F28D 20/00 - Appareils ou ensembles fonctionnels d'accumulation de chaleur en généralAppareils échangeurs de chaleur de régénération non couverts par les groupes ou
2.
SOLID MATERIAL HAVING AN OPEN MULTIPLE POROSITY, COMPRISING A GEOPOLYMER AND SOLID PARTICLES, AND METHOD FOR THE PREPARATION THEREOF
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
ORANO CYCLE (France)
Inventeur(s)
Gossard, Alban
Grandjean, Agnès
Lambertin, David
Fabregue, Nicolas
Abrégé
The invention relates to solid material which has an open multiple porosity and is at least partially interconnected, comprising an inorganic matrix made of a microporous and mesoporous geopolymer, in which at least partially interconnected open macropores are provided which are delimited by partitions or walls made of a microporous and mesoporous geopolymer, and comprising particles of at least one solid compound different from the geopolymer, which are distributed in the macropores and/or in the partitions or walls. A method for the preparation of said material is also disclosed. The invention also relates to a method for separating at least one metal or metalloid cation from a liquid medium containing same, wherein said liquid medium is brought into contact with said material.
B01J 20/28 - Compositions absorbantes ou adsorbantes solides ou compositions facilitant la filtrationAbsorbants ou adsorbants pour la chromatographieProcédés pour leur préparation, régénération ou réactivation caractérisées par leur forme ou leurs propriétés physiques
B01J 20/30 - Procédés de préparation, de régénération ou de réactivation
C02F 1/28 - Traitement de l'eau, des eaux résiduaires ou des eaux d'égout par absorption ou adsorption
C04B 28/00 - Compositions pour mortiers, béton ou pierre artificielle, contenant des liants inorganiques ou contenant le produit de réaction d'un liant inorganique et d'un liant organique, p. ex. contenant des ciments de polycarboxylates
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
ORANO CYCLE (France)
Inventeur(s)
Broussard, Sylvain
Costenoble, Sylvain
Lengrand, Fabien
Sinot, Johann
Abrégé
The invention relates to methods for determining the acidity of an acidic aqueous solution. These methods allow measurement of the total acidity of an aqueous solution comprising a strong acid or a mixture of strong acids and, if this solution contains one or more hydrolysable cations, also allow the free acidity thereof to be measured. Applications: any industrial field and any field of scientific research in which it may be desirable to measure the total acidity or the free acidity of aqueous solutions of strong acids.
G01N 21/77 - Systèmes dans lesquels le matériau est soumis à une réaction chimique, le progrès ou le résultat de la réaction étant analysé en observant l'effet sur un réactif chimique
4.
THIOSULFATES FOR USE AS RETARDERS FOR MAGNESIUM PHOSPHATE CEMENT PASTES
The invention relates to the use of a thiosulfate as a retarder for a cement paste comprising a magnesium phosphate cement. Applies to: civil engineering.
C04B 28/34 - Compositions pour mortiers, béton ou pierre artificielle, contenant des liants inorganiques ou contenant le produit de réaction d'un liant inorganique et d'un liant organique, p. ex. contenant des ciments de polycarboxylates contenant des liants phosphate froids
39 - Services de transport, emballage et entreposage; organisation de voyages
40 - Traitement de matériaux; recyclage, purification de l'air et traitement de l'eau
Produits et services
Logistics services regarding transport of nuclear fuels and
waste; storage of nuclear waste at a centralized site. Treatment of nuclear fuels, including treatment of nuclear
fuel assemblies, differentiated treatment of nuclear fuels
according to the composition of the nuclear fuel assemblies,
separation of materials and elements constituting the
nuclear fuel assemblies into recoverable, recyclable or
reusable materials and elements on the one hand and
non-recoverable materials and elements considered as waste
on the other hand; characterization, treatment and return of
waste including a differentiated treatment according to the
composition of solid, liquid or gaseous nuclear waste and
treatment thereof to immobilize them and pack them in the
form of packages for storage or disposal thereof.
6.
