The present invention relates to a method (400) for checking the uniformity of the composition of a fissile isotope of interest in a chemical element along a main axis (X) of a nuclear fuel rod (15) to be tested, the method comprising the steps of performing a first scan (401) of the fuel rod to be tested (15) along the main axis (X) using a first gamma radiation detector (20) without prior excitation, wherein the first scan generates a first gamma profile; performing a second scan (402) of the fuel rod to be tested (15) along the main axis (X) using a second gamma radiation detector (25) after excitation by means of a neutron source (30), wherein the second scan generates a second gamma profile; obtaining a third gamma profile by subtracting the first profile from the second profile; and evaluating (403) the uniformity of the composition of the fissile isotope of interest along the main axis (X) of the fuel rod to be tested (15) on the basis of the third gamma profile.
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
2.
NUCLEAR FUEL ROD CLADDING AND METHOD FOR PRODUCING SUCH CLADDING
The invention relates to cladding comprising a tube (14) that extends along a longitudinal axis and a tubular inner lining (18) housed inside the tube (14), wherein the tube (14) comprises at least one reinforced layer (16) made of a composite material that comprises a ceramic matrix reinforced with ceramic reinforcing fibres, and wherein the thickness of the tube (14) is between 280 µm and 600 µm.
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
3.
DEVICE FOR THE QUALIFICATION OF A PLURALITY OF SPECIMENS COMPRISING A WIRE AND AT LEAST ONE CRIMPED ELEMENT, AND CORRESPONDING METHOD
The invention relates to a device for qualifying a plurality of specimens (14), each comprising a wire (18) and at least one element (20) crimped onto the wire, the device comprising: - a test zone (28) forming locations (24) intended to receive respective specimens to be tested, - a programmable current source (30), - an electrical circuit (32) for electrically connecting the locations to the current source, the electrical circuit comprising contactors (C1 to C21) configured to be opened or closed and to define, in combination with one another, a plurality of electrical circuit configurations, in particular of a first type, in which: - only one of the locations is selectively electrically connected to the current source, - the others are disconnected from the current source, and - only one of the specimens is intended for a current to pass therethrough.
G01R 31/69 - Test de connexions amovibles, p. ex. des raccords montés sur une carte de circuit imprimé de raccords à l’extrémité d’un câble ou d’un faisceau de filsTest de connexions amovibles, p. ex. des raccords montés sur une carte de circuit imprimé de bornesTest de connexions amovibles, p. ex. des raccords montés sur une carte de circuit imprimé de fiches de prises de courant, p. ex. de prises murales ou de prises de courant montées sur des appareils
G01R 27/20 - Mesure d'une résistance de terreMesure de la résistance de contact de connexions au sol, p. ex. de plaques
G01R 27/08 - Mesure de la résistance par mesure à la fois de la tension et de l'intensité
4.
SYSTEM PROVIDING AN AUTOMATIC PATCH OF ELECTRICAL SIGNALS BETWEEN TWO DIFFERENT DEVICES AND ASSOCIATED METHOD
The invention concerns a system (10), providing a patch of electrical signals between at least two different devices (12, 14) presenting a different number of connecting points, and comprising: - a connecting panel (161) presenting connecting points of one (12) of these device, - a PCB configuration card (18) configured to route some of the connecting points to a free face comprising at least one board to board connector with a predetermined input/output connection pattern; - a flex PCB comprising two identical ends (20) connected by a flexible PCB link (22), each end presenting at least one flex PCB board to board connector configured to be plugged, according to said predetermined input/output connection pattern, one end being connected to the board to board connector, the other end being connected to the other device (14).
This irradiation unit (10) for emitting nuclear radiation having an activity in the range of 9kCi to 15KCi, comprising: - a cylindrical irradiation vessel (18) forming a closed internal volume (22); and - a plurality of irradiation sources (20) located in the closed inner volume (22); wherein: - the irradiation sources (20) are essentially spherical; - the cylindrical irradiation vessel (18) is a single-walled vessel; and - the irradiation unit (10) further comprises a binder (21 ) arranged in the closed inner volume (22), wherein the irradiation sources (20) are embedded in the binder (21).
