A storage container for uranium oxide powder, comprising a drum having a central axis; an insert comprising several tubes extending in respective directions parallel to the central axis, fastened to the drum and located inside the drum; and neutron absorbing bodies housed inside the tubes.
G21F 5/015 - Récipients blindés portatifs ou transportables pour le stockage de sources radioactives, p. ex. supports de sources pour unités d'irradiationRécipients pour radio-isotopes
2.
FUEL ASSEMBLY FOR A NUCLEAR POWER PLANT, METHOD FOR ACTIVATING A MATERIAL TO BE ACTIVATED AND GRIPPER
A fuel assembly (1) for a nuclear power plant includes at least one hollow rod (9, 9a,9b, 9c). The hollow rod is a control rod guide tube (9) of the fuel assembly (1) for the control rod assembly or an instrumentation tube. Each rod (9) is adapted to be filled with one or more containers (38) filled with material to be activated. The fuel assembly further comprises a damping element (36, 36a, 36b, 36c) at the lower end (32) of the hollow rod (9, 9a,9b, 9c).
G21C 3/326 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles comprenant des éléments combustibles de différentes compositionsFaisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles comprenant, en plus des éléments combustibles, d'autres éléments en forme d'aiguille, de barre ou de tube, p. ex. barres de commande, barres de support de grilles, barres fertiles, barres à poison ou barres factices
G21C 7/103 - Ensembles de commande comportant un ou plusieurs absorbants ainsi que d'autres éléments, p. ex. combustibles ou modérateurs
G21C 7/117 - Grappes de barres de commandeStructure en araignée
G21C 7/20 - Disposition de dispositifs amortisseurs de chocs
G21C 19/105 - Dispositifs de relèvement ou d'enlèvement adaptés pour coopérer avec les éléments combustibles ou avec l'élément de commande à éléments de couplage effectuant un mouvement de serrage ou d'extension
G21C 23/00 - Dispositions dans les réacteurs pour faciliter les expériences ou l'irradiation
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p. ex. production d'isotopes radioactifs dans les réacteurs nucléaires
3.
METHOD AND MACHINE FOR TESTING A SPACER GRID OF A NUCLEAR FUEL ASSEMBLY
A test method is for testing a spacer grid of a nuclear fuel assembly comprising a bundle of nuclear fuel rods and N spacer grids distributed along the bundle of nuclear fuel rods, where N is a positive integer equal to or greater than four. The method of testing includes providing a test assembly comprising a bundle of test rods shorter than the nuclear fuel rods and three spacer grids distributed along the test rods, generating an impact on the centrally located spacer grid, and measuring and recording at least one impact parameter and/or at least one displacement of said centrally located spacer grid.
G21C 3/18 - Entretoises intérieures ou autre matériau non actif à l'intérieur de l'enveloppe, p. ex. pour compenser l'expansion des barres combustibles ou pour compenser une réactivité excessive
G21C 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p. ex. pour la consommation ou pour la contamination
4.
METHOD FOR MANUFACTURING A NUCLEAR FUEL ELEMENT AND NUCLEAR FUEL ELEMENT
A method for manufacturing a nuclear fuel element and a nuclear fuel element includes obtaining a core, the coating of the core with an anti-diffusion layer so as to obtain a coated core, the insertion of the coated core into a cladding with interposition, between the coated core and the cladding, of one or more intermediate layer(s), and the pressing of the multilayer assembly. Each intermediate layer is being made of a ductile metal alloy and/or having a conventional yield strength which differs by no more than 30% from that of the material of the cladding, an elongation at break which differs by no more than 30% from that of the material of the cladding and/or a distributed relative elongation which differs by no more than 30% from that of the material of the cladding.
G21C 21/10 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives par extrusion, filage, étirage
B32B 15/01 - Produits stratifiés composés essentiellement de métal toutes les couches étant composées exclusivement de métal
G21C 3/20 - Détails de structure à l'intérieur de l'enveloppe avec revêtement sur le combustible ou sur l'intérieur de l'enveloppeDétails de structure à l'intérieur de l'enveloppe avec une intercouche non active entre l'enveloppe et le matériau actif
5.
Ultrasound probe for inspection of a component at a temperature above 150°C and associated inspection method
An ultrasound probe for inspecting a component at a temperature above 150° C. includes a shoe that makes contact with the component and an ultrasonic transducer. The transducer includes a probe body defining an internal volume having a body length, the probe body further defining an aperture and a disc of piezoelectric material placed in the aperture, the disc having a front side making contact with the shoe, the disc having an acoustic impedance which includes between 7 MRayl and 25 MRayl and a Curie temperature above 250° C. The transducer also includes a damper fastened to the back side of the disc and extending from the back side into the internal volume for a damper length smaller than the body length.
A plate-shaped nuclear fuel element includes a core made of a fissile material and a cladding. The cladding further includes a frame defining a central aperture receiving the core and two cover plates sandwiching the frame and the core. The frame is made of a metallic first cladding material. The cover plates are made of a metallic second cladding material. The first cladding material has a hardness strictly greater than the hardness of the second cladding material.
A method for producing a granulated metal oxide powder and corresponding granulated metal oxide powder includes obtaining an initial metal oxide powder, consisting of particles of a metal oxide, by hydrolysing a chloride of the metal and forming a suspension containing the initial metal oxide powder and an organic binder suspended in a suspension medium. The method also includes drying the suspension so as to obtain granulated metal oxide powder, consisting of grains formed by agglomerates of particles of the initial metal oxide powder.
C09C 3/00 - Traitement, en général, de substances inorganiques, autres que des charges fibreuses, pour améliorer leurs propriétés de pigmentation ou de charge
A method for controlling a nuclear reactor includes acquiring current values of operating parameters of the reactor; and iteratively implementing the sub-steps of generating a sequence of injection of neutron poison and/or water; calculating an evolution in at least one magnitude characteristic of the state of the core of the nuclear reactor during this given time interval using a power program, current values of operating parameters and the injection sequence considered, the evolution being calculated using a predictive model of the core of the reactor; evaluating a cost function, using the calculated evolution; repeating the generating and calculating sub-steps until a convergence criterion of the cost function is met; and repeating the acquiring and the iteratively implementing steps with a time period less than 60 minutes.
G21C 7/22 - Commande de la réaction nucléaire par application de matériau absorbant les neutrons, c.-à-d. matériau avec section efficace d'absorption excédant largement la section efficace de réflexion par déplacement d'un matériau fluide ou fluent absorbant les neutrons
G05B 13/04 - Systèmes de commande adaptatifs, c.-à-d. systèmes se réglant eux-mêmes automatiquement pour obtenir un rendement optimal suivant un critère prédéterminé électriques impliquant l'usage de modèles ou de simulateurs
A method for detecting collision risks when moving a load includes the following steps:
attaching a plurality of proximity sensors around the lateral surface of the load;
lifting and moving the load using the lifting and moving equipment;
transmitting and displaying the signals generated by the proximity sensors on at least one display unit.
A method and system for accelerating the convergence of an iterative computation code of physical parameters of a multi-parameter system, in particular in the field of fluid dynamic computation. The method comprises obtaining first parameter values, of first dimensionality by applying the iterative computation code. The method further comprises applying a data dimensionality reduction on at least a part of the first parameter values of first dimensionality to compute representative second parameters of second dimensionality smaller than the first dimensionality; applying an extrapolation on at least a subset of the second parameters of second dimensionality to predict a set of predicted second parameter values, computing predicted first parameter values from the predicted second parameter values, and using the predicted first parameter values as an input data set for a new iterative computation with the iterative computation code.
G06F 9/50 - Allocation de ressources, p. ex. de l'unité centrale de traitement [UCT]
G06F 30/28 - Optimisation, vérification ou simulation de l’objet conçu utilisant la dynamique des fluides, p. ex. les équations de Navier-Stokes ou la dynamique des fluides numérique [DFN]
A maintenance method is applied to a nuclear reactor having at least one control assembly for controlling a rod cluster assembly including a casing for receiving a lifting mechanism and a sheath for receiving the control rod, a first lip at an upper casing end and a second lip at a sheath lower end forming an omega seal. The maintenance method includes removing the first and second lips; carrying out at least one maintenance operation on the control assembly; creating a welding surface by machining said upper casing end; creating a leak-tight welded connection by welding the welding surface and a complementary welding surface provided at the lower end of the sheath or of a replacement sheath.
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
12.
