Patents by Inventor Sandra Lopes Moreira

Sandra Lopes Moreira has filed for patents to protect the following inventions. This listing includes patent applications that are pending as well as patents that have already been granted by the United States Patent and Trademark Office (USPTO).

  • Patent number: 10252983
    Abstract: Novel dissymmetric N,N-dialkylamides which meet the following formula (I): where R represents a linear or branched alkyl group at C8 to C15. A method for synthesizing these N,N-dialkylamides, and to the uses of same as extractants, alone or in admixture, in order to extract uranium and/or plutonium from an aqueous acid solution, or to totally or separate uranium from plutonium from an aqueous acid solution and, in particular, an aqueous solution resulting from dissolving spent nuclear fuel in nitric acid. Further, a method for processing 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 plutonium reduction operation, and in which one of the aforementioned N,N-dialkylamides or a mixture of same is used as extractant.
    Type: Grant
    Filed: July 28, 2016
    Date of Patent: April 9, 2019
    Assignees: COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES, ORANO CYCLE
    Inventors: Manuel Miguirditchian, Pascal Baron, Sandra Lopes Moreira, Gaëlle Milanole, Cécile Marie
  • Publication number: 20180222849
    Abstract: Novel dissymmetric N,N-dialkylamides which meet the following formula (I): where R represents a linear or branched alkyl group at C8 to C15. A method for synthesizing these N,N-dialkylamides, and to the uses of same as extractants, alone or in admixture, in order to extract uranium and/or plutonium from an aqueous acid solution, or to totally or separate uranium from plutonium from an aqueous acid solution and, in particular, an aqueous solution resulting from dissolving spent nuclear fuel in nitric acid. Further, a method for processing 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 plutonium reduction operation, and in which one of the aforementioned N,N-dialkylamides or a mixture of same is used as extractant.
    Type: Application
    Filed: July 28, 2016
    Publication date: August 9, 2018
    Inventors: Manuel Miguirditchian, Pascal Baron, Sandra Lopes Moreira, Gaëlle Milanole, Cécile Marie