G21G 4/06 - Sources radioactives autres que les sources de neutrons caractérisées par des aspects de leur structure
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
6.
ENDOSCOPIC SCANNING DEVICE WITHOUT MECHANICAL DISPLACEMENT, AND ASSOCIATED ASSEMBLY AND METHOD
The present invention relates to a device (10) for scanning a surface (100) by endoscopy, comprising: - a light source (12) capable of generating an emitted light beam (20) having a wavelength selectively chosen from different wavelengths, - an optical guide (14) suitable for transmitting the emitted light beam (20), and - an optical device (16) arranged to receive the emitted light beam transmitted by the optical guide (14) and to emit an exiting light beam (30) from the received light beam, the optical device (16) being suitable for emitting the exiting light beam (30) at a location and/or at an angle depending on its wavelength. The invention also relates to an associated assembly and scanning method.
A61B 1/06 - Instruments pour procéder à l'examen médical de l'intérieur des cavités ou des conduits du corps par inspection visuelle ou photographique, p. ex. endoscopesDispositions pour l'éclairage dans ces instruments avec dispositifs d'éclairement
G02B 23/24 - Instruments pour regarder l'intérieur de corps creux, p. ex. endoscopes à fibres
7.
METHOD FOR MANUFACTURING A NUCLEAR REACTOR COMPONENT AND RESULTING NUCLEAR REACTOR COMPONENT
The manufacturing method comprises obtaining a strip of nickel-based alloy having a composition, in percentages by weight: trace amounts ≤ C ≤ 0.08%; trace amounts ≤ Mn ≤ 0.35%; trace amounts ≤ Si ≤ 0.35%; trace amounts ≤ P ≤ 0.015%; trace amounts ≤ S ≤ 0.015%; 17.0% ≤ Cr ≤ 21.0%; trace amounts ≤ Co ≤ 1.0%; 2.80% ≤ Mo ≤ 3.30%; 4.75% ≤ Nb + Ta ≤ 5.50%; 0.65% ≤ Ti ≤ 1.15%; 0.20% ≤ Al ≤ 0.80%; trace amounts ≤ Cu ≤ 0.30%; 50.0% ≤ Ni ≤ 55.0%; trace amounts ≤ B ≤ 0.006%; the balance being Fe and impurities resulting from the production, and performing desensitization annealing in a static furnace at an annealing temperature equal to or higher than 900°C and/or equal to or lower than 1050°C for an annealing time equal to or greater than 1 min and/or equal to or less than 180 min.
C22C 19/05 - Alliages à base de nickel ou de cobalt, seuls ou ensemble à base de nickel avec du chrome
C22F 1/10 - Modification de la structure physique des métaux ou alliages non ferreux par traitement thermique ou par travail à chaud ou à froid du nickel ou du cobalt ou de leurs alliages
09 - Appareils et instruments scientifiques et électriques
37 - Services de construction; extraction minière; installation et réparation
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Scientific, surveying, electronic, electric, optical,
weighing, measuring, signaling, checking (supervision) and
emergency (life-saving) used in the nuclear energy
industries; apparatus, instruments and devices for
monitoring and surveillance of industrial installations in
the fields of nuclear energy; apparatus and software for
controlling the stability of industrial facilities in the
fields of nuclear energy; computer programs, software
packages, software and alarms for monitoring and
surveillance of industrial installations; computer programs,
software packages and software used in the nuclear field;
electric or electronic components, particularly
semiconductors, semiconductor devices, electronic circuits
and microcircuits, chips (integrated circuits),
microprocessors, microcontrollers, field-programmable gate
array (FPGA) networks and assemblies bundled together;
expert system generator, namely, expert systems generation
software, knowledge-based construction and operating
development software; apparatus and instruments for
topographies; artificial intelligence software for
monitoring, controlling, optimizing and supporting the
operational management of industrial facilities. Construction and implementation service for research and
engineering facilities and equipment in the fields of
nuclear energy, renewable energies and efforts to combat
climate change; installation and maintenance services for
control, operational control or safety system facilities in
the field of energy. Engineering services for research and development in the
fields of computing and the nuclear field; services for
scientific calculations, design and engineering services
aided or not by computers for the construction or
maintenance of nuclear power plants and the equipment
thereof; monitoring and control services for monitoring and
controlling facilities, equipment in the field of
microprocessor-controlled nuclear energy, monitoring and
controlling facilities and pilot modules using interactive
displays, in the field of computing and the nuclear field;
diagnostics and technical expertise with respect to the
safety and control of facilities in the nuclear field;
technical studies and analyses and diagnostics (provided by
engineers) for the installation of control systems in the
nuclear field; software maintenance; updating of software;
artificial intelligence research in the nuclear field;
conducting tests for control-command of nuclear facilities;
research in the field of controlled nuclear fusion
technology; research work and technical project studies in
the field of nuclear energy, connectics and electronics;
advice, expertise [engineering works] in the fields of
nuclear energy, connectics and electronics; monitoring and
information with respect to instrumentation and
