COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
ORANO (France)
Inventeur(s)
Serp, Jérôme
Abrégé
A device comprising a component configured to contain or circulate a solution, the component having a wall made of steel or a nickel-based alloy comprising chromium, a solution in contact with the wall and including a mixture of molten chloride salts. The solution also includes Ti2+ ions and Ti3+ ions, the Ti3+/Ti2+ ratio being between 20/80 and 70/30.
The invention relates to an operating method, which comprises: - a first operating phase during which current values of state variables characterising the loaded liquid collected in the collecting wells (12) are periodically acquired at determined instants staggered between an initial instant (T0) and a final instant (Tf), the state variables comprising at least the concentration of the element of interest in the loaded liquid; - a phase of estimating control variables characterising a geology of the mine, using the current values of the state variables collected during the first operating phase, the control variables including at least one initial content of the element of interest in solid phase at the initial instant (T0) at least at one point of the mine; the estimation phase comprising the following steps, repeated iteratively: - determining estimated values of the state variables at the determined instants of the first operating phase, by a numerical model of reagent transport in the mine, using at least one set of control variables; - calculating a deviation between the estimated values and the current values of the state variables at the determined instants of the first operating phase; and - determining at least one new set of control variables using the deviation, by an optimisation method, the at least one new set of control variables being used in the step of determining estimated values of the state variables of the next iteration.
A device for evaluating uranium content and hydrogen porosity while drilling includes a probe having a pulsed neutron generator for emitting a pulse of neutrons, a single neutron detector, a neutron counting unit for measuring over time a number of neutrons backscattered from hydrogen nuclei and a number of prompt fission neutrons resulting from interactions with uranium nuclei. The device also includes a hydrogen porosity evaluation unit for evaluating the hydrogen porosity using a total number of backscattered neutrons and a uranium evaluation unit for evaluating the uranium content using a total number of prompt fission neutrons.
G01V 5/10 - Prospection ou détection au moyen de rayonnement ionisant, p. ex. de la radioactivité naturelle ou provoquée spécialement adaptée au carottage en utilisant des sources de radiation nucléaire primaire ou des rayons X en utilisant des sources de neutrons
G01V 5/06 - Prospection ou détection au moyen de rayonnement ionisant, p. ex. de la radioactivité naturelle ou provoquée spécialement adaptée au carottage pour détecter des minerais à radioactivité naturelle
4.
METHOD FOR IRRIGATING A POROUS SUBSTRATE USING A FOAM, AND THE USES THEREOF
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
Inventeur(s)
Durupt, Nicolas
Faure, Sylvain
Frances, Fabien
Grandjean, Agnès
Abrégé
The present invention relates to a method for irrigating a porous substrate comprising the steps of: preparing a foam consisting of a dispersion of air bubbles in a foaming aqueous solution, said foam comprising a liquid fraction of less than or equal to 15% by volume; spreading, over the surface of the porous substrate, a layer of the foam thus prepared, the thickness of the layer being greater than 5 cm, then maintaining the assembly long enough for at least a part of the liquid contained in the foam to infiltrate the porous substrate. The present invention also relates to the use of this method to recover an element of interest contained in a porous substrate and a particular aqueous foam.
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
ORANO (France)
Inventeur(s)
Andreiadis, Eugen
Moreau, Ella
Abrégé
A process for purifying ruthenium from an aqueous nitric acid solution which is present together with technetium and metal impurities, at a concentration at least 10 times lower than that of the technetium. A process for producing ruthenium-97 from a technetium-99 target which has been proton-irradiated beforehand, including implementation of the purification process. The processes herein can be used for production of ruthenium-97-based radiopharmaceuticals used in nuclear medicine for the diagnosis of cancer by imaging and the treatment thereof by targeted radiotherapy.
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
Inventeur(s)
Marchais, Thomas
Perot, Bertrand
Allinei, Pierre-Guy
Toubon, Hervé
Bensedik, Youcef
Abrégé
A method for assessing the uranium content in a region of interest of a subsoil using gamma spectrometry includes acquiring at least one energy spectrum of gamma radiation associated with the region of interest. The energy spectrum includes at least one low-energy band, one high-energy band, a contribution of the self-attenuation of uranium in the low-energy band being greater than a contribution of the self-attenuation of uranium in the high-energy band. The method also includes assessing the uranium content in the region of interest using the area of the low-energy band, the area of the high-energy band of the energy spectrum acquired in the region of interest and at least two calibration coefficients.