METHOD FOR MONITORING ACCESS TO A SOFTWARE OF A CONTROL SYSTEM AND MONITORING SYSTEM
G06F 21/57 - Certification ou préservation de plates-formes informatiques fiables, p. ex. démarrages ou arrêts sécurisés, suivis de version, contrôles de logiciel système, mises à jour sécurisées ou évaluation de vulnérabilité
13.
FLOATING MAINTENANCE PLATFORM FOR NUCLEAR FACILITY
A platform comprises a floor comprising beams and removable slabs supported by the beams; and a floating support, arranged to float on the water filling a pool of the nuclear facility, a peripheral edge of the floor resting on the floating support. The floating support can annular and can internally define an opening. The floor can completely close the opening.
G21C 19/02 - Détails des dispositions pour la manipulation
14.
DEVICE FOR USE IN A FUEL ASSEMBLY OF NUCLEAR POWER PLANT, METHOD FOR MANUFACTURING A DEVICE AND METHOD FOR ACTIVATING A MATERIAL IN A NUCLEAR POWER PLANT
The present disclosure relates to device for use in a fuel assembly of a nuclear power plant, the device comprises at least one rod, each rod comprises a plurality of containers having a space being filled with material to be activated, characterized in that the device further comprises a flow restrictor for a fuel assembly of a nuclear power plant comprising a plurality of fingers adapted to extend respectively into a control rod guide tube of the fuel assembly when the flow restrictor is inserted into the fuel assembly, wherein the at least one rod is connected to a finger of the flow restrictor, wherein the containers are arranged subsequently in a direction of the longitudinal axis of the respective rod.
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p. ex. production d'isotopes radioactifs dans les réacteurs nucléaires
G21C 7/103 - Ensembles de commande comportant un ou plusieurs absorbants ainsi que d'autres éléments, p. ex. combustibles ou modérateurs
15.
METHOD AND ELECTRONIC DEVICE FOR ASSISTING WITH SURVEILLANCE OF AN ELEMENT OF A NUCLEAR REACTOR, ASSOCIATED COMPUTER AND ASSOCIATED SYSTEM
A method for assisting with surveillance of an element of a nuclear reactor, said method being implemented by an electronic device, comprising the steps of training an artificial-intelligence algorithm; acquiring an image of the element; estimating, on the basis of the image and via the artificial-intelligence algorithm, whether a fault is present in the element; displaying the image of the element; and if at least one fault is estimated to be present, generating an alarm. In the estimating step, an input to the artificial-intelligence algorithm is an image of a region comprising the element, and an output is a level of confidence as regards an absence of fault in the element for said region. If the level of confidence is lower than a threshold, then a fault is estimated to be present. In the training step, only images of fault-free elements are inputted into the artificial-intelligence algorithm.
G21C 17/08 - Combinaison structurelle du cœur du réacteur ou de la structure du modérateur avec des moyens de vision, p. ex. avec des caméras de télévision, périscopes, fenêtres
A method for inspecting a plurality of elements of an industrial plant includes developing an application having a user interface with a command for each element to be inspected; repeatedly acquiring image data of the elements of the industrial plant using a mobile device, and storing the image data in an acquisition memory, each image datum comprising at least one image and a timestamp indicating a time at which the image datum was acquired; activating commands at respective activation times; and associating the image data with the elements. The image data is associated with a given element being chosen exclusively from the image data having a timestamp between the time of activation of the command corresponding to said element and the time of activation of either the preceding or the following command.
G05B 19/418 - Commande totale d'usine, c.-à-d. commande centralisée de plusieurs machines, p. ex. commande numérique directe ou distribuée [DNC], systèmes d'ateliers flexibles [FMS], systèmes de fabrication intégrés [IMS], productique [CIM]
G06F 16/58 - Recherche caractérisée par l’utilisation de métadonnées, p. ex. de métadonnées ne provenant pas du contenu ou de métadonnées générées manuellement
17.
DEVICE FOR EXTRACTING A NUCLEAR FUEL ROD OR A CLUSTER ROD AND EXTRACTION METHOD USING SUCH AN EXTRACTION DEVICE
An extraction device for extracting a nuclear fuel rod or a cluster rod comprises an attachment portion configured to be inserted into a sleeve of the rod through an end without an end plug, and a grip portion, the attachment portion comprising an elongated body along a longitudinal axis and at least one tooth projecting from the body, the or each tooth being configured to allow the attachment portion to be forcibly inserted into the sleeve axially, and to engage with the inner surface of the sleeve so as to prevent the attachment portion from being extracted from the sleeve.
G21C 19/26 - Dispositions pour enlever les éléments combustibles ou les éléments de commande grippés ou endommagésDispositions pour déplacer les parties cassées de ceux-ci
An inspection system for inspecting nuclear fuel pellets comprises a supporting device for supporting the fuel pellet(s) such that the pellet axis of each fuel pellet coincides with a reference axis, and an optical measuring device arranged for optically measuring the fuel pellet(s), the optical measuring device comprising a light emitter configured for emitting a light beam propagating along an optical axis and a light detector arranged for receiving the light beam. The fuel pellet interrupts the light beam and generates a shadow projected on the light detector. The optical measuring device includes a measuring module configured for analyzing the shadow for detecting possible defects on the end faces and/or the lateral face of each fuel pellet.
G21C 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p. ex. pour la consommation ou pour la contamination
A nuclear fuel rod comprises nuclear fuel contained in a cladding, the cladding comprising a tube and two plugs, the tube extending along a central axis and having two ends, each plug being attached to a corresponding end of the tube by sealing the end of the tube. The tube is covered by a tube coating extending over the entire length of the tube from one end of the tube to the other.
A manufacturing method provides a nuclear reactor component comprising a substrate and a coating covering a surface of the substrate. The manufacturing method comprises laser-marking a pattern on the surface of the substrate, the marking being carried out so as to form recessed reliefs outlining the pattern in the surface of the substrate, and then applying the coating to the surface of the substrate over the pattern.
A method is for manufacturing a nuclear fuel assembly (2) comprising nuclear fuel rods (4) arranged in a bundle and a skeleton (6) supporting the fuel rods (4). The method comprise the steps of inserting fuel rods (4) into the skeleton (6) to obtain a fuel assembly (2) and packaging the fuel assembly (2) in view of transportation. The steps are being performed in a same nuclear fuel assembly manufacturing plant (20), preferably in a same nuclear fuel assembly manufacturing building (60).
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceauMoyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraireMoyens de couplage de faisceaux adjacents
G21C 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p. ex. pour la consommation ou pour la contamination
A reactor (1) for hydrolysis of uranium hexafluoride comprises a tubular injector (9) comprising first (11), second (13) and third (15) concentric fluid circulation ducts intended to be connected respectively with a source of UF6, a source of inert gas and a source of water vapor. The tubular injector (9) is obtained by additive manufacturing.
B01J 4/00 - Dispositifs d'alimentationDispositifs de commande d'alimentation ou d'évacuation
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
A nuclear fuel cladding element comprises a substrate made of a material containing zirconium and a protective coating covering the substrate on the outside. The protective coating is being made of a material containing chromium, and has a columnar microstructure composed of columnar grains and having on the outer surface thereof a microdroplet density of less than 100 per mm2.
G21C 3/07 - EnveloppesChemises caractérisées par le matériau, p. ex. alliages
G21C 3/20 - Détails de structure à l'intérieur de l'enveloppe avec revêtement sur le combustible ou sur l'intérieur de l'enveloppeDétails de structure à l'intérieur de l'enveloppe avec une intercouche non active entre l'enveloppe et le matériau actif
The invention relates to a nuclear fuel cladding produced with a substrate (14), which is made of pure zirconium or of a zirconium-based alloy, and a multilayer protective coating (16), which covers a surface (14B) of the substrate (14), the protective coating (16) comprising a main layer (18) made of pure chromium and one or more additional layers (20), each additional layer (20) being made of pure chromium or from a material consisting of chromium and, additionally, oxygen and/or nitrogen, with the optional presence of unavoidable impurities.
The invention relates to a flow calming assembly (10) for a nuclear reactor comprising a vessel (12) and an enclosure (14) situated in the vessel (12) wherein a fluid circulates from the vessel (12) to the enclosure (14) at a bottom part of the vessel (12). The flow calming assembly (10) comprises an outer calming device (28) with openings for fluid passage, the outer calming device (28) comprising an upper part (34) and a lower part (36), the upper part (34) comprising a flared or conical collar extending between an upper end (38) and a lower end (40), the lower part (36) having a shape presenting a symmetry along a main axis (D), the lower part (36) extending from the lower end (40) of the upper part (34). The invention further relates to associated reactor and installing method.
