by molybdenum. The uranium containing precipitate is separated from the remaining solution while maintaining the pH of the remaining solution within the same range.

REFERENCES:
Merritt, Robert C., "The Extractive Metallurgy of Uranium" 1971, pp. 211-215, 240-246, 413.
Lennemann, W. L. and F. E. McGinley, "Advances in Uranium ore Processing", Mining Congress Journal, 45(7), 1959, pp. 59-63.

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