G01V 5/06 - Prospection ou détection au moyen de rayonnement ionisant, p. ex. de la radioactivité naturelle ou provoquée spécialement adaptée au carottage pour détecter des minerais à radioactivité naturelle
E21B 49/00 - Test pour déterminer la nature des parois des trous de forageEssais de couchesProcédés ou appareils pour prélever des échantillons du terrain ou de fluides en provenance des puits, spécialement adaptés au forage du sol ou aux puits
G01T 1/202 - Mesure de l'intensité de radiation avec des détecteurs à scintillation le détecteur étant du cristal
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
ORANO (France)
Inventeur(s)
Billy, Emmanuel
Porthault, Hélène
Abrégé
A method for opening an electrochemical generator comprising a negative electrode containing lithium or sodium and a positive electrode optionally containing lithium or sodium, the method including the following successive steps: a) immersing the electrochemical generator in a solution comprising an inert liquid and, optionally, a so-called oxidising redox species able to be reduced on the negative electrode so as to discharge the electrochemical generator, b) opening the electrochemical generator, in the solution, with a cutting element having an electrical resistance of between 1 mΩ and 1 kΩ, and preferably between 5 mΩ and 100Ω.
METHOD AND ASSEMBLY FOR CHARACTERISING A SOLID SAMPLE LIKELY TO CONTAIN A RADIOACTIVE ELEMENT DISINTEGRATING ACCORDING TO A DISINTEGRATION CHAIN BY EMISSION OF α AND/OR β PARTICLES
CENTRE NATIONAL DE LA RECHERCHE SCIENTIFIQUE (France)
Inventeur(s)
Donnard, Jérôme
Sardini, Paul
Descostes, Michaël
Abrégé
The invention relates to a characterisation method which comprises the following steps: - taking an autoradiograph of the solid sample, including recording the following data for each detected α or β particle: time of detection of the particle, spatial coordinates of an emergence point of the particle, charge deposited by the particle upon detection; - analysing the recorded data so as to detect two successive isotopes in the disintegration chain, with the following sub-steps: * locating pairs of particles verifying the following criteria: detection times separated by a time interval less than a given limit; distance between the respective emergence points less than a given limit; charge deposited by the detected first particle corresponding to the disintegration of the first isotope; charge deposited by the detected second particle corresponding to the disintegration of the second isotope; and * counting the number of pairs identified.
G01T 1/178 - Dispositions de circuits non adaptés à un type particulier de détecteur pour la mesure d'une activité spécifique en présence d'autres substances radioactives, p. ex. des substances naturelles, présentes dans l'air ou dans des liquides tels que l'eau de pluie
G01T 1/29 - Mesure effectuée sur des faisceaux de radiations, p. ex. sur la position ou la section du faisceauMesure de la distribution spatiale de radiations
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES M (France)
ORANO (France)
Inventeur(s)
Billy, Emmanuel
Abrégé
A method for recycling at least one electrode comprising the following successive steps: a) providing at least one electrode comprising a current collector, an active material and, optionally, a binder, b) immersing the at least one electrode in an ionic liquid solution, comprising a solvent ionic liquid, in the presence of ultrasounds, whereby the active material, and optionally the binder, is separated from the current collector.
C22B 3/22 - Traitement ou purification de solutions, p. ex. de solutions obtenues par lixiviation par des procédés physiques, p. ex. par filtration, par des moyens magnétiques
C22B 7/00 - Mise en œuvre de matériaux autres que des minerais, p. ex. des rognures, pour produire des métaux non ferreux ou leurs composés
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
ORANO (France)
Inventeur(s)
Billy, Emmanuel
Abrégé
A method for dissolving a positive electrode material of a battery including a step during which the positive electrode material, comprising lithium and optionally cobalt and/or nickel, is submerged in an acid solution having a pH between 0 and 4, the acid solution containing either manganese ions or hydrogen peroxide, by means of which the lithium and optionally the cobalt and/or nickel is dissolved, and the manganese ions are selectively precipitated in the form of manganese oxyhydroxide.
