IP Library Granted Patent US 11,578,031
Granted Patent B2
US 11,578,031 · App. 16/479,830 · Granted Feb 14, 2023

Dissymmetric N,N-dialkylamides used particularly for separating uranium(VI) from plutonium(IV), synthesis thereof and uses of same

Inventors: Gaëlle Milanole (Orange, FR); Emilie Russello (Bagnol sur Ceze, FR); Cécile Marie (Avignon, FR); Manuel Miguirditchian (Avignon, FR); Christian Sorel (Villeneuve les Avignon, FR)
Assignees: COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÊNERGIES ALTERNATIVES; ORANO RECYCLAGE; ELECTRICITE DE FRANCE
C07C233/05C22B3/32C22B60/026C22B60/04G21C19/46C07C231/02Y02E30/30Y02P10/20
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Quick Facts
Patent No.
US 11,578,031
App. No.
16/479,830
Granted
Feb 14, 2023
Kind
B2
Abstract

A dissymmetric RN,N-dialkylamides of formula (I) in which: R 1 represents a linear C 1 to C 4 alkyl, R 2 represents a linear C 1 to C 10 alkyl, and R 3 represents a linear or branched C 6 to C 15 alkyl, where R 3 is different from a n-octyl, n-decyl, n-dodecyl, 2-ethylhexyl and 2-ethyloctyl group when R 1 represents a n-butyl group and R 2 represents an ethyl group. A method for synthesising the N,N-dialkylamides, and uses of same for extracting uranium and/or plutonium from an aqueous acid solution or for fully or partially separating the uranium from the plutonium contained in an aqueous acid solution and a solution resulting from the dissolution of spent nuclear fuel in nitric acid. A method for treating an aqueous solution resulting from the dissolution of spent nuclear fuel in nitric acid, which allows the uranium and the plutonium contained in the solution to be extracted, separated and decontaminated in a single cycle.

Claims (50)

1. A method for separating totally or partially uranium(VI) from plutonium(IV) from an acid aqueous solution A1, comprising:

a) a co-extraction of uranium and plutonium from the aqueous solution A1, the co-extraction comprising at least one contacting of the aqueous solution A1 with an organic solution S1 comprising an N,N-dialkylamide or a mixture of N,N-dialkylamides of formula (I):

wherein:

R 1 is a linear alkyl group having 1 to 4 carbon atoms;

R 2 is a linear alkyl group having 1 to 10 carbon atoms;

R 3 is a linear or branched alkyl group having 6 to 15 carbon atoms;

provided that R 3 differs from an n-octyl, n-decyl, n-dodecyl, 2-ethylhexyl and 2-ethyloctyl group when R 1 is an n-butyl and R 2 is an ethyl group; in an organic diluent, followed by a separation of the aqueous solution A1 from the organic solution S1;

b) a stripping of plutonium, in oxidation state +IV, and of a fraction of uranium from the organic solution S1 resulting from a), the stripping comprising at least one contacting of the organic solution S1 with an aqueous solution A2 comprising from 0.1 mol/L to 0.5 mol/L of nitric acid, followed by a separation of the organic solution S1 from the aqueous solution A2; and

c) an extraction of all or part of the uranium fraction contained in the aqueous solution A2 resulting from b), the extraction comprising at least one contacting of the aqueous solution A2 with an organic solution S2 identical to the organic solution S1 of a), followed by a separation of the aqueous solution A2 from the organic solution S2;

whereby there are obtained an aqueous solution comprising plutonium without uranium, or a mixture of plutonium and uranium, and an organic solution comprising uranium without plutonium.

2. The method of claim 1 , wherein the organic solution S1 of a) comprises from 1 mol/L to 2 mol/L of the N,N-dialkylamide or mixture of N,N-dialkylamides.

3. The method of claim 1 , wherein the acid aqueous solution A1 is an aqueous solution resulting from a dissolution of a spent nuclear fuel in nitric acid.

