The patent badge is an abbreviated version of the USPTO patent document. The patent badge does contain a link to the full patent document.

The patent badge is an abbreviated version of the USPTO patent document. The patent badge covers the following: Patent number, Date patent was issued, Date patent was filed, Title of the patent, Applicant, Inventor, Assignee, Attorney firm, Primary examiner, Assistant examiner, CPCs, and Abstract. The patent badge does contain a link to the full patent document (in Adobe Acrobat format, aka pdf). To download or print any patent click here.

Date of Patent:
Feb. 14, 2023

Filed:

Jan. 25, 2018
Applicants:

Commissariat À L'énergie Atomique ET Aux Énergies Alternatives, Paris, FR;

Orano Cycle, Courbevoie, FR;

Electricite DE France, Paris, FR;

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;

Attorney:
Primary Examiner:
Int. Cl.
CPC ...
C07C 233/05 (2006.01); C22B 3/32 (2006.01); C22B 60/02 (2006.01); C22B 60/04 (2006.01); G21C 19/46 (2006.01); C07C 231/02 (2006.01);
U.S. Cl.
CPC ...
C07C 233/05 (2013.01); C22B 3/32 (2021.05); C22B 60/026 (2013.01); C22B 60/04 (2013.01); G21C 19/46 (2013.01); C07C 231/02 (2013.01); Y02E 30/30 (2013.01); Y02P 10/20 (2015.11);
Abstract

A dissymmetric RN,N-dialkylamides of formula (I) in which: Rrepresents a linear Cto Calkyl, Rrepresents a linear Cto Calkyl, and Rrepresents a linear or branched Cto Calkyl, where Ris different from a n-octyl, n-decyl, n-dodecyl, 2-ethylhexyl and 2-ethyloctyl group when Rrepresents a n-butyl group and Rrepresents 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.


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