C22B 3/22 - Traitement ou purification de solutions, p. ex. de solutions obtenues par lixiviation par des procédés physiques, p. ex. par filtration, par des moyens magnétiques
C22B 3/44 - Traitement ou purification de solutions, p. ex. de solutions obtenues par lixiviation par des procédés chimiques
C22B 7/00 - Mise en œuvre de matériaux autres que des minerais, p. ex. des rognures, pour produire des métaux non ferreux ou leurs composés
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
ORANO (France)
Inventeur(s)
Billy, Emmanuel
Abrégé
A method for securing an electrochemical generator comprising a negative electrode containing lithium or sodium and a positive electrode, the method comprising the following successive steps: a) immersing an electrochemical generator, in an ionic liquid solution comprising a solvent ionic liquid and, possibly, a so-called oxidant redox species able to be reduced on the negative electrode so as to discharge the electrochemical generator, b) opening the electrochemical generator with an electrically-insulating element, opening being carried out in the ionic liquid solution.
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
ORANO (France)
Inventeur(s)
Billy, Emmanuel
Brunbuisson, David
Guilpain, Mathilde
Abrégé
A method for discharging an electrochemical generator comprising a negative electrode containing lithium or sodium and a positive electrode, the method comprising a step of discharging the electrochemical generator during which the electrochemical generator is brought into contact with an ionic liquid solution comprising a solvent ionic liquid and an electrically-conductive powder so as to discharge it.
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
Inventeur(s)
Durupt, Nicolas
Faure, Sylvain
Frances, Fabien
Grandjean, Agnès
Abrégé
The present invention relates to a method for irrigating a porous substrate, comprising the steps of: preparing a foam consisting of a dispersion of air bubbles in a foaming aqueous solution, said foam comprising a liquid fraction of less than or equal to 15% by volume; spreading, over the surface of the porous substrate, a layer of the foam thus prepared, the thickness of the layer being greater than 5 cm; then maintaining the assembly long enough for at least a part of the liquid contained in the foam to infiltrate the porous substrate. The present invention further relates to the use of this method to recover an element of interest contained in a porous substrate and a particular aqueous foam.
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVESÉ (France)
ORANO (France)
Inventeur(s)
Billy, Emmanuel
Barthelemy, Sandrine
Abrégé
A method for selectively separating a carbon-containing material from a mixture comprising a positive electrode and a negative electrode originating from electrochemical cells and/or accumulators, the method comprising the following successive steps: a) providing a mixture comprising a positive electrode and a negative electrode, each electrode comprising a current collector, an active material and a binder, the active material of the negative electrode being a carbon-containing material, preferably graphite, b) contacting the mixture comprising the positive electrode and the negative electrode with a separation solution, in the presence of ultrasound, the separation solution comprising a solvent and, optionally, additives, until selectively separating the carbon-containing material from the current collector of the negative electrode, the active material of the positive electrode remaining secured to the current collector of the positive electrode.
H01M 10/54 - Récupération des parties utiles des accumulateurs usagés
B09B 3/80 - Destruction de déchets solides ou transformation de déchets solides en quelque chose d'utile ou d'inoffensif impliquant une étape d'extraction
B09B 3/70 - Traitement chimique, p. ex. ajustement du pH ou oxydation
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
Inventeur(s)
Fondement, Valentin
Perot, Bertrand
Marchais, Thomas
Toubon, Hervé
Bensedik, Youcef
Abrégé
The invention relates to a device (10) for evaluating uranium content and hydrogen porosity while drilling. The device (10) comprises: - a probe (16) having a pulsed neutron generator (36) for emitting a pulse of neutrons and a single neutron detector (38); - a neutron counting unit (26) for measuring over time a number of neutrons backscattered from hydrogen nuclei and a number of prompt fission neutrons from interactions with uranium nuclei; - a hydrogen porosity evaluation unit (28) for evaluating the hydrogen porosity using a total number of backscattered neutrons; and - a uranium content evaluation unit (30) for evaluating the uranium content using a total number of prompt fission neutrons.
G01V 5/10 - Prospection ou détection au moyen de rayonnement ionisant, p. ex. de la radioactivité naturelle ou provoquée spécialement adaptée au carottage en utilisant des sources de radiation nucléaire primaire ou des rayons X en utilisant des sources de neutrons
16.