A test method is for testing a spacer grid of a nuclear fuel assembly comprising a bundle of nuclear fuel rods and N spacer grids distributed along the bundle of nuclear fuel rods, where N is a positive integer equal to or greater than four. The method of testing includes providing a test assembly comprising a bundle of test rods shorter than the nuclear fuel rods and three spacer grids distributed along the test rods, generating an impact on the centrally located spacer grid, and measuring and recording at least one impact parameter and/or at least one displacement of said centrally located spacer grid.
G21C 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p. ex. pour la consommation ou pour la contamination
G21C 3/18 - Entretoises intérieures ou autre matériau non actif à l'intérieur de l'enveloppe, p. ex. pour compenser l'expansion des barres combustibles ou pour compenser une réactivité excessive
27.
PLATFORM AND PLATFORM SYSTEM FOR NUCLEAR POWER PLANT
A platform for a nuclear power plant is configured to span a pool (4) of a nuclear power plant by being movable along two parallel rails (6) arranged on either side of the pool (4). The platform comprises at least one platform module (16) having a module floor (18) defining at least part of a platform floor (14) and two guide assemblies (20) for mating with rails (6) to guide the platform along said rails (6). Each platform module is expandable to vary the spacing between the two guide assemblies (20) of the platform module (16), the two guide assemblies (20) being close together in a storage configuration and far apart in a service configuration.
A CNC machining device (1) comprises a control console (3) and a CNC machine (5). A training assembly (33) for training operation of the CNC machining device includes a training control console (35) substantially identical to the control console (3) of the CNC machining device (1); a digital twin (36) of the CNC machine (5), comprising a simulator (37) configured to simulate the effect of commands from the training control console (35) on the CNC machine (5); and a display device (39) configured for a trainee to view the current state of the simulator (37).
G09B 19/00 - Enseignement non couvert par d'autres groupes principaux de la présente sous-classe
G05B 19/4155 - Commande numérique [CN], c.-à-d. machines fonctionnant automatiquement, en particulier machines-outils, p. ex. dans un milieu de fabrication industriel, afin d'effectuer un positionnement, un mouvement ou des actions coordonnées au moyen de données d'un programme sous forme numérique caractérisée par le déroulement du programme, c.-à-d. le déroulement d'un programme de pièce ou le déroulement d'une fonction machine, p. ex. choix d'un programme
G09B 5/02 - Matériel à but éducatif à commande électrique avec présentation visuelle du sujet à étudier, p. ex. en utilisant une bande filmée
29.
Process and installation for the destruction of radioactive sodium
A radioactive sodium destruction facility includes a tank for storing liquid metallic sodium, located at a first level; a reaction vessel containing an aqueous solution; a sodium feed circuit comprising a sodium circulation member located at a second level higher than the first level, the circulation member having a suction in fluid communication with the tank and a discharge in fluid communication with the reaction vessel; an inert gas supply unit configured to supply the tank; a controller driving the sodium circulation member; and an inert gas supply unit configured to supply the tank; and a controller driving the supply unit to control a gas pressure in the tank, such that a pressure at the suction of the sodium circulation member is maintained within a predetermined range.
The plate-shaped nuclear fuel element (2) comprises a core (4) made of a fissile material and a cladding (6), the cladding comprising a frame (8) defining a central aperture (10) receiving the core (4) and two cover plates (12) sandwiching the frame (8) and the core (4), wherein the frame (8) is made of a metallic first cladding material and the cover plates (12) are made of a metallic second cladding material, the first cladding material having a hardness strictly greater than the hardness of the second cladding material.
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p. ex. production d'isotopes radioactifs dans les réacteurs nucléaires
31.
ULTRASOUND PROBE FOR INSPECTING A COMPONENT AT A TEMPERATURE ABOVE 150°C AND ASSOCIATED INSPECTING METHOD
The present invention relates to an ultrasound probe (10) for inspecting a component at a temperature above 150°C. The probe (10) comprises a shoe (14) that makes contact with the component and an ultrasonic transducer (16). The transducer comprises: - a probe body (24) defining an internal volume (30) having a body length (LC), the probe body further defining an aperture (32); - a disc (26) of piezoelectric material placed in the aperture, the disc having a front side (38) making contact with the shoe, the disc having an acoustic impedance comprised between 7 Mrayl and 25 Mrayl and a Curie temperature above 250°C; - a damper (28) fastened to the back side (40) of the disc and extending from the back side into the internal volume over a damper length (LA) smaller than the body length (LC).
B06B 1/06 - Procédés ou appareils pour produire des vibrations mécaniques de fréquence infrasonore, sonore ou ultrasonore utilisant l'énergie électrique fonctionnant par effet piézo-électrique ou par électrostriction
G01N 29/22 - Recherche ou analyse des matériaux par l'emploi d'ondes ultrasonores, sonores ou infrasonoresVisualisation de l'intérieur d'objets par transmission d'ondes ultrasonores ou sonores à travers l'objet Détails
A BWR fuel assembly is elongated along a fuel assembly axis and comprises a lower tie plate, an upper tie plate axially spaced from the lower tie plate, a bundle of fuel rods extending axially between the lower tie plate and the upper tie plate, and a tubular fuel channel extending from the lower tie plate to the upper tie plate with encasing the fuel rods. The fuel assembly comprises an interaction device mounted on the lower tie plate and configured to interact with the fuel channel. The interaction device has an inactive configuration and an active configuration.
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceauMoyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraireMoyens de couplage de faisceaux adjacents
33.
METHOD FOR PRODUCING A GRANULATED METAL OXIDE POWDER, AND CORRESPONDING GRANULATED METAL OXIDE POWDER
The invention relates to a production method which comprises the following steps: - obtaining an initial metal oxide powder, consisting of particles of a metal oxide, by hydrolysing a chloride of said metal; - forming a suspension containing the initial metal oxide powder and an organic binder suspended in a suspension medium; and - drying the suspension so as to obtain granulated metal oxide powder, consisting of grains formed of agglomerates of particles of the initial metal oxide powder.
C04B 35/48 - Produits céramiques mis en forme, caractérisés par leur compositionCompositions céramiquesTraitement de poudres de composés inorganiques préalablement à la fabrication de produits céramiques à base d'oxydes à base d'oxydes de zirconium ou d'hafnium ou de zirconates ou d'hafnates
34.
PROCESS AND INSTALLATION FOR THE DESTRUCTION OF RADIOACTIVE SODIUM
An installation is for the destruction of radioactive metallic sodium and includes a reaction vessel containing an aqueous solution, the reaction vessel having an aqueous solution outlet; a sodium feed circuit configured for feeding liquid metallic sodium into the reaction vessel; a liquid effluent treatment unit, comprising a drain tank and a drain line fluidically connecting the aqueous solution outlet to the drain tank; a gas treatment unit configured for diluting the gases and releasing the diluted gases into the atmosphere, the drain tank having a gas outlet fluidically connected to the gas treatment unit; an inert gas feed unit configured for feeding the drain tank.
G21C 1/02 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur
G21C 19/18 - Appareils pour porter les éléments combustibles à l'aire de charge du réacteur, p. ex. depuis un emplacement de stockage
G21C 19/303 - Dispositions pour introduire un matériau fluent à l'intérieur du cœur du réacteurDispositions pour enlever un matériau fluent du cœur du réacteur avec purification continue du matériau fluent en circulation, p. ex. par extraction des produits de fission spécialement adaptés pour des gaz
35.
Method of determination of a nuclear core loading pattern
A method of determination of a nuclear core loading pattern defining the disposition of fuel assemblies. The method includes defining at least one potential core loading pattern and calculating predictive bowing of the fuel assemblies at the end of the operation cycle for each potential core loading pattern. The calculation is carried out by an automatic learning algorithm trained on a training data set that includes a plurality of other core loading patterns. The set also includes, for each of the other core loading patterns, measurements of bowing of fuel assemblies at the end of operation cycle. The method also includes evaluating the at least one potential core loading pattern based on the predictive bowing calculations and at least one predetermined criteria. The method further includes selecting one of the potential core loading patterns based at least in part on the evaluating.
G21D 3/00 - Commande des installations à énergie nucléaire
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
36.