METHOD FOR CONDITIONING AN ACID WASTE BY CEMENTATION
INSTITUT FRANÇAIS DES SCIENCES ET TECHNOLOGIES DES TRANSPORTS,DE L'AMÉNAGEMENT ET DES RÉSEAUX (France)
Inventeur(s)
Stefan, Lavinia
Chaussadent, Thierry
Le Rouzic, Mathieu
Abrégé
The invention relates to a method for conditioning an acid waste by cementation, wherein the acid waste is chosen among liquids of pH less than or equal to 4, semi-liquids of pH less than or equal to 4, solids for which partial or total dissolving in water leads to a solution or a suspension of pH less than or equal to 4, and mixtures thereof, which method comprises the steps of: a) preparing a cement paste having as components at least: a phosphomagnesium cement and the acid waste, and b) curing the cement paste thus obtained, and is characterised in that in step a), the cement paste is prepared without the acid waste having been subjected beforehand to a treatment consisting of lowering its acidity. The invention is applicable for conditioning any acid waste whatever its origin and, more specifically, acid waste produced in the nuclear industry.
B09B 3/00 - Destruction de déchets solides ou transformation de déchets solides en quelque chose d'utile ou d'inoffensif
C04B 28/34 - Compositions pour mortiers, béton ou pierre artificielle, contenant des liants inorganiques ou contenant le produit de réaction d'un liant inorganique et d'un liant organique, p. ex. contenant des ciments de polycarboxylates contenant des liants phosphate froids
G21F 9/16 - Traitements par fixation dans un milieu solide stable
7.
FRAME FOR EYE WEAR PROVIDING IMPROVED PROTECTION AGAINST IONIZING RADIATION AND RADIO PROTECTIVE EYEWEAR COMPRISING SUCH A FRAME
The invention relates to a frame (20) for eyewear for protecting against ionizing radiation, comprising a frontal portion (30) extending laterally by the two lateral protective elements (50), and a device (60) for maintaining the frame on the face of a user under the conditions under which it is worn, and characterized in that the lateral protective elements are integrally formed with the frontal portion and in that the frontal portion and the lateral protective elements are made of a radio-attenuation material. The invention also relates to eyewear (10) for protecting against ionizing radiation comprising such a frame and to an assembly comprising this eyewear and a device for distributing weight. Applications: protection of individuals liable to be exposed to ionizing radiation in the exercise of their professional activity.
The invention relates to a method of determining a quantity of a first radioisotope in a source term, disintegrating into a second radioisotope, the radioisotopes respectively emitting first and second gamma rays screened by the source term, the method comprising the steps: a) determining the theoretical ratio of counts between the first and second rays emitted in the absence of screening; b) measuring the net counts associated with the first and second rays emitted by the first and second radioisotopes; c) determining the screening rates of the first and second rays by the source term based on the ratio obtained in step a) and the counts obtained in step b); d) determining the quantity of the first radioisotope based on the screening rate of either the first or the second ray determined in step c).
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
Inventeur(s)
Poncelet, François
Vigier, Nicolas
Arab-Chapelet, Bénédicte
Gauthe, Aurélie
Welcomme, Eléonore
Noire, Marie-Hélène
Abrégé
382221+21+21+2 into an aqueous phase and a solid phase comprising the particles of uranium(IV) oxalate and the particles of plutonium(IV) oxalate; and d) calcining the solid phase to convert (1) the particles of uranium(IV) oxalate to particles of triuranium octoxide and (2) the particles of plutonium(IV) oxalate to particles of plutonium(IV) dioxide, whereby the powder is obtained; and and in that steps b) and c) are performed simultaneously or successively. Applications: fabrication of nuclear fuels of MOX type, e.g. for LWR or FNR reactors.
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
ORANO CYCLE (France)
ELECTRICITE DE FRANCE (France)
Inventeur(s)
Marie, Cécile
Berger, Clémence
Mossand, Guillaume
Russello, Emilie
Andreiadis, Eugen
Guillaumont, Dominique
Miguirditchian, Manuel
Sorel, Christian
Abrégé
The invention relates to the use of ureas as extractants for fully or partially separating uranium(VI) from plutonium(IV) in an aqueous solution obtained by dissolving a spent nuclear fuel in nitric acid, by means of liquid-liquid extraction, without carrying out any reduction of the plutonium(IV) to plutonium(III). The invention also relates to new ureas. Uses are the processing of spent nuclear fuels based on uranium (especially uranium oxides - UOX) or uranium and plutonium (especially mixed uranium and plutonium oxides - MOX).