METHOD FOR ASSESSING THE URANIUM CONTENT IN A BOREHOLE USING GAMMA SPECTROMETRY AND ASSOCIATED DEVICE
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
Inventeur(s)
Marchais, Thomas
Perot, Bertrand
Allinei, Pierre-Guy
Toubon, Hervé
Bensedik, Youcef
Abrégé
The invention relates to a method for assessing the uranium content in a region of interest (10) of a subsoil (11) using gamma spectroscopy, the method comprising the following steps: a) acquiring at least one energy spectrum of gamma radiation associated with the region of interest (10), the energy spectrum comprising at least one low-energy band, one high-energy band, a contribution from the self-attenuation of uranium in the low-energy band being greater than a contribution from the self-attenuation of uranium in the high-energy band; b) assessing the uranium content in the region of interest (10) using the area of the low-energy band, the area of the high-energy band of the energy spectrum acquired in the region of interest and at least two calibration coefficients.
G01N 23/083 - Recherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p. ex. rayons X ou neutrons, non couvertes par les groupes , ou en transmettant la radiation à travers le matériau et mesurant l'absorption le rayonnement consistant en rayons X
G01T 1/36 - Mesure de la distribution spectrale des rayons X ou d'une radiation nucléaire
18.
DEVICE FOR SAMPLING SOLID PRODUCTS IN A BOREHOLE, ASSOCIATED SAMPLING ASSEMBLY AND METHOD
The invention relates to a device (10) for sampling solid products (14) in a borehole (12), comprising: - a frame (32) having an outer wall intended to be placed facing the inner side wall (28) of the borehole (12), - a filter basket (34) mounted on the frame (32) having a lower wall and a side wall connected to the lower wall, the side wall defining an upper opening for the passage of solid products (14). The outer wall of the frame (32) and/or the side wall of the filter basket (34) are configured to loosen at least a portion of the solid products (14) by scraping the inner side wall (28) of the borehole (12).
E21B 49/06 - Test pour déterminer la nature des parois des trous de forageEssais de couchesProcédés ou appareils pour prélever des échantillons du terrain ou de fluides en provenance des puits, spécialement adaptés au forage du sol ou aux puits par prélèvements mécaniques d'échantillons du terrain au moyen d'outils de forage latéral ou de dispositifs de raclage
E21B 27/00 - Récipients pour ramasser ou déposer des substances dans les trous de forage ou les puits, p. ex. cuillers pour ramasser de la boue ou du sableTrépans comportant des moyens pour ramasser des substances, p. ex. trépans à clapet
19.
METHOD FOR ASSESSING THE URANIUM CONTENT USING GAMMA SPECTROMETRY IN A WELLBORE AND ASSOCIATED DEVICE
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
Inventeur(s)
Marchais, Thomas
Perot, Bertrand
Carasco, Cedric
Toubon, Hervé
Bensedik, Youcef
Abrégé
The invention relates to a method for assessing the uranium content of at least one region of interest (10) of a subsoil (11) traversed by a wellbore (12) using gamma spectrometry. The method comprises the following steps: a) acquiring a first and a second calibration energy spectrum of gamma radiation in a first and a second calibration region (18, 20); b) respectively obtaining at least one first and one second radioactive imbalance of uranium; c) computing a first and a second ratio between the area of a first energy band and the area of a second energy band of the first and second calibration energy spectra; d) computing a first and a second coefficient from the radioactive imbalances and the ratios; e) acquiring an energy spectrum associated with the region of interest (10); f) computing the uranium content in the region of interest (10) using the first and second coefficients in particular.
G01V 5/06 - Prospection ou détection au moyen de rayonnement ionisant, p. ex. de la radioactivité naturelle ou provoquée spécialement adaptée au carottage pour détecter des minerais à radioactivité naturelle
20.
MEASURING DEVICE FOR RADIOLOGICAL CHARACTERISATION OF A GEOGRAPHICAL REGION OF INTEREST AND ASSOCIATED METHODS
The invention relates to a measuring device (10) for radiological characterisation of a geographical region of interest (12), the device (10) comprising: - a pole (14), the pole (14) comprising a lower end (18) intended to make contact with the geographical region of interest (12), and the pole (14) containing least one internal volume (36), - at least one nuclear measuring unit (38), accommodated in the at least one internal volume (36), and configured to measure at least one nuclear quantity, and - a positioning unit (52) configured to measure a position of the pole (14), the positioning unit (52) comprising at least one antenna (54) fastened to the pole (14), with a view to receiving a positioning signal, the measured position of the pole (14) being associated with the at least one measured nuclear quantity.