4. The method of claim 1 , wherein R 1 is a methyl, ethyl or n-propyl group.

5. The method of claim 1 , wherein R 2 is an n-propyl, n-butyl, n-pentyl, n-hexyl or n-heptyl group.

6. The method of claim 1 , wherein R 3 is an n-hexyl, n-heptyl, n-octyl, 2-ethylhexyl, n-nonyl, n-decyl or 2-ethyloctyl group.

7. The method of claim 1 , wherein:

R 1 is a methyl group, R 2 is an n-butyl group and R 3 is an n-nonyl group; or

R 1 and R 2 are each an n-propyl group and R 3 is an n-octyl group; or

R 1 is an n-propyl group, R 2 is an n-pentyl group and R 3 is an n-hexyl group.

8. A single-cycle method for processing an aqueous solution A1 resulting from a dissolution of a spent nuclear fuel in nitric acid, the aqueous solution A1 comprising uranium, plutonium, americium, curium and fission products including technetium, the cycle comprising:

a) a co-extraction of uranium and plutonium from the aqueous solution A1, the co-extraction comprising at least one contacting, in an extractor, of the aqueous solution A1 with an organic solution S1 comprising an N,N-dialkylamide or a mixture of N,N-dialkylamides of formula (I):

wherein:

R 1 is a linear alkyl group having 1 to 4 carbon atoms;

R 2 is a linear alkyl group having 1 to 10 carbon atoms;

R 3 is a linear or branched alkyl group having 6 to 15 carbon atoms;

provided that R 3 differs from an n-octyl, n-decyl, n-dodecyl, 2-ethylhexyl and 2-ethyloctyl group when R 1 is an n-butyl and R 2 is an ethyl group; in an organic diluent, followed by a separation of the aqueous solution A1 from the organic solution S1;

b) a decontamination of the organic solution S1 resulting from a) with respect to americium, curium and fission products, the decontamination comprising at least one contacting, in an extractor, of the organic solution S1 with an aqueous solution A2 comprising from 1 mol/L to 6 mol/L of nitric acid, followed by a separation of the organic solution S1 from the aqueous solution A2;

c) a partitioning of the uranium and plutonium contained in the organic solution S1 resulting from b) into an aqueous solution comprising either plutonium without uranium, or a mixture of plutonium and uranium, and an organic solution comprising uranium without plutonium, the partitioning comprising:

c 1 ) a stripping of plutonium, in oxidation state +IV, and of a fraction of uranium from the organic solution S1 resulting from b), the stripping comprising at least one contacting, in an extractor, of the organic solution S1 with an aqueous solution A3 comprising from 0.1 mol/L to 0.5 mol/L of nitric acid, followed by a separation of the organic solution S1 from the aqueous solution A3;

c 2 ) an extraction of all or part of the uranium fraction contained in the aqueous solution A3 resulting from c 1 ), the extraction comprising at least one contacting, in an extractor, of the aqueous solution A3 with an organic solution S2 identical to the organic solution S1 of a), followed by a separation of the aqueous solution A3 from the organic solution S2;

d) a decontamination of the organic solution S2 resulting from c 1 ) with respect to technetium, the decontamination comprising:

d 1 ) a stripping of technetium, in oxidation state +IV, from the organic solution S2 resulting from c 1 ), the stripping comprising at least one contacting, in an extractor, of the organic solution S2 with an aqueous solution A4 comprising from 0.1 mol/L to 3 mol/L of nitric acid and at least one reducing agent capable of reducing technetium from oxidation state +VII to oxidation state +IV, followed by a separation of the organic solution S2 from the aqueous solution A4;

d 2 ) an extraction of the uranium fraction contained in the aqueous solution A4 resulting from d 1 ), the extraction comprising at least one contacting, in an extractor, of the aqueous solution A4 with an organic solution S3 identical to the organic solution S1 of a), followed by a separation of the aqueous solution A4 from the organic solution S3;

e) a stripping of the uranium from the organic solution S3 resulting from d 1 ), the stripping comprising at least one contacting, in an extractor, of the organic solution S3 with an aqueous solution A5 comprising no more than 0.5 mol/L of nitric acid, followed by a separation of the organic solution S3 from the aqueous solution A5; and

f) a regeneration of the organic solution S3 resulting from e);

whereby a first and a second aqueous solution are obtained, decontaminated with respect to americium, curium and fission products including technetium, the first aqueous solution comprising plutonium without uranium, or a mixture of plutonium and uranium, and the second aqueous solution comprising uranium without plutonium.