NUCLEAR FUEL ASSEMBLY BOTTOM END PART DEBRIS FILTER AND METHOD OF MANUFACTURING SUCH A DEBRIS FILTER
A nuclear fuel assembly bottom end part debris filter has an inlet face (18A) and an outlet face (18B) opposed to the inlet face (18A) and comprises a plurality of filtering structures (50) protruding on the inlet face (18A) of the debris filter (18). Each filtering structure (50) has a structure base (52) and a structure apex (54) spaced along a structure axis (A), and each filtering structure (50) includes blades (56) distributed circumferentially around the structure axis (A). Each blade has one end connected to the structure base (52) and one end connected to the structure apex (54), and each blade (56) delimits a slot (58) with each adjacent blade (56) of the same filtering structure (50).
G21C 3/32 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceauMoyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraireMoyens de couplage de faisceaux adjacents
G21C 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci
B33Y 80/00 - Produits obtenus par fabrication additive
B01D 29/03 - Filtres à éléments filtrants stationnaires pendant la filtration, p. ex. filtres à aspiration ou à pression, non couverts par les groupes Leurs éléments filtrants avec des éléments filtrants plats autoportants
B01D 29/58 - Filtres à éléments filtrants stationnaires pendant la filtration, p. ex. filtres à aspiration ou à pression, non couverts par les groupes Leurs éléments filtrants à plusieurs éléments filtrants caractérisés par leur agencement relatif montés en série disposés de façon concentrique ou coaxiale
37.
DEBRIS FILTER FOR A NUCLEAR FUEL ASSEMBLY BOTTOM END PART AND METHOD OF MANUFACTURING SUCH A DEBRIS FILTER
A debris filter configured for a nuclear fuel assembly bottom end part includes a lower nozzle (8) and the debris filter (18) is supported by the lower nozzle (8). The debris filter (18) has an inlet face (18A) and an outlet face (18B) opposed to the inlet face (18A), and comprises at least one filtering section (18D) that has a retention capacity that increases gradually or stepwise towards from the inlet face (18A) to the outlet face (18B).
A nuclear fuel assembly comprises nuclear fuel rods (4) extending along a longitudinal axis (L) and a support skeleton (6) configured to support the nuclear fuel rods (4). The support skeleton (6) includes two end pieces (8, 10), a plurality of guide tubes (12) connecting the end pieces (8, 10) to each other, and spacer grids (14) attached to the guide tubes (12), with each spacer grid (14) supporting the nuclear fuel rods (4). The nuclear fuel assembly further includes at least one reinforcement device (20) comprising at least one reinforcement plate (22) which is in contact with at least two of the guide tubes (12) and attached to one or more of the guide tubes (12) at attachment points (21). Each reinforcement plate (22) has at least two attachment points (21) that are offset relative to each other along the longitudinal axis (L).
The invention relates to a method comprising the following steps: - attaching a plurality of proximity sensors (11) around the side surface of the load (3); - lifting and moving the load (3) using the lifting and moving device (7); - transmitting and displaying the signals generated by the proximity sensors (11) on at least one display device (15).
A tubular component for a pressurised-water nuclear reactor, has the following composition by weight:
0.8%≤Nb≤2.8%;
traces≤Sn≤0.65%;
0.015%≤Fe≤0.40%; preferably 0.020%≤Fe≤0.35%;
traces≤C≤100 ppm;
600 ppm≤O≤2300 ppm; preferably 900 ppm≤O≤1800 ppm;
5 ppm≤S≤100 ppm; preferably 8 ppm≤S≤35 ppm;
traces≤Cr+V+Mo+Cu≤0.35%;
traces≤Hf≤100 ppm;
F≤1 ppm;
the remainder being zirconium and impurities resulting from production. The tubular component has an outer surface with a roughness Ra less than or equal to 0.5 μm, obtained following a final mechanical polishing step. The outer surface has a roughness Rsk≤1 in absolute value and a roughness Rku≤10.
The invention concerns a method and system for accelerating the convergence of an iterative computation code of physical parameters of a multi- parameter system, in particular in the field of fluid dynamic computation. The method comprises obtaining (12,14) first parameter values, of first dimensionality by applying the iterative computation code. The method further comprises applying (18) a data dimensionality reduction on at least a part of the first parameter values of first dimensionality to compute representative second parameters of second dimensionality smaller than the first dimensionality; applying (20) an extrapolation on at least a subset of the second parameters of second dimensionality to predict a set of predicted second parameter values, computing (22) predicted first parameter values from the predicted second parameter values, and using the predicted first parameter values as an input data set for a new iterative computation with the iterative computation code.
G06F 17/11 - Opérations mathématiques complexes pour la résolution d'équations
G06F 30/28 - Optimisation, vérification ou simulation de l’objet conçu utilisant la dynamique des fluides, p. ex. les équations de Navier-Stokes ou la dynamique des fluides numérique [DFN]
42.
Method and system for using computational resources of a multiprocessor computing system
A system (1) includes a module (30) for calculating a design of experiment comprising a plurality of software tasks to be performed in order to solve a predetermined physical problem. The software tasks of the design of experiment have a first priority level. The system also includes a module (4) for scheduling the execution of software tasks by the computing system, configured to check for the presence of at least one software task with a second priority level higher than the first priority level waiting to be executed; in case of the presence of at least one such software task, obtaining freed-up computational resources for executing said at least one software task of a second priority level; in the absence of at least one such software task, allocate at least some of the software tasks of the first priority level to the available computational resources.
The inspection system comprises a supporting device (20) for supporting the fuel pellet(s) (4) such that the pellet axis (A) of each fuel pellet (4) coincides with a reference axis (B), and an optical measuring device (40) arranged for optically measuring the fuel pellet(s) (4), the optical measuring device (40) comprising a light emitter (42) configured for emitting a light beam propagating along an optical axis (C) and a light detector (46) arranged for receiving the light beam (44), wherein each fuel pellet (4) interrupts the light beam (44) and generates a shadow projected on the light detector (46), the optical measuring device (40) comprising a measuring module (48) configured for analyzing the shadow for detecting possible defects on the end faces (10) and/or the lateral face (8) of each fuel pellet (4).
The nuclear fuel rod comprises nuclear fuel contained in a cladding (4), the cladding (4) comprising a tube (6) and two end caps (8), the tube (6) extending along a central axis (A) and having two ends, each end cap (8) being fastened to a respective end of the tube (6), sealingly closing this end. The tube (6) is covered by a tube coating (16) extending over the entire length of the tube (16), from one end of the tube (6) to the other.
The method comprises the following steps:
acquisition of a plurality of quantities characterizing the operation of the nuclear reactor;
calculation of at least one critical thermal flux ratio using a deep neural network, the entries of the deep neural network being determined by using the acquired quantities, the deep neural network comprising at least two hidden layers of at least five neurons each;
calculation of the deviations between the at least one calculated critical thermal flux ratio and a plurality of predetermined reference threshold values;
formulation of a control signal for a reactor control system by using the calculated deviations, the control signal being:
automatic reactor shutdown or alarm;
do nothing;
emergency shutdown of the nuclear reactor or emission of an alarm signal if relevant.
K) of the corrective values of the commands produced by the regulator (33); and regulation of the operating parameters of the nuclear reactor, by controlling actuators using the vector (U) of the corrected values of the controls.
G21D 3/10 - Régulation de différents paramètres dans l'installation par une combinaison d'une variable dérivée du flux de neutrons avec d'autres variables de commande, p. ex. dérivées de la température, du flux du réfrigérant, de la pression
G21D 3/00 - Commande des installations à énergie nucléaire
A nuclear fuel assembly for a boiling water reactor extends along a fuel assembly axis and includes a base including a lower tie plate, a head including an upper tie plate and a lift handle, a bundle of fuel rods extending axially between the lower tie plate and the upper tie plate, and a water channel extending within the bundle of fuel rods with axially connecting the base to the head such that the load of the base is transferred to the head via the water channel. The fuel assembly further comprises a tie rod extending between the base and the head. The tie rod is axially fixed to the base and connected to the head via a connection assembly comprising a stopping member configured to abut an abutting surface of the head for limiting a downward movement of the base relative to the head during lifting of the fuel assembly, in case of a breakage of the water channel.
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceauMoyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraireMoyens de couplage de faisceaux adjacents
G21C 3/32 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles
G21C 3/322 - Moyens pour influencer l'écoulement du réfrigérant à travers ou autour des faisceaux
G21C 3/328 - Disposition relative des éléments dans le réseau
48.