A method is for analyzing, using a detector of alpha particles, a sample comprising at least one radionuclide emitter of a plurality of alpha particles. The detector comprises a detection medium and a plurality of measurement cells suitable for measuring at least one incident signal generated by an interaction of the alpha particle with said detection medium. The detector is designed to provide an autoradiographic image of said sample. The method comprises a step for determining (E1) an initial energy of each alpha particle. The step comprises repeating three sub-steps: determining (D1) a position of a first interaction of an alpha particle with the detection medium, determining (D2) an energy deposited by the particle in the interior of the detector and determining (D3) the initial energy of the alpha particle. The method then comprises constructing an energy spectrum for one zone of the autoradiographic image.
The operating method comprises a routine phase implemented at the end of life of a block (3) of cells (5) of a mine, during which the following operations are carried out: - collecting the leachate produced by at least one cell (5) being recycled in the block (3), the leachate forming the recycled leachate; - injecting the recycled leachate into at least one cell (5) of the block (3).
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
Inventeur(s)
Marchais, Thomas
Perot, Bertrand
Carasco, Cédric
Ma, Jean-Luc
Toubon, Hervé
Goupillou, Romain
Abrégé
The invention relates to a method for assessing the mass concentration of uranium in a sample of uranium-bearing material by gamma spectrometry, comprising the following steps: a) acquiring (200) an energy spectrum of gamma radiation from the sample using a scintillator detector, the energy spectrum (100) comprising at least a first energy band (110) between 87 keV and 110 keV, and a second energy band (120) between 560 keV and 660 keV, the second energy band comprising at least one energy line (130) at 609 keV from 214U0UU0U0) and the corrective coefficient (K).
The operating facility (1) comprises: - a supply manifold (9) for supplying leach liquor to the injector wellheads (3); - a production manifold (15), configured to discharge leachate to a leachate treatment plant (17); - a treatment manifold (19); - a facility (20) for providing a treatment solution, configured to inject the treatment solution into the treatment manifold (19) and/or into the supply manifold (9); - for each producing well, a tubing (21) equipped with a production cut-off device (25) and a treatment pipe (23) equipped with a treatment cut-off device (27), fluidically connecting the corresponding production wellhead (5) in parallel, respectively, to the production manifold (15) and to the treatment manifold (19).
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
Inventeur(s)
Cuer, Frédéric
Marbet, Manon
Marie, Cécile
Abrégé
8 saturated or unsaturated, linear or branched hydrocarbon group; the cross-linking polymerisation being carried out in the presence of a cross-linking agent and one or more pore-forming agents.
C22B 60/02 - Obtention du thorium, de l'uranium ou des autres actinides
C02F 1/28 - Traitement de l'eau, des eaux résiduaires ou des eaux d'égout par absorption ou adsorption
C08J 9/26 - Mise en œuvre de substances macromoléculaires pour produire des matériaux ou objets poreux ou alvéolairesLeur post-traitement par élimination d'une phase solide d'un objet ou d'une composition macromoléculaire, p. ex. par lessivage
The invention relates to a method for assessing the mass concentration of uranium in a material containing uranium (16) by gamma spectrometry. The method comprises the following steps: a) measuring (600) a gamma radiation energy spectrum of the material using a detector, said energy spectrum including at least a 92 keV energy line and a 98 keV energy line, each line having a net area; b) assessing (610) by calculating a magnitude characterising the mass concentration of uranium in the material using the net area of the 92 keV energy line and the net area of the 98 keV energy line of the measured energy spectrum.
The invention relates to a method for separating colloidal zirconium hydroxide contained in an acid aqueous suspension with a pH of more than 3, comprising a step a) in which the aqueous suspension is subjected to a solid/liquid separation on a support in the presence of calcium sulfate, thereby obtaining an acid liquor containing pure zirconium and a solid phase containing calcium sulfate and zirconium hydroxide.
