Published May 22, 1979 | Version v1
Patent Open

In situ carbonate leaching and recovery of uranium from ore deposits

Description

Uranium is leached from redox roll ore deposits by selective in-situ leaching with a solution of pH 7.4 to 9 (preferably 7.5 to 8.5) containing from about 0.5 to 5g/l of NH4HCO3 and from about 0.1 to 3g/l of peroxide (preferably aqueous H2O2), and sufficient NH3 to maintain the desired pH. The leach solution is then withdrawn from the ore deposit and contacted with a strong base anion exchange material to strip the uranium from the leach solution. The uranium is eluted from the anion exchange material by an aqueous eluant, and the uranium is recovered from the eluate by first acidifying it and then treating it with ammonia to produce a precipitate of relatively pure ammonium diuranate. The content of the three components in the stripped leach solution is adjusted, and then the leach solution is recirculated through the ore deposit. After the uranium ore is removed to the extent economically practicable, the leach solution is replaced with an aqueous reducing solution which when passed into the ore deposit precipitates and renders insoluble any uranium and elements such as vanadium, molybdenum, and selenium. This process produces above ground a very low volume of impurities and waste solutions requiring disposal and does not cause material contamination of the underground deposit or any aquifer associated with the deposit

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Additional titles

Augmented title (English)
Patent

Publishing Information

Imprint Pagination
18 p.
IPC:
Int. Cl.C01G43/00.
IPC
Int. Cl.C01G43/00.
Patent number
US patent document 4,155,982/A/