9. The method of claim 8 , wherein the organic solution S1 of a) comprises from 1 mol/L to 2 mol/L of the N,N-dialkylamide or mixture of N,N-dialkylamides.

10. The method of claim 8 , wherein the aqueous solution A2 of b) comprises from 4 mol/L to 6 mol/L of nitric acid.

11. The method of claim 8 , wherein b) further comprises a de-acidification of the organic solution S1, the de-acidification comprising at least one contacting of the organic solution S1 with an aqueous solution A6 comprising from 0.1 mol/L to 1 mol/L of nitric acid, followed by a separation of the organic solution S1 from the aqueous solution A6.

12. The method of claim 8 , wherein the contacting of the organic solution S1 and the aqueous solution A3 in the extractor of c 1 ) comprises a circulation of the organic solution S1 and the aqueous solution A3 in the extractor with a ratio of the organic solution S1 flowrate to the aqueous solution A3 flowrate higher than 1.

13. The method of claim 8 , wherein d 2 ) comprises an acidification of the aqueous solution A4 resulting from d 1 ), to bring the concentration of nitric acid in the aqueous solution A4 to a value of at least 2.5 mol/L, the acidification comprising an addition of nitric acid to the extractor of d 2 ).

14. The method of claim 8 , wherein the contacting of the organic solution S3 and the aqueous solution A5 in the extractor of e) comprises a circulation of the organic solution S3 and the aqueous solution A5 in the extractor with a ratio of the organic solution S3 flowrate to the aqueous solution A5 flowrate higher than 1.

15. The method of claim 8 , wherein the aqueous solution A1 is an aqueous solution resulting from a dissolution of a spent nuclear fuel in nitric acid.

16. The method of claim 8 , wherein R 1 is a methyl, ethyl or n-propyl group.

17. The method of claim 8 , wherein R 2 is an n-propyl, n-butyl, n-pentyl, n-hexyl or n-heptyl group.

18. The method of claim 8 , wherein R 3 is an n-hexyl, n-heptyl, n-octyl, 2-ethylhexyl, n-nonyl, n-decyl or 2-ethyloctyl group.

19. The method of claim 8 , wherein:

R 1 is a methyl group, R 2 is an n-butyl group and R 3 is an n-nonyl group; or

R 1 and R 2 are each an n-propyl group and R 3 is an n-octyl group; or

R 1 is an n-propyl group, R 2 is an n-pentyl group and R 3 is an n-hexyl group.

Assignments (4)
CHANGE OF NAME Recorded Feb 4, 2022
From: ORANO CYCLE
To: ORANO DÉMANTÈLEMENT
Reel/Frame 058955/0522 →
ASSIGNMENT OF ASSIGNOR'S INTEREST Recorded Feb 4, 2022
From: ORANO DÉMANTÈLEMENT
To: ORANO RECYCLAGE
Reel/Frame 058955/0535 →
CHANGE OF NAME Recorded Feb 4, 2022
From: AREVA NC
To: ORANO CYCLE
Reel/Frame 058957/0601 →
ASSIGNMENT OF ASSIGNOR'S INTEREST Recorded Jul 22, 2019
From: MILANOLE, GAËLLE; RUSSELLO, EMILIE; MARIE, CÉCILE; MIGUIRDITCHIAN, MANUEL; SOREL, CHRISTIAN
To: COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES; ORANO CYCLE; ELECTRICITE DE FRANCE
Reel/Frame 049822/0650 →
Priority Claims (1)
FR 1750657 · Jan 26, 2017 · national
Continuity (1)
Related Publication 20210332002A1 · Oct 28, 2021