The invention relates to a method for analysing, using a detector of alpha particles, a sample comprising at least one radionuclide emitter of a plurality of alpha particles. The detector comprises a detection medium and a plurality of measurement cells suitable for measuring at least one incident signal generated by an interaction of an alpha particle with said detection medium. The detector is designed to deliver an autoradiographic image of said sample. The method comprises a step (E1) of determining an initial energy of each alpha particle. Said step comprises repeating three substeps: determining (D1) a position of a first interaction of an alpha particle with the detection medium, determining (D2) an energy deposited by the particle in the interior of the detector and determining (D3) the initial energy of the alpha particle. The method then comprises constructing an energy spectrum for one zone of the autoradiographic image.
G01T 1/29 - Mesure effectuée sur des faisceaux de radiations, p. ex. sur la position ou la section du faisceauMesure de la distribution spatiale de radiations
G01T 1/36 - Mesure de la distribution spectrale des rayons X ou d'une radiation nucléaire
29.
BIFUNCTIONAL COMPOUNDS CONTAINING THIOPHOSPHINE FUNCTION, OF USE AS EXTRACTANTS OF URANIUM(VI), PROCESSES FOR THE SYNTHESIS THEREOF AND USES THEREOF
The invention relates to bifunctional compounds which have a thiophosphine function and which are capable of highly effectively extracting uranium(VI) from an aqueous solution of phosphoric acid, and do so with a high selectivity with respect to iron. These compounds correspond to the general formula (I): wherein R1and R22 1616 alkyl group; R31 1515 alkyl group; Z represents O or S; and R41 1616 alkyl group, or a monocyclic heteroaromatic or aromatic group. The invention also relates to processes making it possible to synthesize these compounds, to the uses thereof as extractants of uranium(VI) and especially for extracting uranium(VI) from an aqueous solution of phosphoric acid such as a solution resulting from the attack of a natural phosphate by sulfuric acid, and also to a process making it possible to recover the uranium(VI) present in an aqueous solution of phosphoric acid resulting from the attack of a natural phosphate by sulfuric acid.
C07F 9/53 - Oxydes des organo-phospinesSulfures des organo-phosphines
C22B 3/26 - Traitement ou purification de solutions, p. ex. de solutions obtenues par lixiviation par extraction liquide-liquide utilisant des composés organiques
C22B 60/02 - Obtention du thorium, de l'uranium ou des autres actinides
30.
MESOPOROUS ORGANIC MATERIAL, USEFUL IN PARTICULAR FOR EXTRACTING URANIUM(VI) FROM AQUEOUS MEDIA INCLUDING PHOSPHORIC ACID, AND USES THEREOF
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
Inventeur(s)
Cuer, Frédéric
Marbet, Manon
Marie, Cécile
Abrégé
The invention relates to a mesoporous organic material which makes it possible to extract, using the liquid-solid extraction technique, the uranium(VI) contained in an aqueous medium including phosphoric acid, with high efficiency and high selectivity for the iron that said medium can likewise contain. The invention also relates to the uses of said material. The material is likely to be obtained by cross-linking polymerisation of a monomer of formula (I) below, wherein: R1, R2 and R3 are, independently from one another, H, a C1 to C12 saturated or unsaturated, linear or branched hydrocarbon group, or a polymerisable group, with the condition that at least one of R1, R2 and R3 is a polymerisable group; R4 and R5 are, independently from one another, H or a C1 to C8 saturated or unsaturated, linear or branched hydrocarbon group; the cross-linking polymerisation being carried out in the presence of a cross-linking agent and one or more pore-forming agents. The invention can be used in the treatment of natural phosphates with a view to recovering the uranium(VI) contained in these phosphates.