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
ORANO CYCLE (France)
Inventeur(s)
Vaudez, Stéphane
Brothier, Méryl
Robisson, Anne Charlotte
Chambon, Cébastien
Abrégé
The invention relates to a process for preparing pellets of a dense mixed fuel comprising uranium dioxide UO2, plutonium oxide PuO2 and optionally at least one oxide of minor actinide(s) or of a fuel comprising a solid solution of uranium dioxide, plutonium and optionally at least one minor actinide successively comprising the following steps: a) a step of co-micronization of a mixture of powders comprising a powder of uranium oxide(s), of which all or some of this powder consists of triuranium octoxide U3O8, a powder of plutonium oxide PuO2 and optionally a powder of oxide(s) of minor actinide(s); b) a step of compacting the mixture of powders in the form of pellets; c) a step of sintering the pellets obtained in b).
The invention relates to a containment airlock (1), in particular an airlock for intervention on a site likely to be contaminated with radiation, asbestos and biological and/or chemical agents. The containment airlock (1) comprises a self-supporting frame (3) and a flexible containment shell (5). The shell (5) is configured to be assembled with the frame (3). The frame (3) is articulated so as to be extensible between a folded storage position and an extended intervention position. The frame (3) comprises articulated reinforcement rods (7). The articulated reinforcement rods (7) comprise rigid segments (72, 74) and at least one intermediate articulation (8) connecting the segments (72, 74).
E04H 1/12 - Petits bâtiments ou autres constructions pour occupation limitée, élevés en plein air ou aménagés à l'intérieur de bâtiments, p. ex. kiosques, abris pour arrêts d'autobus ou pour stations de distribution d'essence, toits pour quais de gare, guérites de gardien ou cabines de bains
E04H 15/48 - Moyens de support, p. ex. armatures repliables, p. ex. du type démontable pliables, c.-à-d. avec des charnières ou des gonds
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
Orano Cycle (France)
ELECTRICITE DE FRANCE (France)
Inventeur(s)
Milanole, Gaëlle
Russello, Emilie
Marie, Cécile
Miguirditchian, Manuel
Sorel, Christian
Abrégé
The invention relates to novel dissymmetric RN,N-dialkylamides of formula (I) in which: R1 represents a linear C1 to C4 alkyl, R2 represents a linear C1 to C10 alkyl, and R3 represents a linear or branched C6 to C15 alkyl, provided that R3 is different from a n-octyl, n-decyl, n-dodecyl, 2-ethylhexyl and 2-ethyloctyl group when R1 represents a n-butyl group and R2 represents an ethyl group. The invention also relates to a method for synthesising said N,N-dialkylamides, and to the uses of same for extracting uranium and/or plutonium from an aqueous acid solution or for fully or partially separating the uranium from the plutonium contained in an aqueous acid solution and, in particular, to a solution resulting from the dissolution of spent nuclear fuel in nitric acid. The invention further relates to a method for the treatment of an aqueous solution resulting from the dissolution of spent nuclear fuel in nitric acid, which allows the uranium and the plutonium contained in said solution to be extracted, separated and decontaminated in a single cycle, without having to perform a plutonium reduction operation, and in which one of said N,N-dialkylamides or a mixture of same is used as an extractant. The invention is applicable in the treatment of spent nuclear fuel.
C07C 233/05 - Amides d'acides carboxyliques ayant des atomes de carbone de groupes carboxamide liés à des atomes d'hydrogène ou à des atomes de carbone acycliques ayant les atomes d'azote des groupes carboxamide liés à des atomes d'hydrogène ou à des atomes de carbone de radicaux hydrocarbonés non substitués avec des atomes de carbone de groupes carboxamide liés à des atomes de carbone d'un squelette carboné saturé acyclique ayant les atomes d'azote des groupes carboxamide liés à des atomes d'hydrogène ou à des atomes de carbone acycliques
C22B 60/02 - Obtention du thorium, de l'uranium ou des autres actinides
An apparatus (1) for thermal denitration of a uranyl nitrate hydrate to uranium trioxide UO3. The apparatus (1) comprises a burner (114) and a reaction chamber (110) configured to carry out thermal denitration of uranyl nitrate hydrate and to form uranium trioxide UO3 in the form of particles. The apparatus also comprises a separating chamber (120) suitable for separating UO3 particles from the gases resulting from the thermal denitration carried out in the reaction chamber (110), and at least one filter (130) configured for purifying the gases. The separating chamber (120) is a decanting chamber into which the reaction chamber (110) directly opens out. The filter (130) is capable of performing the separation at a temperature greater than or equal to 350° C. The invention also relates to use of such an apparatus, to a thermal denitration process and to UO3 particles obtained by such a process.
