Abstract: 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.

Abstract: 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.

Abstract: The invention relates to a module for capturing at least one gas dissolved in a liquid (L), arranged so as to be mounted on a body (12) of a device (10) for measuring the value of at least one parameter of said gas, said capturing module (20) comprising a gas circulation base arranged so as to be mounted on said body (12), the capturing module (20) being characterized in that it comprises a housing for receiving at least one membrane, defining an opening and projecting from said base, and at least one membrane mounted in said housing so as to extend inside said opening in order to capture the gas dissolved in the liquid (L).

Abstract: The invention relates to a module for capturing at least one gas dissolved in a liquid (L), arranged so as to be mounted on a body (12) of a device (10) for measuring the value of at least one parameter of said gas, said capturing module (20) comprising a gas circulation base arranged so as to be mounted on said body (12), the capturing module (20) being characterised in that it comprises a housing for receiving at least one membrane, defining an opening and projecting from said base, and at least one membrane mounted in said housing so as to extend inside said opening in order to capture the gas dissolved in the liquid (L).

Abstract: 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.

Abstract: 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.

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.

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.

Abstract: A protection device to close the gun slit (or opening) of a mount, such gun slit delimited by two lateral flanges and two end flanges and in which pivots or moves a mobile organ carrying a mobile wall positioned between the exterior and interior of the mount, device which comprises at least one flexible bellows integral on one side with an end flange of the gun slit and on the other with the mobile organ (3), such device wherein the bellows and wall delimit an intermediate chamber that is linked to the internal space (10) of the mount, such space being pressurized by pressurization means.

Abstract: The invention concerns a method for detecting a known function, from nucleic acids present in a sample, characterized in that it comprises the following steps: (a) preparing, from the nucleic acids of the sample, nucleic acid molecules comprising the gene(s) coding for the protein(s) corresponding to said function, and the control elements required for the transcription and the translation of said gene(s); (b) in vitro transcription and translation of the nucleic acid molecule prepared in step (a); (c) detecting and/or measuring the function corresponding to the protein(s) produced in step (b).

Abstract: The invention relates to methods of determining the mutational load of a gene bank obtained by random mutagenesis of a gene of interest by preparing a chart linking the mutational load of a gene bank obtained by random mutagenesis of a model gene with the fraction of mutated model genes observed in the bank; performing, in parallel, random mutagenesis of the model gene used for preparing the chart and the gene of interest to obtain the corresponding mutated gene banks; determining the mutational load of the gene bank obtained using the model gene on the basis of the chart plotted; and applying a correction factor to the mutational load of the mutated model gene bank to determine the mutational load in the gene bank of the mutated genes of interest.

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.

Abstract: Ligation-mediated method of recombining polynucleotides in vitro. Polynucleotides from a library are fragmented and the fragments are hybridized to an assembly template. The hybridized fragments are iteratively re-hybridized and ligated until the ends of the hybridized fragments are adjacent to the ends of other hybridized fragments on the assembly template. A final ligation produces recombined polynucleotides.

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.

Abstract: The present invention relates to a method used to determine the mutational load of a gene bank obtained by means of random mutagenesis of a gene of interest comprising: a) the preparation of a chart linking the mutational load (ML) of gene bank obtained by means of random mutagenesis of a model gene with the fraction of mutated model genes observed in said bank; b) the random mutagenesis of the model gene used for the preparation of the chart for step (a) and the gene of interest to obtain the corresponding mutated gene banks; c) the determination of the mutational load (ML) of the gene bank obtained using the model gene in step (b) on the basis of the chart plotted in step (a); d) the application of a correction factor (CF) to the mutational load (ML) of the mutated model gene bank determined in step (c) to determine the mutational load (ML) of the banks of mutated genes of interest from step (b).

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.

Abstract: The present invention provides methods and composition for enhancing in vitro synthesis of biological macro-molecules in a call-free system where ATP is required as a primary energy source, wherein said cell-free system is enriched with ATP-sulfurylase The invention relates also to as cell-free systems and cell-free extracts enriched with ATP-sulfurylase for enhancing in vitro synthesis of any biological macromolecules.

Abstract: The object of this invention is a process for the creation of at least one recombinant polynucleotide sequence comprising a step of oriented ligation of fragments derived from a bank of at least two polynucleotide sequences, and optionally cloning the recombinant polynucleotide sequences, and the selection of polynucleotide sequences offering advantageous characteristics compared to one or several reference sequences.

Abstract: Ligation-mediated method of recombining polynucleotides in vitro. Polynucleotides from a library are fragmented and the fragments are hybridized to an assembly template. The hybridized fragments are iteratively re-hybridized and ligated until the ends of the hybridized fragments are adjacent to the ends of other hybridized fragments on the assembly template. A final ligation produces recombined polynucleotides.

Abstract: Ligation-mediated method of recombining polynucleotides in vitro. Polynucleotides from a library are fragmented and the fragments are hybridized to an assembly template. The hybridized fragments are iteratively re-hybridized and ligated until the ends of the hybridized fragments are adjacent to the ends of other hybridized fragments on the assembly template. A final ligation produces recombined polynucleotides.