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publicationDate 2010-12-02-04:00^^<http://www.w3.org/2001/XMLSchema#date>
publicationNumber US-2010301287-A1
titleOfInvention Process for Treating Spent Nuclear Fuel
abstract Process for treating spent nuclear fuel (SNF) to make mixed metal oxides of UO 3 and PuO 2 to prevent nuclear proliferation. The process comprises the steps of (1) dissolving spent nuclear fuel in an acidic solution in the presence of an agent that reduces Pu +6 to Pu +4 and an agent that oxidizes Pu +3 to Pu +4 ; (2) extracting U +6 and Pu +4 from acidic solution with an organic solvent comprising a ligand that binds U +6 and Pu +4 and which is soluble in the organic solvent; (3) jointly extracting U +6 and Pu +4 from the organic solvent with an acidic aqueous solution; and (4) precipitating a mixture of U +6 and Pu +4 by adding a carboxylic acid to the acidic aqueous solution. The U +6 and Pu +4 precipitate is then be calcined to form a mixed metal oxide of UO 3 and PuO 2 . Additional steps can result in the formation of a mixed metal oxide of UO 3 , PuO 2 and NpO 2 as well as the removal and isolation of technecium from the SNF.
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