control-command of infrastructures, facilities, equipment
and apparatus in the fields of nuclear energy, renewable
energies and efforts to combat climate change; monitoring
and control-command service for infrastructure, facilities,
equipment and apparatus in the fields of nuclear energy,
renewable energies and efforts to combat climate change.
9.
METHOD AND ASSEMBLY FOR MAINTAINING AN ITEM OF EQUIPMENT OF AN INDUSTRIAL FACILITY
The invention relates to a maintenance method comprising the repeated execution of an operating sequence, the operating sequence comprising the following steps: - (S10) acquiring an image by means an image acquisition member (35), the image showing the item of equipment (37) and an environment of the item of equipment (37); - (S12) comparing the image with the image acquired in the preceding operating sequence; - (S14) determining a position of the image acquisition member (35) with respect to the item of equipment (37) using the comparison; - (S16) displaying, in the image, a sign that allows the item of equipment (37) to be distinguished from its environment, in a given position with respect to the item of equipment (37), using the position of the image acquisition member (35) with respect to the item of equipment (37).
G21C 17/003 - Inspection à distance des enceintes, p. ex. des cuves de pression
G05D 1/00 - Commande de la position, du cap, de l'altitude ou de l'attitude des véhicules terrestres, aquatiques, aériens ou spatiaux, p. ex. utilisant des pilotes automatiques
09 - Appareils et instruments scientifiques et électriques
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Digital platform (IT) for design and validation of digital
simulators intended for simulation of instrumentation and
control of industrial installation operations and safety. Design and development of a digital platform (IT) for design
and validation of digital simulators intended for simulation
of instrumentation and control of industrial installation
operations and safety; design and development of digital
simulators intended for simulation of instrumentation and
control of industrial installation operations and safety.
09 - Appareils et instruments scientifiques et électriques
37 - Services de construction; extraction minière; installation et réparation
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Scientific, surveying, electronic, electric, optical, weighing, measuring, signaling, checking (supervision) and emergency (life-saving) used in the nuclear energy industries; apparatus, instruments and devices for monitoring and surveillance of industrial installations in the fields of nuclear energy; apparatus and software for controlling the stability of industrial facilities in the fields of nuclear energy; computer programs, software packages, software and alarms for monitoring and surveillance of industrial installations; computer programs, software packages and software used in the nuclear field; electric or electronic components, particularly semiconductors, semiconductor devices, electronic circuits and microcircuits, chips (integrated circuits), microprocessors, microcontrollers, field-programmable gate array (FPGA) networks and assemblies bundled together; expert system generator, namely, expert systems generation software, knowledge-based construction and operating development software; apparatus and instruments for topographies; artificial intelligence software for monitoring, controlling, optimizing and supporting the operational management of industrial facilities. Construction and implementation service for research and engineering facilities and equipment in the fields of nuclear energy, renewable energies and efforts to combat climate change; installation and maintenance services for control, operational control or safety system facilities in the field of energy. Engineering services for research and development in the fields of computing and the nuclear field; services for scientific calculations, design and engineering services aided or not by computers for the construction or maintenance of nuclear power plants and the equipment thereof; monitoring and control services for monitoring and controlling facilities, equipment in the field of microprocessor-controlled nuclear energy, monitoring and controlling facilities and pilot modules using interactive displays, in the field of computing and the nuclear field; diagnostics and technical expertise with respect to the safety and control of facilities in the nuclear field; technical studies and analyses and diagnostics (provided by engineers) for the installation of control systems in the nuclear field; software maintenance; updating of software; artificial intelligence research in the nuclear field; conducting tests for control-command of nuclear facilities; research in the field of controlled nuclear fusion technology; research work and technical project studies in the field of nuclear energy, connectics and electronics; advice, expertise [engineering works] in the fields of nuclear energy, connectics and electronics; monitoring and information with respect to instrumentation and control-command of infrastructures, facilities, equipment and apparatus in the fields of nuclear energy, renewable energies and efforts to combat climate change; monitoring and control-command service for infrastructure, facilities, equipment and apparatus in the fields of nuclear energy, renewable energies and efforts to combat climate change.