Welding torch and corresponding manufacturing method
A welding torch includes a head (3) having a body (11) bearing an electrode (13); an electric power source (27); and a filler metal wire (17) and a wire guide (19) guiding the filler metal wire (17) to the electrode (13). The body (11) is obtained by additive manufacturing from an electrically conductive metal, and the electrode (13) is electrically connected to the electric power source (27) by the metal constituting the body (11). The wire guide (19) includes an insulating sheath (29) inside which the filler metal wire (17) moves, and the filler metal wire (17) is electrically insulated from the potential of the body (11) by the insulating sheath (29).
B23K 9/028 - Soudage de joints continusSupportsPièces rapportées pour des joints curvilignes situés dans un plan
B22F 5/10 - Fabrication de pièces ou d'objets à partir de poudres métalliques caractérisée par la forme particulière du produit à réaliser d'articles avec des cavités ou des trous, non prévue dans les sous-groupes précédents
B23K 9/167 - Soudage ou découpage à l'arc utilisant des gaz de protection et une électrode non consommable
B23K 9/173 - Soudage ou découpage à l'arc utilisant des gaz de protection et une électrode consommable
B23K 9/29 - Dispositifs de support adaptés pour servir de moyens de protection
A method comprises inserting the fuel rod (4) through the spacer grids (14) aligned along an assembling axis (A) with passing the fuel rod (4) through a lubrication chamber (30) aligned with the spacer grids (14) such that the lubrication chamber (30) is passed through by the fuel rod (4) before the insertion of the fuel rod (4) through one of the spacer grids (14), and circulating a lubrication fluid containing a gas and a lubricant in gaseous phase and/or mist form in the lubrication chamber (30). The lubrication fluid is injected in the lubrication chamber (30) at a temperature strictly higher than ambient temperature, such that lubricant deposits or condensates in liquid phase with forming a lubricant film on an external surface of the fuel rod (4) that is being inserted through said one of the spacer grids (14).
F16N 15/00 - Lubrification avec des substances autres que l'huile ou la graisseLubrification caractérisée par l'utilisation de lubrifiants particuliers dans des appareils particuliers ou dans des conditions particulières
A method for protecting a nuclear reactor includes reconstructing a maximum linear power density released among the fuel rods of the nuclear fuel assemblies of the core; calculating the thermomechanical state and the burnup fraction of the rods; calculating a mechanical stress or deformation energy density in the cladding of one of the rods by using the said reconstructed maximum linear power density, the calculated thermomechanical states and the calculated burnup fractions, by means of a meta-model of a thermomechanical code; comparing the calculated mechanical stress or the calculated deformation energy density with a respective threshold; and stopping the nuclear reactor if the calculated mechanical stress or the calculated deformation energy density exceeds the respective threshold.
The nuclear fuel cladding element comprises a substrate (16) made of a material based on zirconium and a protective coating (18) externally covering the substrate (16), the protective coating (18) being made of a material based on chromium, and having a columnar microstructure composed of columnar grains (20) and having on its outer surface (18B) a microdroplet density of less than 100 per mm2.
An operating facility (1) for operating a mine by in-situ leaching comprises a supply manifold (9) for supplying leach liquor to the injector well heads (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); and for each producing well, a production pipe (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 producing well head (5) in parallel, respectively, to the production manifold (15) and to the treatment manifold (19).
E21B 43/28 - Dissolution de matières minérales autres que des hydrocarbures, p. ex. par un agent de lessivage alcalin ou acide
E21B 33/068 - Têtes de puitsLeur mise en place comportant des dispositions pour introduire des objets dans les puits ou pour les en retirer, ou pour y introduire des fluides
53.
Method and facility for converting uranium hexafluoride into uranium dioxide
6 supplied to the reactor (4) is between 75 and 130 kg/h, the hourly mass flowrate of dry water vapour supplied to the reactor (4) for hydrolysis is between 15 and 30 kg/h, and the temperature inside the reactor (4) is between 150 and 250° C.
B01J 4/00 - Dispositifs d'alimentationDispositifs de commande d'alimentation ou d'évacuation
B01J 12/00 - Procédés chimiques généraux faisant réagir des milieux gazeux avec des milieux gazeuxAppareillage spécialement adapté à cet effet
B01J 12/02 - Procédés chimiques généraux faisant réagir des milieux gazeux avec des milieux gazeuxAppareillage spécialement adapté à cet effet pour l'obtention d'au moins un produit de réaction solide à la température ambiante
B01J 19/24 - Réacteurs fixes sans élément interne mobile
B01J 12/02 - Procédés chimiques généraux faisant réagir des milieux gazeux avec des milieux gazeuxAppareillage spécialement adapté à cet effet pour l'obtention d'au moins un produit de réaction solide à la température ambiante
B01J 19/00 - Procédés chimiques, physiques ou physico-chimiques en généralAppareils appropriés
C01B 13/22 - Méthodes de préparation des oxydes ou hydroxydes en général par oxydation d'éléments à l'état gazeuxMéthodes de préparation des oxydes ou hydroxydes en général par oxydation ou hydrolyse de composés à l'état gazeux d'halogénures ou d'oxyhalogénures
55.
INSTALLATION AND METHOD FOR CONVERTING URANIUM HEXAFLUORIDE TO URANIUM DIOXIDE
An installation for the conversion of uranium hexafluoride (UF6) to uranium dioxide (UO2) comprises a hydrolysis reactor (4) for the conversion of UF6 into uranium oxyfluoride powder (UO2F2), a pyrohydrolysis furnace (6) for converting the UO2F2 powder supplied by the reactor (4) into UO2 powder, a supply device (8) comprising reagent injection ducts (10) for the injection of UF6, water vapor or H2, and a control system (16) designed to control the supply device (8) so as to supply at least one of the reagent injection ducts (10) with a neutral gas during a shut-down or start-up phase of the conversion installation.
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
A nuclear reactor includes guide tubes; and vessel head penetrations each comprising a tubular adapter fixed in one of the openings and defining an inner passage. Each vessel head penetration also includes a tubular sleeve engaged in the inner passage and axially extending in line with one of the guide tubes. Each sleeve is suspended by an upper axial sleeve end lying on an upper range on the corresponding adapter. A lower axial end of the sleeve projects axially into the vessel beyond the adapter and is separated from an upper axial end of the corresponding guide tube by an axial gap having an axial height of less than 50 millimeters.
G21C 13/036 - Raccords entre le tube et la paroi d'une enceinte, p. ex. tenant compte des contraintes thermiques le tube traversant la paroi, c.-à-d. s'étendant de chaque côté
G21C 7/16 - Aménagements de conduite hydrauliques ou pneumatiques
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
57.
METHOD AND FACILITY FOR CONVERTING URANIUM HEXAFLUORIDE INTO URANIUM DIOXIDE
A conversion process for converting uranium hexafluoride into uranium dioxide includes the steps of hydrolysis of UF6 to uranium oxyfluoride (UO2F2) in a hydrolysis reactor (4) by reaction between gaseous UF6 and dry water vapour injected into the reactor (4), pyrohydrolysis of UO2F2 to UO2 in a pyrohydrolysis furnace (6) by reacting UO2F2 with dry steam and gaseous hydrogen (H2) injected into the furnace (6), extracting excess gas in the reactor (4) via a collecting device (50) comprising several filters (52), periodically cleaning the filters (52) by injecting a neutral gas into the filters (52) from the outside to the inside of the reactor (4) to remove powder stuck on the filters (52), and measuring the relative pressure in the reactor (4). The conversion method further includes carrying out point cleaning of the filters (52) when the relative pressure in the reactor (4) exceeds a predetermined point cleaning threshold.
The digitally-controlled machining device (1) comprises a control console (3) and a digitally-controlled machining machine (5). The training assembly (33) comprises: - a training control console (35) substantially identical to the control console (3) of the digitally-controlled machining device (1); - a digital duplicate (36) of the digitally-controlled machining machine (5) comprising a simulator (37) configured to simulate the effect of the commands from the training control console (35) on the digitally-controlled machining machine (5); - a display device (39) configured so that an operator in training can view the current state of the simulator (37).
A method for intervention in a radioactive zone includes production of a digital model representing the three-dimensional topography of the radioactive zone (1); and intervention of the at least one operator in the radioactive zone (1). The intervention step includes repeated measurement of the radioactive radiation intensity by a portable detector (3), and determination of the spatial coordinates of the portable detector (3) at the time of the measurement; recording of a plurality of said measurements and the corresponding spatial coordinates in the digital model; materialisation of the recorded measurements in an augmented reality device (5) worn by the at least one operator, by a plurality of discrete holographie symbols (7).
