Commissariat &#xc0; L'&#xc9;nergie Atomique Et Aux &#xc9;nergies Alternatives

Other

Commissariat a L'energie Atomique

Compagnie Generale Des Matieres Nucleaires

Areva Nc

Orano Cycle

Michel Masson

Pascal Baron

Binh Dinh

Manuel Miguirditchian

Christian Sorel

Francois Drain

Xavier Heres

Michael Lecomte

Didier Saudray

Laurence Chareyre

François Poncelet

Vladimir Peretroukhine

Sylvain Costenoble

Alexandre Masslennikov

Vincent Vanel

Jean Luc Emin

Philippe Pradel

Jean-Luc Emin

François Drain

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.

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

The invention relates to a process for reprocessing spent nuclear fuel which, among other advantages, does not require a plutonium-reducing stripping operation. This process finds particular application in the processing of uranium oxide fuels and uranium and plutonium mixed oxide fuels.

Process for reprocessing spent nuclear fuel not requiring a plutonium-reducing stripping operation

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 HNO. 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.

Method for treating spent nuclear fuel

The invention relates to a process for reprocessing a spent nuclear fuel and for preparing a mixed uranium-plutonium oxide, which process comprises: Applications: reprocessing of nuclear fuels based on uranium oxide or on mixed uranium-plutonium oxide.

Process for reprocessing a spent nuclear fuel and of preparing a mixed uranium-plutonium oxide

The present invention relates to a process for separating technetium from a nitric solution of technetium through cathodic electrodeposition of said technetium by electrolysis. According to the process of the invention, the nitric solution of technetium is denitrified and its pH is adjusted to a value of approximately 5.5 to 7.5 before electrolysis. Electrolysis is conducted at galvanostatic rate, and the cathode potential is approximately &minus;1.36 V/SHE to &minus;1.16/SHE. The ratio of the cathode surface area (S) to the volume of the technetium solution to be electrolyzed may be in the region of 0.25 to 0.50 cm,.

Method for separating technetium from a nitric solution

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Avignon, France

Michel Masson