09 - Appareils et instruments scientifiques et électriques
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Digital platform (IT) for design and validation of digital simulators intended for simulation of instrumentation and control of industrial installation operations and safety. Design and development of a digital platform (IT) for design and validation of digital simulators intended for simulation of instrumentation and control of industrial installation operations and safety; design and development of digital simulators intended for simulation of instrumentation and control of industrial installation operations and safety.
13.
METHOD FOR MANUFACTURING A NUCLEAR FUEL ROD CLADDING AND CORRESPONDING NUCLEAR FUEL ROD CLADDING
The manufacturing method is intended for the manufacture of a nuclear fuel rod cladding (4) comprising a substrate (14) covered with a protective coating (16). The manufacturing method comprises providing the substrate (14) and applying the protective coating (16) to the substrate (14) by physical vapour deposition by sputtering, simultaneously employing two or more mutually different techniques of physical vapour deposition by sputtering.
G21C 3/07 - EnveloppesChemises caractérisées par le matériau, p. ex. alliages
G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
C23C 14/16 - Matériau métallique, bore ou silicium sur des substrats métalliques, en bore ou en silicium
C23C 28/00 - Revêtement pour obtenir au moins deux couches superposées, soit par des procédés non prévus dans un seul des groupes principaux , soit par des combinaisons de procédés prévus dans les sous-classes et
C23C 30/00 - Revêtement avec des matériaux métalliques, caractérisé uniquement par la composition du matériau métallique, c.-à-d. non caractérisé par le procédé de revêtement
H01J 37/34 - Tubes à décharge en atmosphère gazeuse fonctionnant par pulvérisation cathodique
14.
SPOT WELDING ELECTRODE AND CORRESPONDING SPOT WELDING ASSEMBLY AND SPOT WELDING DEVICE
The spot welding electrode has an active surface (14) for contact with a part to be welded (4, 6), wherein the active surface (14) is convex and profiled along a longitudinal axis (A).
The invention relates to a nuclear fuel pellet which has a rotationally symmetrical shape about a central axis (B) and contains a fissile material, the pellet having concentric layers including a proximal layer (20), an intermediate layer (22) and a distal layer (24), in which the enrichment of fissile material within the pellet varies radially, the intermediate layer (22) comprising a high enrichment zone in which the enrichment is strictly greater than the enrichment in the proximal layer (20) and/or than the enrichment in the distal layer (24).
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
Disclosed is a debris filter formed by a grid (32) having a first face (32A) and an opposite second face (32B), the grid (36) having passages (36) which extend between an inlet (36A) located on the first face (32A) and an outlet (36B) located on the second face (32B) and which allow a cooling fluid to flow through the grid (32), the grid (32) having a first zone (Z1) and at least one second zone (Z2) in which the grid (32) has a thickness greater than that of the grid (32) in the first zone (Z1), passages (36) being present in the first zone (Z1) and in each second zone (Z2).
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
B01D 29/01 - 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
B01D 35/02 - Filtres adaptés à des endroits particuliers, p. ex. conduites, pompes, robinets
17.