B01J 19/24 - Réacteurs fixes sans élément interne mobile
B01J 19/26 - Réacteurs du type à injecteur, c.-à-d. dans lesquels la distribution des réactifs de départ dans le réacteur est effectuée par introduction ou injection au moyen d'injecteurs
B01J 4/00 - Dispositifs d'alimentationDispositifs de commande d'alimentation ou d'évacuation
B01D 50/20 - Combinaisons de dispositifs couverts par les groupes et
B01D 39/20 - Autres substances filtrantes autoportantes en substance inorganique, p. ex. papier d'amiante ou substance filtrante métallique faite de fils métalliques non-tissés
B01D 45/08 - Séparation de particules dispersées dans des gaz ou des vapeurs par gravité, inertie ou force centrifuge par inertie par projection contre les diaphragmes séparateurs
B01D 49/00 - Séparation de particules dispersées dans l'air, des gaz ou des vapeurs par d'autres méthodes
SOLID NANOCOMPOSITE MATERIAL MADE FROM HEXA- OR OCTACYANOMETALLATES OF ALKALI METALS, METHOD FOR PREPARING SAME, AND METHOD FOR EXTRACTING METAL CATIONS
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
Orano Cycle (France)
Inventeur(s)
Grandjean, Agnès
Fremy, Virginie
Charlot, Alexandre
Barre, Yves
Abrégé
The invention concerns a solid nanocomposite material comprising nanoparticles of a hexacyanometallate or octacyanometallate of an alkali metal and a transition metal, of formula [Alk+ x]Mn+ [M'(CN)m] z- in which Alk is an alkali metal, x is 1 or 2, M is a transition metal, n is 2 or 3, M' is a transition metal, m is 6 or 8, z is 3 or 4, attached to at least one surface of a porous inorganic solid support, in which the nanoparticles are attached by adsorption to said at least one surface of the solid support, and in which said surface is a basic surface. The invention also concerns a method for preparing this material, and a method for extracting at least one metal cation from a liquid medium containing it, that involves bringing said liquid medium into contact with said material.
B01J 20/04 - Compositions absorbantes ou adsorbantes solides ou compositions facilitant la filtrationAbsorbants ou adsorbants pour la chromatographieProcédés pour leur préparation, régénération ou réactivation contenant une substance inorganique contenant des composés des métaux alcalins, des métaux alcalino-terreux ou du magnésium
B01J 20/28 - Compositions absorbantes ou adsorbantes solides ou compositions facilitant la filtrationAbsorbants ou adsorbants pour la chromatographieProcédés pour leur préparation, régénération ou réactivation caractérisées par leur forme ou leurs propriétés physiques
INSTITUT FRANÇAIS DES SCIENCES ET TECHNOLOGIES DES TRANSPORTS, DE L'AMÉNAGEMENT ET DES RÉSEAUX (France)
Inventeur(s)
Stefan, Lavinia
Chaussadent, Thierry
Dominique, Nadia
Abrégé
The invention relates to a process for immobilizing a mercury-containing waste, which comprises: - stabilizing the mercury of the waste by precipitating the mercury as mercury (II) sulfide; then - encapsulating the waste by cementation, the cementation comprising coating the waste in a cement paste obtained by mixing a composition comprising a powder of at least one binder chosen from hydraulic cements, alkali-activated cements and acid-activated cements, with an aqueous mixing solution, then hardening the cement paste; and which is characterized in that the precipitation of the mercury as mercury (II) sulfide is obtained by reacting the mercury with a thiosulfate in a basic aqueous medium, while stirring and in the presence of a sulfide of an alkali metal, the molar ratio of the thiosulfate to the mercury being at least equal to 1. Applications: immobilization of any mercury-containing waste regardless of the origin thereof and, in particular, of mercury-containing waste from nuclear facilities.
A62D 3/33 - Procédés pour rendre les substances chimiques nuisibles inoffensives ou moins nuisibles en effectuant un changement chimique dans les substances par réaction avec des agents chimiques par fixation chimique de la substance nuisible, p. ex. par chélation ou complexation
A62D 101/24 - Substances organiques contenant des métaux lourds
A62D 101/43 - Substances inorganiques contenant des métaux lourds à l'état lié ou libre
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
Inventeur(s)
Leturcq, Gilles
Delahaye, Thibaud
Abrégé
The invention relates to a method for dissolving nuclear fuel, in particular irradiated nuclear fuel, which comprises submerging the nuclear fuel in a nitric acid solution. According to the invention, said dissolution method also comprises mechanical crushing of the nuclear fuel, said mechanical crushing being carried out in the nitric acid solution during said submersion. The invention likewise relates to the use of a crusher provided with mechanical crushing means for carrying out such a dissolution method.