An intervention device for carrying out intervention on a nuclear fuel assembly comprises an articulated robotic arm (22) comprising a securing base (26), a terminal member (28) and at least one arm segment (30, 32) connecting the base (26) to the terminal member (28), and an intervention member (24) carried by the terminal member (28). The intervention member (24) is designed to intervene on the nuclear fuel assembly (2).
G21C 19/26 - Dispositions pour enlever les éléments combustibles ou les éléments de commande grippés ou endommagésDispositions pour déplacer les parties cassées de ceux-ci
G21C 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p. ex. pour la consommation ou pour la contamination
B25J 15/04 - Têtes de préhension avec possibilité pour l'enlèvement ou l'échange à distance de la tête ou de parties de celle-ci
B25J 9/04 - Manipulateurs à commande programmée caractérisés par le mouvement des bras, p. ex. du type à coordonnées cartésiennes par rotation d'au moins un bras en excluant le mouvement de la tête elle-même, p. ex. du type à coordonnées cylindriques ou polaires
61.
Detector for high-energy radiography and associated imaging assembly
A detector (10) for high-energy radiography includes, in the following order: a metal screen (12) arranged to receive incident radiation, at least part of the incident radiation being transmitted through the metal screen and forming a transmitted radiation, a scintillator component (14) arranged to convert the radiation transmitted by the metal screen into light, and a detection layer (16) arranged to detect the intensity of the light emitted by the scintillator component. The screen (12) is made of a metal having an atomic number that is strictly greater than 70 or is made of an alloy comprising at least 50% mass content of one or more metals having an atomic number that is strictly greater than 70 and in that the thickness of the screen is between 20 μm and 900 μm.
N), two distinct types of functional blocks being suitable for executing at least one distinct function, at least one processing module suitable for receiving at least one sequence (46) of functional block(s) to be executed, and at least one internal memory (38) configured to store at least said sequence (46). The programmable logic circuit (10) includes a single functional block of each type, a given functional block being suitable for being called several times, and an execution module (22) configured to execute the called functional block(s) in series, according to said sequence (46).
G21D 3/00 - Commande des installations à énergie nucléaire
H03K 19/17728 - Blocs logiques reconfigurables, p. ex. tables de consultation
H03K 19/17736 - Détails structurels des ressources de routage
H03K 19/17704 - Circuits logiques, c.-à-d. ayant au moins deux entrées agissant sur une sortieCircuits d'inversion utilisant des éléments spécifiés utilisant des circuits logiques élémentaires comme composants disposés sous forme matricielle les fonctions logiques étant réalisées par l'interconnexion des lignes et des colonnes
H03K 19/1776 - Détails structurels des ressources de configuration pour les mémoires
64.
Electronic device and method for simulating an ultrasonic response of a metal part, associated testing electronic system and method and computer program
k), with the computation of elementary distributions, each corresponding to an ultrasonic response received by a receiver located at a border (F) of said zone; and determining a resultant distribution of ultrasonic waves for the part with defect, from the first and second computed distributions, the resultant distribution forming a simulation of an ultrasonic response received from the part including the defect (20), in response to an ultrasonic excitation toward said part.
An anchoring device (1) for anchoring an equipment to a civil engineering structure includes a support plate (5) for the equipment, with at least two orifices (7); for each orifice (7), a longitudinal dowel (13) intended to be rigidly fastened in the civil engineering structure (3); for each orifice (7), a fastening member (25) mounted around the dowel (13); for each orifice (7), a connection (27) of the fastening member (25) to the plate (5), allowing the fastening member (25) to be placed at any given position in a defined region of the orifice (7) in a plane parallel to the plate (5); and for each orifice (7), a reversible lock (55) for blocking the fastening member (25) with respect to the plate in the given position and for blocking the fastening member in position along the dowel (13).
E04B 1/41 - Dispositifs d'assemblage spécialement adaptés pour être noyés dans du béton armé ou de la maçonnerie
F16B 5/02 - Jonction de feuilles ou de plaques soit entre elles soit à des bandes ou barres parallèles à elles par organes de fixation utilisant un filetage
E04B 1/38 - Assemblages pour les constructions du bâtiment en général
66.
Subrack assembly, associated rack and assembly method
A subrack assembly (1) comprising a subrack (3) comprising two top rails (9), two bottom rails (7) and side elements (5), at least one rigidifying frame (21) comprising a front crossbeam, a rear crossbeam and two side beams; and at least one connector (70) for connecting the rigidifying frame (21) to the top and/or bottom of the subrack (3), comprising at least one movable block movable in translation relative to the rigidifying frame (21) between an insertion position, in which it is spaced away from the subrack (3) and a use position, in which it bears against the subrack (3). The connector (70) is configured for connecting the rigidifying frame (21) to the top and/or bottom of the subrack (3) such that the front and rear crossbeams each extend substantially parallel to a top or bottom rail (7, 9) of the subrack (3) and in alignment therewith along a vertical direction.
A tubular component of a pressurised water nuclear reactor has the following composition on a weight basis: - 0.8% = Nb = 2.8%; - traces = Sn = 0.65%; - 0.015% = Fe = 0.40%; preferably 0.020 % = Fe = 0.35 %; - traces = C = 100 ppm; - 600 ppm = O = 2300 ppm; preferably 900 ppm = O = 1800 ppm; - 5 ppm = S = 100 ppm; preferably 8 ppm = S = 35 ppm, - traces = Cr + V + Mo + Cu = 0.35%; - traces = Hf = 100 ppm; - F = 1 ppm; the balance being zirconium and fabrication impurities, and has an outer surface with a roughness Ra of not more than 0.5 µm, obtained after final mechanical polishing, characterised in that it has an outer surface with a roughness Rsk = 1 as an absolute value, and a roughness Rku = 10. A method for obtaining said component.
C21D 8/10 - Modification des propriétés physiques par déformation en combinaison avec, ou suivie par, un traitement thermique pendant la fabrication de corps tubulaires
G21C 1/08 - Réacteurs hétérogènes, c.-à-d. dans lesquels le combustible et le modérateur sont séparés le modérateur étant hautement pressurisé, p. ex. réacteur à eau bouillante, réacteur à surchauffe intégrale, réacteur à eau pressurisée
G21C 3/07 - EnveloppesChemises caractérisées par le matériau, p. ex. alliages
G21C 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci
A boring assembly extends along a main axis and comprises a boring head comprising at least one first nozzle and at least one second nozzle The or each second nozzle is different from the or each first nozzle. The boring assembly includes a first delivery device configured to deliver a jet of abrasive-free water at a pressure comprised between 2000 bar and 4000 bar to the at least one first nozzle. The boring assembly includes a second delivery device configured to deliver a jet containing at least one abrasive material at a pressure comprised between 2000 bar and 6000 bar to the at least one second nozzle.
E21B 7/18 - Forage par action de jets de liquides ou de gaz, avec ou sans entraînement de grenaille
E21B 7/16 - Application de grenailles ou de billes séparées grâce à la pression du trépan, dénommée forage à la grenaille
E21B 7/24 - Forage utilisant des moyens vibrants ou oscillants, p. ex. des masses déséquilibrées
E21B 21/06 - Dispositions pour traiter les fluides de forage à l'extérieur du trou de forage
69.
Method for determining at least one threshold value of at least one operating parameter of a nuclear reactor, and associated computer program and electronic system
A method for determining at least one threshold value of at least one operating parameter of a nuclear reactor is implemented by an electronic determination system and includes the steps of determining a first threshold value of a respective operating parameter for an operation of the reactor at a first power; and determining a second threshold value of said parameter for an operation of the reactor at a second power. The operation at the lower power of the first and second powers is an operation continued for a duration of at least 8 hours over a 24-hour sliding window. The method also includes determining a third threshold value of said parameter for an operation of the reactor at a third power between the first power and the second power.
