Purex method and its uses

Details Purex method and its uses Purex method and its uses

2005-12-27

2010-06-08

Mayes, Melvin C (Department: 1793)

Compositions

Radioactive compositions

Nuclear reactor fuel

C423S008000

Reexamination Certificate

active

07731870

ABSTRACT:
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).Uses: reprocessing of spent nuclear fuels based on UO2, (U,Pu)O2or (U,Th)O2mixed oxide.

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French Seach Report, FA 658629; FR 0414034, 2 pgs., (Mar. 11, 2005).
Germain, M. et al., “Extraction En Milieu Nitrique Du Thorium, Due Neptunium, Du Plutonium, Par Les Solutions De Phosphate De Tributyle Chargee En Uranium”, Article of Germain et al., J. Inorg. Chem., vol. 32, pp. 245-253, (1970).

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