Patents by Inventor Jean-Luc Emin

Jean-Luc Emin 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: 8394346
    Abstract: A method for treating spent nuclear fuel, which includes first decontaminating the uranium, plutonium and neptunium found in a nitric aqueous phase resulting from dissolving the nuclear fuel in HNO3. The uranium, plutonium and neptunium found in the solvent phase is then split in a first aqueous phase and a second aqueous phase. Next, the first aqueous phase is stored. Following, the plutonium or other mixtures found in the first aqueous phase is purified relative to the fission products still found in said phase, in order to obtain, at the end of said purification, an aqueous solution containing a mixture of Pu and U or Pu, U and Np. Finally the resulting mixture of Pu and U or the mixture of Pu, U and Np is co-converted into a mixed oxide.
    Type: Grant
    Filed: June 29, 2010
    Date of Patent: March 12, 2013
    Assignees: Areva NC, Commissariat a l'Energie Atomique et aux Energies Alternatives
    Inventors: Jean Luc Emin, Francois Drain, Francois Poncelet, Binh Dinh, Philippe Pradel, Pascal Baron, Michel Masson
  • Publication number: 20120128555
    Abstract: A method for treating spent nuclear fuel, which includes first decontaminating the uranium, plutonium and neptunium found in a nitric aqueous phase resulting from dissolving the nuclear fuel in HNO3. The uranium, plutonium and neptunium found in the solvent phase is then split in a first aqueous phase and a second aqueous phase. Next, the first aqueous phase is stored. Following, the plutonium or other mixtures found in the first aqueous phase is purified relative to the fission products still found in said phase, in order to obtain, at the end of said purification, an aqueous solution containing a mixture of Pu and U or Pu, U and Np. Finally the resulting mixture of Pu and U or the mixture of Pu, U and Np is co-converted into a mixed oxide.
    Type: Application
    Filed: June 29, 2010
    Publication date: May 24, 2012
    Applicants: Commissariat à l'énergie atomique et aux énergies alternatives, AREVA NC
    Inventors: Jean Luc Emin, Francois Drain, Francois Poncelet, Binh Dinh, Philippe Pradel, Pascal Baron, Michel Masson
  • Patent number: 7887767
    Abstract: The invention relates to a process for reprocessing a spent nuclear fuel and for preparing a mixed uranium-plutonium oxide, which process comprises: a) the separation of the uranium and plutonium from the fission products, the americium and the curium that are present in an aqueous nitric solution resulting from the dissolution of the fuel in nitric acid, this step including at least one operation of coextracting the uranium and plutonium from said solution by a solvent phase; b) the partition of the coextracted uranium and plutonium to a first aqueous phase containing plutonium and uranium, and a second aqueous phase containing uranium but no plutonium; c) the purification of the plutonium and uranium that are present in the first aqueous phase; and d) a step of coconverting the plutonium and uranium to a mixed uranium/plutonium oxide. Applications: reprocessing of nuclear fuels based on uranium oxide or on mixed uranium-plutonium oxide.
    Type: Grant
    Filed: May 24, 2007
    Date of Patent: February 15, 2011
    Assignees: Commissariat a l'Energie Atomique, Compagnie Generale des Matieres Nucleaires
    Inventors: Pascal Baron, Binh Dinh, Michel Masson, Francois Drain, Jean-Luc Emin
  • Publication number: 20090184298
    Abstract: A process for reprocessing a spent nuclear fuel and for preparing a mixed uranium-plutonium oxide. The process: a) separates the uranium and plutonium from fission products, americium, and curium that are present in an aqueous nitric solution resulting from dissolution of the fuel in nitric acid, the separating including at least one operation of coextracting the uranium and plutonium from the solution by a solvent phase; b) partitions the coextracted uranium and plutonium to a first aqueous phase containing plutonium and uranium, and a second aqueous phase containing uranium but no plutonium; c) purifies the plutonium and uranium that are present in the first aqueous phase; and d) coconverts the plutonium and uranium to a mixed uranium/plutonium oxide.
    Type: Application
    Filed: May 23, 2007
    Publication date: July 23, 2009
    Applicants: Commissariat A L'Energie Atomique, Areva NC
    Inventors: Pascal Baron, Binh Dinh, Michel Masson, Francois Drain, Jean Luc Emin
  • Publication number: 20070290178
    Abstract: The invention relates to a process for reprocessing a spent nuclear fuel and for preparing a mixed uranium-plutonium oxide, which process comprises: a) the separation of the uranium and plutonium from the fission products, the americium and the curium that are present in an aqueous nitric solution resulting from the dissolution of the fuel in nitric acid, this step including at least one operation of coextracting the uranium and plutonium from said solution by a solvent phase; b) the partition of the coextracted uranium and plutonium to a first aqueous phase containing plutonium and uranium, and a second aqueous phase containing uranium but no plutonium; c) the purification of the plutonium and uranium that are present in the first aqueous phase; and d) a step of coconverting the plutonium and uranium to a mixed uranium/plutonium oxide. Applications: reprocessing of nuclear fuels based on uranium oxide or on mixed uranium-plutonium oxide.
    Type: Application
    Filed: May 24, 2007
    Publication date: December 20, 2007
    Applicants: COMMISSARIAT A L'ENERGIE ATOMIQUE, COMPAGNIE GENERALE DES MATIERES NUCLEAIRES
    Inventors: Pascal Baron, Binh Dinh, Michel Masson, Francois Drain, Jean-Luc Emin