G21D 3/10 - Régulation de différents paramètres dans l'installation par une combinaison d'une variable dérivée du flux de neutrons avec d'autres variables de commande, p. ex. dérivées de la température, du flux du réfrigérant, de la pression
The invention concerns a method and system for using computing resources of a computing system comprising a plurality of interconnected microprocessors designed to function in parallel, in order to perform software tasks. The system (1) comprises: - a module (30) for computing an experimental design comprising a plurality of software tasks to be performed in order to solve a physical problem defined by at least one input parameter and at least one output parameter, the experimental design being computed on the basis of a predetermined initial computational budget, the software tasks to be performed having a first priority level, - a module (4) for planning the execution of the software tasks by the computing system, configured to: - verify the presence of at least one software task with a second level of priority higher than the first level of priority waiting to be executed, - if at least one such software task is present, obtain computational resources freed up to perform the at least one software task with a second level of priority; - in the absence of at least one such software task, distributing at least some of the software tasks with the first level of priority over the available computing resources.
A cable lead-through assembly (2) includes s frame (10) delimiting a cable reception space (20); and an in-frame sub-system (11) configured for securing cables (1) to the frame (10). The in-frame sub-system (11) includes at least two plates (32) intended for extending in said cable reception space (20), the plates (32) being configured for being coupled to the frame (10) and for forming between each other at least one cable's path for at least one cable (1); securing means (14) configured for securing the or each cable (1) to a corresponding plate (32); and a locking unit (16) coupled to the frame (10). The locking unit (16) has an at-rest configuration and an operational configuration. The locking unit (16) is configured for displacing the plates (32).
H02G 3/22 - Installations de câbles ou de lignes à travers les murs, les sols ou les plafonds, p. ex. dans les immeubles
H02B 1/30 - Enveloppes du type armoireParties constitutives ou accessoires
H02G 3/04 - Tubes ou conduits de protection, p. ex. échelles à câbles ou goulottes de câblage
H02G 3/32 - Installations de câbles ou de lignes sur les murs, les sols ou les plafonds utilisant des colliers de fixation
72.
Electronic device and method for managing the display of data for controlling a nuclear power plant, associated control system and computer program product
An electronic device (18) is for managing the display of data to control a nuclear power plant. The data comes from a plurality of electronic control units (16A, 16B, 16C). Each control unit is configured to perform at least one action from among acquiring a value measured by a sensor (12A, 12B, 12C) and controlling an actuator (14A, 14B, 14C), the control units, sensor(s) and/or actuator(s) being according to several different nuclear safety classes. This electronic device (18) is able to be connected to the control units, and includes a set (25) of electronic module(s) (26A, 26B, 26C) for creating overlay(s) (28A, 28B, 28C). Each overlay contains information associated with one or several control units and according to a respective safety class; and a module (30) for generating a page (32) to be displayed, by superposition of several separate overlays.
A device for detecting a defect on a surface including an optical device (14) suitable for acquiring an image of the surface in a given optical direction, a lighting device (15) comprising a plurality of light sources (16), the light sources (16) being arranged in a hemisphere (20), each light source (16) having an off and an on state, an electronic calculation device (18). The electronic calculation device (18) is able to control the optical device (14) and the lighting device (15) so that the optical device (14) acquires a plurality of images of the surface, different light sources (16) or different combinations of light sources (16) being switched on for each image, the hemisphere (20) having a diameter D smaller than or equal to 50 mm.
A tube inspection unit (10) includes an eddy current probe (14). The probe (14) has a plurality of inductors and a plurality of receivers. The receivers are magnetoresistances having a substantially linear functional zone. The inductors of the probe (14) are linked to a controller (26). The controller (26) is programmed to inject, into the inductors, a voltage with a sinusoidal component and a nonzero direct-current component, such that the receivers have a polarization center situated inside the substantially linear functional zone.
G01N 27/90 - Recherche ou analyse des matériaux par l'emploi de moyens électriques, électrochimiques ou magnétiques en recherchant des variables magnétiques pour rechercher la présence des criques en utilisant les courants de Foucault
G01N 27/904 - Recherche ou analyse des matériaux par l'emploi de moyens électriques, électrochimiques ou magnétiques en recherchant des variables magnétiques pour rechercher la présence des criques en utilisant les courants de Foucault avec plusieurs capteurs
75.
NUCLEAR FUEL ASSEMBLY MANUFACTURING METHOD, NUCLEAR FUEL ASSEMBLY MANUFACTURING PLANT AND METHOD OF EXPANDING SUCH A PLANT
The method is for manufacturing a nuclear fuel assembly (2) comprising nuclear fuel rods (4) arranged in a bundle and a skeleton (6) supporting the fuel rods (4). The method comprise the steps of inserting fuel rods (4) into the skeleton (6) to obtain a fuel assembly (2) and packaging the fuel assembly (2) in view of transportation, the steps being performed in a same nuclear fuel assembly manufacturing plant (20), preferably in a same nuclear fuel assembly manufacturing building (60).
G21C 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p. ex. pour la consommation ou pour la contamination
G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
76.
METHOD AND ASSEMBLY FOR INTERVENTION IN A RADIOACTIVE ZONE
The invention relates to a method and assembly for intervention in a radioactive zone. Said method comprises the following steps: production of a digital model representing the three-dimensional topography of the radioactive zone (1); and intervention of the at least one operator in the radioactive zone (1), the intervention step comprising at least the following substeps: repeated measurement of the radioactive radiation intensity by a portable detector (3), and determination of the spatial coordinates of the portable detector (3) at the time of the measurement; recording of a plurality of said measurements and the corresponding spatial coordinates in the digital model; and materialisation of the recorded measurements in an augmented reality device (5) worn by the at least one operator, by a plurality of discrete holographic symbols (7).
A leakage testing device for testing leakage of a nuclear fuel assembly (18) by sipping. The device includes a collection assembly (32) that is configured to close an upper end (24A) of a cell (24) of a storage rack (22) for storing nuclear fuel assemblies discharged from a nuclear reactor (4). The closing prevents water contained in the cell from escaping via the upper end of the cell. The collection assembly is configured to collect products containing possible fission products released by a nuclear fuel assembly contained in the cell.
A nuclear reactor includes a vessel (1), a support plate (8), arranged in the vessel (1) above the core (2); a plurality of separate dispensing ducts (21); and support members (33) provided to keep the thermocouple ducts (21) in position. Each support member (33) includes a foot (35) rigidly attached to the support plate (8), a head (37) to which the or each thermocouple duct (21) is attached, and a detachable connection (39) from the head (37) to the foot (35).
G21C 5/02 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur Détails
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
79.
Method for inspecting a metal surface and associated device
A method for inspecting a metal surface (12) includes providing a first laser source (14) that is arranged to generate a first laser beam having a first wavelength comprised between 1000 nm and 1100 nm and a power higher than 1 W; providing a second laser source (16) that is arranged to generate a second laser beam having a second wavelength comprised between 1500 nm and 1800 nm and a power higher than 1 W; activating one of the first and second laser sources and transmitting the first or second laser beam to the entrance (22) of an optic (18); scanning the metal surface (12) with the laser beam projected by the optic; and acquiring at least one image of the infrared radiation emitted by the metal surface (12).
A method for inspecting a nuclear reactor part includes placing an optical sensor (38) in front of the part to be inspected using a carrier (40); acquiring at least a first image of at least a reference portion of the part using the optical sensor (38), the or each first image being taken with a first magnification; reconstituting a three-dimensional model of said reference portion of the part using the or each first acquired image; calculating the position of an area to be inspected relative to the optical sensor (38) using the three-dimensional model; acquiring at least a second image of the area to be inspected using the optical sensor (38), the or each second image of the area to be inspected being taken with a second magnification higher than the first magnification.
G01N 21/00 - Recherche ou analyse des matériaux par l'utilisation de moyens optiques, c.-à-d. en utilisant des ondes submillimétriques, de la lumière infrarouge, visible ou ultraviolette
G21C 17/08 - Combinaison structurelle du cœur du réacteur ou de la structure du modérateur avec des moyens de vision, p. ex. avec des caméras de télévision, périscopes, fenêtres
G21C 17/003 - Inspection à distance des enceintes, p. ex. des cuves de pression
G06T 7/73 - Détermination de la position ou de l'orientation des objets ou des caméras utilisant des procédés basés sur les caractéristiques
H04N 5/232 - Dispositifs pour la commande des caméras de télévision, p.ex. commande à distance
G06T 17/00 - Modélisation tridimensionnelle [3D] pour infographie
G21C 17/007 - Inspection des surfaces externes des enceintes
A method for calculating a PCI margin associated with a loading pattern of a nuclear reactor including a core into which fuel assemblies are loaded according to the loading pattern is implemented by an electronic system. The fuel assemblies include fuel rods each including fuel pellets of nuclear fuel and a cladding surrounding the pellets. This method includes calculating a reference principal PCI margin for a reference loading pattern of the fuel assemblies in the core; calculating a reference secondary PCI margin for the reference pattern; calculating a modified secondary PCI margin for a modified loading pattern of the fuel assemblies in the core, and calculating a modified principal PCI margin for the modified pattern, depending on a comparison of the modified secondary PCI margin with the reference secondary PCI margin.