The invention relates to a sludge suction head (5) which can be used in particular in radioactive environments and comprises a screen (52), sludge comminuting means (7), and sludge diluting means (60).
E01F 3/00 - Aires d'atterrissage pour hélicoptères, p. ex. installées sur des bâtiments
E02B 3/00 - Ouvrages relatifs au contrôle ou à l'utilisation des cours d'eau, rivières, côtes ou autres emplacements maritimesÉtanchements ou joints pour travaux de génie civil en général
19.
METHOD FOR SLOWING THE DISSOLUTION OF A COMPOUND USING AN ANTI-FOAMING AGENT
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
Orano Cycle (France)
Inventeur(s)
Magnaldo, Alastair
Marc, Philippe
Olivier, Pierre
Abrégé
The present invention concerns a method for preventing, slowing or stopping the dissolution of a compound generating a gas when it is brought into contact with a dissolution solution, and doing so, optionally, with respect to the dissolution of another compound that does not generate any gas when it is brought into contact with said same dissolution solution, the method comprising the addition, to the dissolution solution, of at least one anti-foaming agent chosen from the group consisting of solid hydrophobic particles, silicone oils, polar oils and the mixtures of same.
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
Orano Cycle (France)
Inventeur(s)
Magnaldo, Alastair
Marc, Philippe
Olivier, Pierre
Abrégé
The present invention relates to a method for selective dissolution of a first solid compound present in a mixture with respect to at least one second solid compound different from said first solid compound, also present in said mixture, wherein said method comprises at least one step consisting in bringing said mixture into contact with a dissolving solution in which said first solid compound is dissolved, generating at least one gaseous compound, and in which said second solid compound is dissolved without generating any gaseous compound, said dissolving solution comprising at least one non-ionic surfactant.
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
ORANO CYCLE (France)
Inventeur(s)
Griffiths, Nina
Van Der Meeren, Anne
Abrégé
The invention relates to a method for predicting the bioavailability of a radioelement in an animal living organism following the contamination of said organism by said radioelement, said method comprising the steps of: (a) producing a gel imitating the area of contamination in said animal living organism and in which said radioelment is uniformly distributed; (b) bringing the gel produced in said step (a) into contact with a solution imitating a biological fluid associated with the area of contamination in said animal living organism, then stirring the mixture; and (c) measuring the quantity of said radioelement in said solution at a given moment t, said measurement allowing the prediction of the bioavailability of said radioelement in said animal living organism. The invention also relates to the use of such a method for identifying a molecule exhibiting chelating properties in relation to a given radioelement and/or for characterising the chelating properties of a molecule.
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
ORANO CYCLE (France)
Inventeur(s)
Heres, Xavier
Bernier, Gilles
Dinh, Binh
Pochon, Patrick
Sans, Danièle
Zekri, Elisabeth
Abrégé
The invention relates to the use of hydroxy-imine alkanoic acids including at least four carbon atoms as anti-nitrous agents in operations of reductive back-extraction of plutonium. The invention may be useful in any method for reprocessing spent nuclear fuel that includes one or more operations of reductive back-extraction of plutonium and, more particularly, in the PUREX method as implemented in modern nuclear fuel reprocessing plants, as well as in processes derived therefrom.
c) stripping the uranyl nitrate of the organic phase obtained at the end of step b), by circulating this organic phase in an apparatus, as a counter current against an aqueous phase A3.
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.
Self-priming centrifugal pumps for special impellers
consisting of a body attached to pipework and a detachable
part used especially in irradiating, toxic, or chemically
aggressive environments in industrial/in-plant atmosphere or
clean atmosphere.
27.
Device for supporting electrodes in an electrolysis installation
The invention relates to a device for supporting electrodes in an electrolysis installation, said support comprising a busbar having electrodes fastened thereto, said electrodes being disposed on either side of the busbar and extending vertically below said busbar, the busbar and said electrodes being designed to be immersed at least in part in an electrolyte that gives off one or more gaseous species of a corrosive nature. The device further comprises a protective element of carbon/carbon material placed under the busbar, the protective element being of length and width that are not less than the length and the width of the busbar.