Method for the treatment of an aqueous nitric solution resulting from dissolving spent nuclear fuel, said method being performed in a single cycle and without requiring any operation involving reductive stripping of plutonium

US10249396B2 · US · B2

Patent metadata
FieldValue
Publication numberUS-10249396-B2
Application numberUS-201615747713-A
CountryUS
Kind codeB2
Filing dateJul 28, 2016
Priority dateJul 29, 2015
Publication dateApr 2, 2019
Grant dateApr 2, 2019

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Abstract

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A method for the treatment of an aqueous solution resulting from the dissolution of a spent nuclear fuel in nitric acid, allowing the uranium and plutonium contained in the solution to be extracted, separated and decontaminated in a single cycle, without requiring any operation involving a reductive stripping of plutonium. Applications for the method include the processing of uranium-based and/or plutonium-based spent nuclear fuels.

First claim

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What is claimed is: 1. A method for processing in one cycle an aqueous solution resulting from a dissolution of a spent nuclear fuel in nitric acid, the aqueous solution 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, the co-extraction comprising at least one contacting, in an extractor, of the aqueous solution with a first organic solution comprising from 1 mol/L to 2 mol/L of N,N-di(2-ethylhexyl)-3,3-dimethylbutanamide or a mixture of N,N-di(2-ethylhexyl)-isobutanamide and N,N-di(2-ethylhexyl)-n-butanamide as extractant, in solution in an organic diluent, followed by a separation of the aqueous solution from the organic solution; b) a decontamination of the organic solution 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 resulting from a) with an aqueous solution comprising from 0.5 mol/L to 6 mol/L of nitric acid, followed by a separation of the organic solution from the aqueous solution; c) a partitioning of the uranium and plutonium contained in the organic solution resulting from b) into an aqueous solution and an organic solution, the aqueous solution comprising either plutonium without uranium, or a mixture of plutonium and uranium, and the 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 resulting from b), the stripping comprising at least one contacting, in an extractor, of the organic solution resulting from b) with an aqueous solution comprising from 0.1 mol/L to 0.5 mol/L of nitric acid, followed by a separation of the organic solution from the aqueous solution; c 2 ) an extraction of all or part of the uranium fraction contained in the aqueous solution resulting from c 1 ), the extraction comprising at least one contacting, in an extractor, of the aqueous solution resulting from c 1 ) with a second organic solution identical to the first organic solution, followed by a separation of the aqueous solution from the second organic solution; d) a decontamination of the organic solution 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 resulting from c 1 ), the stripping comprising at least one contacting, in an extractor, of the organic solution resulting from c 1 ) with an aqueous solution 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, or a complexing agent capable of stabilising technetium in aqueous phase, followed by a separation of the organic solution from the aqueous solution; d 2 ) an extraction of the uranium fraction contained in the aqueous solution resulting from d 1 ), the extraction comprising at least one contacting, in an extractor, of the aqueous solution resulting from d 1 ) with a third organic solution identical to the first organic solution, followed by a separation of the aqueous solution from the third organic solution; e) a stripping of uranium from the organic solution resulting from d 1 ), the stripping comprising at least one contacting, in an extractor, of the organic solution resulting from di) with an aqueous solution comprising no more than 0.05 mol/L of nitric acid, followed by a separation of the organic solution from the aqueous solution; and f) a regeneration of the organic solution resulting from e); whereby a first and 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. 2. The method of claim 1 , wherein the first organic solution comprises from 1.3 mol/L to 1.4 mol/L of N,N-di(2-ethylhexyl)-3,3-dimethyl-butanamide. 3. The method of claim 1 , wherein the first organic solution comprises from 1.35 mol/L to 1.45 mol/L of the mixture of N,N-di(2-ethylhexyl)-isobutanamide and N,N-di-2(ethylhexyl)-n-butanamide. 4. The method of claim 3 , wherein the molar ratio of N,N-di(2-ethylhexyl)-isobutanamide to N,N-di-2(ethylhexyl)-n-butanamide in the first organic solution is 1.75 to 1.85. 5. The method of claim 4 , wherein the first organic solution comprises 0.9 mol/L of N,N-di(2-ethylhexyl)-isobutanamide and 0.5 mol/L of N,N-di-2(ethylhexyl)-n-butanamide. 6. The method of claim 1 , wherein the aqueous solution of b) comprises from 4 mol/L to 6 mol/L of nitric acid. 7. The method of claim 6 , wherein b) further comprises a deacidification of the organic solution resulting from a), the deacidification comprising at least one contacting of the organic solution resulting from a) with an aqueous solution comprising no more than 1 mol/L of nitric acid, followed by a separation of the organic and aqueous solutions. 8. The method of claim 1 , wherein the contacting of the organic and aqueous solutions in the extractor of c 1 ) comprises a circulation of the organic and aqueous solutions with a ratio of the flow of the organic solution to the flow of the aqueous solution higher than 1. 9. The method of claim 1 , wherein the reducing agent of d 1 ) is uranous nitrate, hydrazinium nitrate, hydroxylammonium nitrate, acetaldoxime or a mixture thereof. 10. The method of claim 1 , wherein the extractor of d 1 ) is heated to a temperature of 30° C. to 40° C. 11. The method of claim 1 , wherein d 2 ) comprises an acidification of the aqueous solution resulting from d 1 ) to bring the concentration of nitric acid in the aqueous solution resulting from d 1 ) to a value of at least 2.5 mol/L, the acidification comprising the addition of nitric acid to the extractor of d 2 ). 12. The method of claim 1 , wherein the extractor of e) is heated to a temperature of 40° C. to 50° C. 13. The method of claim 1 , wherein the contacting of the organic and aqueous solutions in the extractor of e) comprises a circulation of the organic and aqueous solutions with a ratio of the flow of the organic solution to the flow of the aqueous solution higher than 1. 14. The method of claim 1 , wherein the regeneration of the organic solution resulting from e) comprises at least one washing of the organic solution resulting from e) with a basic aqueous solution, followed by at least one washing of the washed organic solution with an aqueous solution of nitric acid. 15. The method of claim 1 , wherein the organic solution resulting from f) is divided into a first and a second fraction, the first fraction forming the first organic solution of a) and the second fraction forming the second organic solution of c 2 ).

Assignees

Inventors

Classifications

  • G21C19/46Primary

    Aqueous processes {, e.g. by using organic extraction means, including the regeneration of these means} · CPC title

  • liquid-liquid extraction with or without dissolution in organic solvents · CPC title

  • Chemistry & Metallurgy · mapped topic

  • Cross-Sectional Technologies · mapped topic

  • Carboxylic acids · CPC title

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What does patent US10249396B2 cover?
A method for the treatment of an aqueous solution resulting from the dissolution of a spent nuclear fuel in nitric acid, allowing the uranium and plutonium contained in the solution to be extracted, separated and decontaminated in a single cycle, without requiring any operation involving a reductive stripping of plutonium. Applications for the method include the processing of uranium-based and/…
Who is the assignee on this patent?
Commissariat Energie Atomique, Areva Nc, Orano Cycle
What technology area does this patent fall under?
Primary CPC classification G21C19/46. Mapped technology areas include Physics.
When was this patent published?
Publication date Tue Apr 02 2019 00:00:00 GMT+0000 (Coordinated Universal Time) (B2). Legal status and post-grant events are not shown on this page.
What related patents are in patentsdb?
We list 1 related publication on this page (citations in our corpus or others sharing the same primary CPC).