DEBRIS FILTER FOR THE LOWER END OF A NUCLEAR FUEL ASSEMBLY, HAVING VARIABLE DEFLECTION PASSAGES
Disclosed is a debris filter formed by a grid (32) having a first face (32A) and an opposite second face (32B), the grid (36) having passages (36) to allow a cooling fluid to flow through the grid (32), each passage (36) extending between an inlet (36A), located on the first face (32A) and having an inlet axis (A1), and an outlet (36B), located on the second face (32B) and having an outlet axis (A2), an inclination angle being defined between the inlet axis (A1) and the outlet axis (A2), the grid (32) comprising passages (36) having different inclination angles between their inlet axis (A1) and their outlet axis (A2).
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
B01D 35/02 - Filtres adaptés à des endroits particuliers, p. ex. conduites, pompes, robinets
B01D 29/01 - 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
The invention relates to a maintenance method for a control rod drive assembly. The method comprises the steps of: - removing the initial weld (67) from the omega seal (65) and removing the jacket (25); - performing at least one maintenance operation on the control assembly (17); - cutting an edge (69) of the first lip (61) of the omega seal (65); - obtaining a replacement jacket (25R) comprising a new second lip (71); - creating a new sealed weld (73) between the first lip (61) and the new second lip (71), the new weld (73) being angularly offset by an angle (α) of between 15° and 80° in relation to the initial weld.
G21C 7/08 - 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 des éléments de commande solides, p. ex. barres de commandes
G21C 13/028 - Joints, p. ex. pour les cuves de pression ou les enceintes de confinement
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
19.
METHOD FOR MONITORING ACCESS TO A SOFTWARE OF A CONTROL SYSTEM AND MONITORING SYSTEM
The control system (1) comprises at least one cabinet (3) containing hardware components (5) comprising software components or giving access to software components. The monitoring method comprising: - determining a plurality of physical intrusion ways to the software components for which monitoring is desired; - providing tamperproof elements (23) at respective defined marking locations on the hardware components (5) and/or on the cabinet (3), each tamperproof element (23) having a unique identification code, the marking locations being chosen such that an intrusion through one of said physical intrusion ways causes at least one of the tamperproof elements (23) to be damaged; - storing in a database (35) a reference status comprising the unique identification code of the tamperproof elements (23) and the corresponding marking locations; and - during a monitoring phase, checking at least some of the marking locations and comparing with the reference status
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
20.
METHOD AND SYSTEM FOR INSPECTING AN OBJECT, SUCH AS A NUCLEAR REACTOR COMPONENT, E.G. A NUCLEAR FUEL ASSEMBLY
The inspection method is for detecting a defect on an object, in particular a nuclear reactor component, e.g. a nuclear fuel assembly, the inspection method comprising the steps of: - obtaining a first image (F1) of a region of interest of the nuclear component; - inputting the first image (F1) to an autoencoder (34) configured for encoding the first image (F1) into an image code and decoding the image code to output a second image (F2); and - comparing the first image (F1) with the second image (F2) for detecting the representation of a defect in the first image (F1).
The present application relates in particular to a welding method comprising the following successive steps: removing a layer of an inner surface (9) of the end (11, 13) of at least one of the pipes, thereby creating a recessed zone (15) extending in the inner surface (9) to the free edge (14); filling the recessed zone (15) by deposition of a stainless steel (17); welding the pipe ends (11, 13) to each other by end-to-end welding.
Nuclear fuel element containing a core made of fissile material and a reinforcement cover and method of manufacturing the same The nuclear fuel element is configured for insertion into a cladding tube of a nuclear fuel rod, the nuclear fuel element extending along a central axis and comprising a fissile core made of fissile material and a reinforcement cover made of a thread winding and/or interlaced threads, the reinforcement cover surrounding the fissile core.
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
G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
23.
NUCLEAR FUEL CLADDING AND METHOD FOR PRODUCING SUCH CLADDING
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.
