Purex method and its uses

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United States of America Patent

PATENT NO 7731870
APP PUB NO 20080089819A1
SERIAL NO

11793891

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ATTORNEY / AGENT: (SPONSORED)

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Abstract

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The invention relates to a method constituting an improvement of the PUREX method, which makes it possible to obtain separation of uranium from the other actinides (Pu, Np, Th, . . . ) in a single purification cycle.This method successively comprises: a) co-extracting the uranium(VI), plutonium(IV) and other actinides(IV) or (VI) from an aqueous nitric solution by using solvent phase and scrubbing the latter; b) back-extracting the plutonium in oxidation state (III) from the solvent phase by using an aqueous nitric solution; c) back-extracting the uranium in oxidation state (VI) from the solvent phase by using an aqueous nitric solution; d) concentrating the aqueous nitric solution resulting from step c) with respect to uranium(VI); and it is characterized in that some of the uranium(VI)-concentrated aqueous solution obtained in step d) is used for back-extracting the actinide(IV) or actinides(IV) from the solvent phase during step b) or between steps b) and c).mixed oxide.

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Patent Owner(s)

  • COMPAGNIE GENERALE DES MATIERES NUCLEAIRES

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Inventor(s)

Inventor Name Address # of filed Patents Total Citations
Moulin, Jean-Paul Bois d'Arcy, FR 6 14

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