Purex method and its uses
View Patent ↗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 UO 2 , (U,Pu)O 2 or (U,Th)O 2 mixed oxide.
1. A method for reprocessing a spent nuclear fuel, which successively comprises:
a) separating uranium, plutonium and other actinides from fission products present in an aqueous nitric solution obtained by dissolving the fuel in nitric acid, said separation comprising co-extracting uranium(VI), plutonium(IV) and other actinides(IV) or (VI) from said aqueous solution by using a water-immiscible solvent phase comprising at least one extractant in an organic diluent, and then scrubbing the solvent phase with an aqueous nitric solution;
b) back-extracting plutonium in the oxidation state (III) from the solvent phase resulting from step a) by using an aqueous nitric solution which contains a reducing agent capable of reducing plutonium(IV) into plutonium(III);
c) back-extracting uranium(VI) from the solvent phase resulting from step b) by using an aqueous nitric solution;
d) concentrating the aqueous nitric solution resulting from step c) with respect to uranium(VI);
and in which a part of the uranium(VI)-concentrated aqueous solution resulting from step d) is used for further back-extracting during step b) at least one actinide(IV) selected from neptunium(IV) and thorium(IV) from the solvent phase resulting from step a).
2. The method of claim 1 , in which step b) comprises:
i) back-extracting the majority of the plutonium(III) from the solvent phase in a first extractor, and
ii) completing the back-extraction of plutonium(III) from the solvent phase in a second extractor,
wherein the uranium(VI)-concentrated aqueous solution part is used for back-extracting the actinide(IV) during step ii).
3. The method of claim 2 , in which the uranium(VI)-concentrated aqueous solution part is introduced into the second extractor and is supplemented with nitric acid, the reducing agent capable of reducing plutonium(IV) into plutonium(III) and an anti-nitrous agent.
4. The method of claim 1 , in which the back-extraction of the actinide(IV) from the solvent phase is obtained by mixing said solvent phase and said uranium(VI)-concentrated solution part, and then by separating this mixture into a solvent phase and an aqueous phase containing the back-extracted actinide(IV).
5. The method of claim 4 , further comprising the step of subjecting the aqueous phase containing the back-extracted actinide(IV) to one or more scrubbings with a water-immiscible solvent phase comprising an extractant of uranium(VI) in an organic diluent.
6. The method of claim 5 , in which the extractant and the organic diluent of said solvent phase are identical to those of the solvent phase used in step a).
7. The method of claim 1 , in which the solvent phase used during step a) comprises tri-n-butyl phosphate as an extractant.
8. The method of claim 1 , in which the solvent phase used during step a) comprises hydrogenated tetrapropylene as an organic diluent.
9. The method of claim 1 , in which the reducing agent capable of reducing plutonium(IV) into plutonium(III) is uranous nitrate.
10. The method of claim 3 , in which the uranium(VI)-concentrated aqueous solution part is furthermore supplemented with one or more agents complexing actinides(IV).
11. The method of claim 1 , in which the actinide(IV) to be back-extracted during step b) is neptunium.
12. The method of claim 1 , in which the spent nuclear fuel is an uranium oxide nuclear fuel, an uranium-plutonium mixed oxide nuclear fuel or an uranium-thorium mixed oxide nuclear fuel.
13. A method for reprocessing a spent nuclear fuel, which successively comprises:
a) separating uranium, plutonium and other actinides from fission products present in an aqueous nitric solution obtained by dissolving the fuel in nitric acid, said separation comprising co-extracting uranium(VI), plutonium(IV) and other actinides(IV) or (VI) from said aqueous solution by using a water-immiscible solvent phase comprising at least one extractant in an organic diluent, and then scrubbing the solvent phase with an aqueous nitric solution;
b) back-extracting plutonium in the oxidation state (III) from the solvent phase resulting from step a) by using an aqueous nitric solution which contains a reducing agent capable of reducing plutonium(IV) into plutonium(III);
c) back-extracting uranium(VI) from the solvent phase resulting from step b) by using an aqueous nitric solution;
d) concentrating the aqueous nitric solution resulting from step c) with respect to uranium(VI);
and in which a part of the uranium(VI)-concentrated aqueous solution resulting from step d) is used for back-extracting between steps b) and c) at least one actinide(IV) selected from neptunium(IV), thorium(IV) and plutonium(IV) from the solvent phase resulting from step b).
14. The method of claim 13 , in which the uranium(VI)-concentrated aqueous solution part is used for back-extracting the actinides(IV) in an extractor specifically allocated to this back-extraction.
15. The method of claim 14 , in which step b) comprises:
i) back-extracting the majority of the plutonium(III) from the solvent phase in a first extractor, and
ii) completing the back-extraction of plutonium(III) from the solvent phase in a second extractor,
and in which the uranium(VI)-concentrated aqueous solution part is introduced into a third extractor which is supplied with solvent phase by the second extractor, and is supplemented with nitric acid.
16. The method of claim 13 , in which the back-extraction of the actinide(IV) from the solvent phase is obtained by mixing said solvent phase and said uranium(VI)-concentrated solution part, and then by separating this mixture into a solvent phase and an aqueous phase containing the back-extracted actinide(IV).
17. The method of claim 16 , which furthermore comprises a step of subjecting the aqueous phase containing the back-extracted actinide(IV) to one or more scrubbings with a water-immiscible solvent phase comprising an extractant of uranium(VI) in an organic diluent.
18. The method of claim 17 , in which the extractant and the organic diluent of said solvent phase are identical to those of the solvent phase used in step a).
19. The method of claim 13 , in which the solvent phase used during step a) comprises tri-n-butyl phosphate as an extractant.
20. The method of claim 13 , in which the solvent phase used during step a) comprises hydrogenated tetrapropylene as an organic diluent.
21. The method of claim 13 , in which the reducing agent capable of reducing plutonium(IV) into plutonium(III) is uranous nitrate.
22. The method of claim 15 , in which the uranium(VI)-concentrated aqueous solution part is furthermore supplemented with one or more agents complexing actinides(IV).
23. The method of claim 13 , in which the actinide(IV) to be back-extracted between steps b) and c) is neptunium(IV).
24. The method of claim 13 , in which the spent nuclear fuel is an uranium oxide nuclear fuel, an uranium-plutonium mixed oxide nuclear fuel or an uranium-thorium mixed oxide nuclear fuel.