C08F 230/02 - Copolymères de composés contenant un ou plusieurs radicaux aliphatiques non saturés, chaque radical ne contenant qu'une seule liaison double carbone-carbone et contenant du phosphore, du sélénium, du tellure ou un métal contenant du phosphore
C08F 283/06 - Composés macromoléculaires obtenus par polymérisation de monomères sur des polymères prévus par la sous-classe sur des polyéthers, des polyoxyméthylènes ou des polyacétals
C22B 60/02 - Obtention du thorium, de l'uranium ou des autres actinides
C08J 9/26 - Mise en œuvre de substances macromoléculaires pour produire des matériaux ou objets poreux ou alvéolairesLeur post-traitement par élimination d'une phase solide d'un objet ou d'une composition macromoléculaire, p. ex. par lessivage
The invention relates to a method for extracting uranium (VI) from an aqueous solution including phosphoric acid, which includes placing the aqueous solution in contact with an organic material, followed by separating the aqueous solution and the organic material. Said organic material includes a solid polymer substrate impregnated with a compound having the following general formula (I): wherein: m = 0, 1 or 2; R1 and R2 = a saturated or unsaturated, straight or branched C6 to C12 hydrocarbon group; R3 = H; a saturated or unsaturated, straight or branched C1 to C12 hydrocarbon group; a saturated or unsaturated C3 to C8 hydrocarbon group including one or more cycles; or an aryl group including one or more cycles; or else R2 and R3 together form a -(CH2)n- group wherein n = 1 to 4; R4 = a saturated or unsaturated, straight or branched C2 to C8 hydrocarbon group; a saturated or unsaturated hydrocarbon group including one or more cycles; or an aromatic group including one or more cycles; and R5 = H or a saturated or unsaturated, straight or branched C1 to C12 hydrocarbon group. The invention also relates to a method for retrieving uranium (VI) from an aqueous solution including phosphoric acid.
C22B 60/00 - Obtention des métaux ayant un nombre atomique de 87 ou plus, c.-à-d. métaux radioactifs
32.
NOVEL ORGANIC MATERIAL FOR EXTRACTING THE URANIUM FROM AN AQUEOUS SOLUTION OF PHOSPHORIC ACID, ASSOCIATED METHODS FOR EXTRACTING AND RETRIEVING THE URANIUM AND A PRECURSOR OF SUCH AN ORGANIC MATERIAL
The invention relates to an organic material which includes a solid polymer substrate onto which molecules having the following general formula (I) are grafted: Formula (I) in which: m = 0, 1 or 2; R1 and R2 = a saturated or unsaturated, straight or branched C6 to C12 hydrocarbon group; R3 = H; a saturated or unsaturated, straight or branched C1 to C12 hydrocarbon group; a saturated or unsaturated C3 to C8 hydrocarbon group including one or more cycles; or an aryl group including one or more cycles; or else R2 and R3 together form a -(CH 2)n- group wherein n = 1 to 4; R4 = a saturated or unsaturated, straight or branched C2 to C8 hydrocarbon group; a saturated or unsaturated hydrocarbon group including one or more cycles; or an aromatic group including one or more cycles; and R5 = a saturated or unsaturated, straight or branched C1 to C12 hydrocarbon group; a saturated or unsaturated hydrocarbon group including one or more cycles; or a hydrocarbon group including an aryl group made up of one or more cycles, R5 being connected to at least one group G, in turn connected to the solid polymer substrate by at least one covalent bond (shown by the dotted line) and selected from an amide, alkenyl, alkynyl, amine, thioether, ether-oxide or 1,2,3-triazole group. The invention also relates to the use of the organic material to extract the uranium (VI) from an aqueous acid solution, to associated methods for extracting and retrieving uranium (VI) as well as to a molecule which is a precursor of the organic material.
C08F 8/40 - Introduction d'atomes de phosphore ou de groupes contenant du phosphore
C08F 10/00 - Homopolymères ou copolymères d'hydrocarbures aliphatiques non saturés contenant une seule liaison double carbone-carbone
C08F 12/00 - Homopolymères ou copolymères de composés contenant un ou plusieurs radicaux aliphatiques non saturés, chaque radical ne contenant qu'une seule double liaison carbone-carbone et l'un au moins étant terminé par un noyau carbocyclique aromatique
C08F 20/18 - Esters des alcools ou des phénols monohydriques des phénols ou des alcools contenant plusieurs atomes de carbone avec l'acide acrylique ou l'acide méthacrylique
B01J 45/00 - Échange d'ions dans lequel se forme un complexe ou un chélateUtilisation d'une substance comme échangeur d'ions formant des complexes ou des chélatesTraitement d'une substance en vue d'améliorer ses propriétés d'échange d'ions formant des complexes ou des chélates
C22B 60/02 - Obtention du thorium, de l'uranium ou des autres actinides
C22B 3/24 - Traitement ou purification de solutions, p. ex. de solutions obtenues par lixiviation par des procédés physiques, p. ex. par filtration, par des moyens magnétiques par adsorption sur des substances solides, p. ex. par extraction avec des résines solides