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classificationIPCInventive http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/C22B60-02
filingDate 1980-12-24-04:00^^<http://www.w3.org/2001/XMLSchema#date>
grantDate 1984-10-09-04:00^^<http://www.w3.org/2001/XMLSchema#date>
inventor http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_0df88f3b67426eb7c7aa558b219841e9
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publicationDate 1984-10-09-04:00^^<http://www.w3.org/2001/XMLSchema#date>
publicationNumber US-4476099-A
titleOfInvention Method of recovering uranium
abstract Uranium is recovered from a carbonate leach solution containing a dissolved uranium salt and a monovalent ion. The pH of the leach solution is adjusted to about 5 to about 7.5, and preferably to about 6 to about 7. Phosphate ion is then added to typical in-situ leach solutions in an amount from about 10 to about 30 mole % in excess of the amount needed to stoichiometrically react with the uranium in said solution. This results in the precipitation of a compound made up of the monovalent ion, uranium, and the phosphate ion, which is insoluble in the solution. The precipitate is then separated from the solution preferably by means of a centrifuge or a vortex clarifier. It can then be dissolved in acid, and the uranium extracted into an organic solvent such as DEHPA-TOPA in kerosene.
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