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
82.
Method for detecting a defect on a surface by multidirectional lighting and associated device
A method for detecting a defect on a surface (12) by multidirectional lighting includes acquiring a plurality of images of the surface (12) using an optical device (14) having an optical axis, each image being acquired with a lighting of the surface along a lighting direction (E, E′) given for each point of the surface (12) and an optical direction (O), the images being acquired with different lighting directions (E, E′) or different combinations and/or with different optical directions (O); for each point, calculating a plurality of parameters, the parameters including coefficients of an equation characterizing the response of said point of the surface as a function of the lighting direction (E, E′) and an observation direction (B, B′); and deducing from the calculated parameters whether the surface (12) has a defect at said point.
A repair device for underwater repair of a hole in a nuclear reactor part includes a holder (32), a cutting tool (22) held by the holder (32) and having at least one cutting tooth (70) for remachining an inner surface of the hole. The cutting tool (22) has a suction channel (44) extending into the cutting tool (22) between at least one inlet opening (46) and at least one outlet opening (48), a drive shaft (34) for rotating the cutting tool (22), the drive shaft (34) being held by the holder (32), and a suction tube (36) connected to the holder (32) and fluidly connected to the outlet opening (48) of the suction channel (44).
B23D 75/00 - Machines à aléser ou dispositifs d'alésage
B23D 77/14 - Alésoirs pour travaux particuliers, p. ex. pour usiner des stries de cylindres
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceauMoyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraireMoyens de couplage de faisceaux adjacents
G21C 5/06 - Moyens pour placer ou pour supporter les éléments combustibles
G21C 19/02 - Détails des dispositions pour la manipulation
An absorber cluster for a nuclear reactor includes at least a first absorber assembly and a second absorber assembly. Each absorber assembly respectively comprises neutron absorbing elements. Absorber elements of each of the first absorber assembly and the second absorber assembly are made from the same material or the same combination of materials selected from the group of neutron absorbing materials consisting of a first europium hafnate, a second europium hafnate, a first samarium hafnate, a second samarium hafnate, hafnium carbide, and samarium hexaboride. The first europium hafnate and the second europium hafnate have different compositions. The first samarium hafnate and the second samarium hafnate have different compositions. The absorber elements of the first absorber assembly have a cross-sectional structure different to that of the absorber elements of the second absorber assembly.
G21C 7/24 - Emploi de substances spécifiées pour utilisation comme matériau absorbant les neutrons
G21C 7/117 - Grappes de barres de commandeStructure en araignée
G21C 1/08 - Réacteurs hétérogènes, c.-à-d. dans lesquels le combustible et le modérateur sont séparés le modérateur étant hautement pressurisé, p. ex. réacteur à eau bouillante, réacteur à surchauffe intégrale, réacteur à eau pressurisée
85.
HIGH-ENERGY RADIOGRAPHY DETECTOR AND ASSOCIATED IMAGING KIT
High-energy radiography detector and associated imaging kit. Detector (10) for high energy radiography, comprising in this order: - a metal screen (12) arranged to receive incident radiation, at least part of the incident radiation being transmitted through the metal screen and forming transmitted radiation, - a scintillator component (14) arranged to convert the radiation transmitted by the metal screen into light, and - a detection layer (16) arranged to detect the intensity of the light emitted by the scintillator component. The screen (12) is made of a metal having an atomic number strictly greater than 70 or of an alloy comprising at least 50% by mass content of one or more metals having an atomic number strictly greater than 70 and in that the screen has a thickness between 20 µm and 900 µm.
The invention concerns a programmable logic circuit (10) for controlling an electrical facility, in particular a nuclear facility, the programmable logic circuit including a functional unit (14) comprising: - a plurality of types of functional block (FB1, FBi, FBN), two distinct types of functional block being suitable for executing at least one distinct function, - at least one processing module suitable for receiving at least one sequence (46) of functional blocks to be executed, - at least one internal memory (38) configured to store at least said sequence (46). According to the invention, the programmable logic circuit (10) comprises a single functional block of each type, a given functional block being suitable for being called several times, and an execution module (22) configured to execute the called functional block or blocks in series, according to said sequence (46).
G05B 19/05 - Automates à logique programmables, p. ex. simulant les interconnexions logiques de signaux d'après des diagrammes en échelle ou des organigrammes
G21D 3/00 - Commande des installations à énergie nucléaire
H03K 19/17724 - Détails structurels des blocs logiques
H03K 19/1776 - Détails structurels des ressources de configuration pour les mémoires
87.
Method for producing nuclear fuel products by cold spraying a core comprising aluminum and low enriched uranium
A method of producing a nuclear fuel product includes the steps of providing a core comprising aluminium and low-enriched uranium; and sealing said core in a cladding. The low-enriched uranium has a proportion of U235 below 20 wt %. The step of providing the core including melting low-enriched uranium and aluminium in a furnace to form a melt of uranium-aluminium alloy, producing a powder from the melt of uranium-aluminium alloy, and cold-spraying the powder on a surface of the cladding.
B22F 9/04 - Fabrication des poudres métalliques ou de leurs suspensionsAppareils ou dispositifs spécialement adaptés à cet effet par des procédés physiques à partir d'un matériau solide, p. ex. par broyage, meulage ou écrasement à la meule
B22F 5/00 - Fabrication de pièces ou d'objets à partir de poudres métalliques caractérisée par la forme particulière du produit à réaliser
G21G 4/08 - Sources radioactives autres que les sources de neutrons caractérisées par des aspects de leur structure spécialement adaptées aux applications médicales
88.
TUBE INSPECTION UNIT WITH EDDY CURRENT PROBE AND CORRESPONDING METHOD
The invention relates to a tube inspection unit (10) comprising an eddy current probe (14), said probe (14) having a plurality of inductors and a plurality of receivers. The receivers are magnetoresistors having a substantially linear functional zone. The inductors of the probe (14) are linked to a controller (26). The controller (26) is programmed to inject into the inductors a voltage with a sinusoidal component and a non-zero direct-current component, such that the receivers have a polarization centre situated inside the substantially linear functional zone.
G01N 27/904 - Recherche ou analyse des matériaux par l'emploi de moyens électriques, électrochimiques ou magnétiques en recherchant des variables magnétiques pour rechercher la présence des criques en utilisant les courants de Foucault avec plusieurs capteurs
89.
METHOD FOR INSPECTING A METAL SURFACE AND ASSOCIATED DEVICE
The invention relates to a method for inspecting a metal surface (12). The method comprises the following steps: providing a first laser source (14) that is arranged to generate a first laser beam having a first wavelength comprised between 1000 nm and 1100 nm and a power higher than 1 W; providing a second laser source (16) that is arranged to generate a second laser beam having a second wavelength comprised between 1500 nm and 1800 nm and a power higher than 1 W; activating one of the first and second laser sources and transmitting the first or second laser beam to the entrance (22) of an optic (18); scanning the metal surface (12) with the laser beam projected by the optic; acquiring at least one image of the infrared radiation emitted by the metal surface (12).
The invention relates to a nuclear fuel cladding comprising: i) a substrate containing a zirconium-based inner layer, optionally coated with at least one intermediate layer formed by at least one intermediate material selected from among tantalum, molybdenum, tungsten, niobium, vanadium, hafnium or the alloys thereof; and ii) at least one protective outer layer placed on the substrate and formed by a protective material selected from either chromium or an alloy of chromium. The nuclear fuel cladding produced using the method of the invention has improved resistance to oxidation/hydriding. The invention also relates to the method for the production of the nuclear fuel cladding by ion etching of the surface of the substrate and deposition of the outer layer on the substrate with a high power impulse magnetron sputtering method (HiPIMS), as well as to the use thereof to protect against oxidation and/or hydriding.
G21C 3/20 - Détails de structure à l'intérieur de l'enveloppe avec revêtement sur le combustible ou sur l'intérieur de l'enveloppeDétails de structure à l'intérieur de l'enveloppe avec une intercouche non active entre l'enveloppe et le matériau actif
brevets
