Commissariat a L'energie Atomique Et Aux Energies Alternatives

Commissariat a L'energie Atomique

Compagnie Generale Des Matieres Nucleaires

Areva Nc

Orano Cycle

Binh Dinh

Pascal Baron

Gilles Bernier

Christian Sorel

Michel Masson

Manuel Miguirditchian

Francois Drain

Xavier Heres

Michael Lecomte

Patrick Pochon

Elisabeth Zekri

Philippe Moisy

François Poncelet

Didier Saudray

Marc Montuir

Michaël Lecomte

Jean-Luc Emin

Philippe Pradel

Jean Luc Emin

Laurent Venault

Jean Bertin

Isabelle Bisel

Coralie Balaguer

Danièle Sans

François Drain

The use of hydroxyiminoalkanoic acids including at least four carbon atoms as anti-nitrous agents in operations of reductive stripping of plutonium. The invention may be useful in any method for processing spent nuclear fuels that includes one or more operations of reductive stripping of plutonium and, more particularly, in the PUREX method as implemented in modern nuclear fuel processing plants, as well as in processes derived therefrom.

Use of hydroxyiminoalkanoic acids as anti-nitrous agents in operations of reductive stripping of plutonium

A method with which uranium from a natural uranium concentrate may be purified, including The extractant is an N,N-dialkylamide and the ratio between the flow rate at which the organic phase obtained at the end of step b) and the aqueous phase A3 circulate in the apparatus where step c) occurs, is greater than 1.

Method for purifying the uranium from a natural uranium concentrate

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

The invention relates to the use of butyraldehyde oxime as an anti-nitrous agent in a plutonium stripping operation based on a reduction of this element from oxidation state (IV) to oxidation state (III). Applications: any nuclear fuel reprocessing process in which employing a compound that has the twofold property of being extractable into an organic phase and of being capable of destroying the nitrous acid therein may be useful and especially any process including one or more operations for the reductive stripping of plutonium.

Use of butyraldehyde oxime as an anti-nitrous agent in an operation for the reductive stripping of plutonium

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 invention relates to a method for separating uranium(VI) from one or more actinides selected from actinides(IV) and actinides(VI) other than uranium(VI), characterized in that it comprises the following steps: a) bringing an organic phase, which is immiscible with water and contains the said uranium and the said actinide or actinides, in contact with an aqueous acidic solution containing at least one lacunary heteropolyanion and, if the said actinide or at least one of the said actinides is an actinide(VI), a reducing agent capable of selectively reducing this actinide(VI); and b) separating the said organic phase from the said aqueous solution. Applications: reprocessing irradiated nuclear fuels, processing rare-earth, thorium and/or uranium ores.

Method for separating uranium (VI) from actinides(IV) and/or actinides (VI) and its uses

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Pont Saint Esprit, France

Binh Dinh