The invention relates to a method for the maintenance of an in-core neutron measuring device (3) of a nuclear reactor (1), which has a device (33) for selecting the measurement passage (11) into which the neutron measuring probe (25) is to be sent. The maintenance method comprises the following steps: - removing the input part (35) from the selection device (33); - attaching a replacement input part (63) to the selection device (33), the replacement input part (63) comprising a replacement input passage (65) having the same geometry as the input passage (31) of the input part (35); - inserting an adjustment probe (71) into the replacement input passage (65) and adjusting the detector (45); - removing the replacement input part (63) from the selection device (33); - placing the input part (35) back on the selection device (33).
G21C 17/116 - Passages ou isolateurs, p. ex. pour câbles électriques
G21C 19/02 - Détails des dispositions pour la manipulation
G21C 19/19 - Parties de réacteurs spécifiquement adaptées pour faciliter la manipulation, p. ex. pour faciliter le chargement ou le déchargement des éléments combustibles
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
26.
DEVICE FOR RAISING OR LOWERING A NUCLEAR FUEL ASSEMBLY OUT OF AND INTO A POOL OF A NUCLEAR FACILITY
The invention relates to a device (10) for raising or lowering a nuclear fuel assembly (12) out of and into a pool (14) of a nuclear facility, comprising: - a guide system (20); and - a vertically movable gondola (22) that defines a housing (24) for accommodating the nuclear fuel assembly and water; - a movable cover (28) for closing the gondola (22) in a watertight manner, the housing (24) containing a gas layer (44), or for allowing loading of the nuclear fuel assembly; - at least one sampling system (30) for providing at least one water sample (32) taken from the housing; and - a depressurization system (34) for extracting some of the gas layer and lowering the pressure in the housing (24) when the cover is closed.
A test method is for testing a spacer grid (14) of a nuclear fuel assembly (2) comprising a bundle of nuclear fuel rods (4) 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 (20) comprising a bundle of test rods (20) 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
The invention relates to a wheel chock (23) comprising: - two wedges (25) arranged longitudinally on either side of a space (27) for accommodating the wheel (5); - a lateral member (37) delimiting the accommodating space (27) on a first transverse side and connecting respective first lateral sides of the two wedges (25) to one another, the lateral member (37) being made of a flexible material; - two partial lateral members (47) which delimit the accommodating space (27) on a second transverse side opposite the first and are secured to respective second lateral sides of the two wedges (25), the two partial lateral members (47) being separated from one another; the two wedges (25) having respective sloped surfaces (29) each with a planar region (31) for contact with the wheel (5), forming an angle (α) of between 15° and 45° with the lower plane I of the wedges.
B65G 69/34 - Accessoires, p. ex. dispositifs de retenue des véhicules, dispositifs d'immobilisation des roues, dispositifs de positionnement ou d'amortissement
B65G 69/00 - Mesures auxiliaires ou dispositifs utilisés en liaison avec le chargement ou le déchargement
B60T 3/00 - Dispositifs portatifs pour empêcher le mouvement non voulu d'un véhicule, p. ex. cales
09 - Appareils et instruments scientifiques et électriques
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Downloadable computer software for use in computer network management; downloadable computer software for computer system security and enterprise system management; downloadable computer software for monitoring computer networks, computer systems security and computer enterprise systems; downloadable computer software for managing compliance and certification of computer networks, computer systems security and enterprise systems; downloadable software for assessing and correcting computer network vulnerabilities, intrusion detection, managing computer software updates, and managing regulatory compliance, security accreditation and certification Maintenance and updating of computer software; technical support services, namely, troubleshooting of computer software problems; computer hardware and computer software consultation in the fields of selection, implementation and use of computer hardware and software systems for others; computer network services, namely, configuring, maintaining and troubleshooting problems with computer network software systems and remote and on-site management of enterprise information technology systems for others; Computer system security services, namely, monitoring of computer systems for protecting data and information from unauthorized access and featuring assessment and correction of computer network vulnerabilities, network intrusion detection, compliance management and security accreditation, all for security purposes; providing temporary use of online non-downloadable computer software for use in computer network management; providing temporary use of online non-downloadable computer software for computer system security and enterprise system management; providing temporary use of online non-downloadable computer software for monitoring computer networks, computer systems security and computer enterprise systems; providing temporary use of online non-downloadable computer software for managing compliance and certification of computer networks, computer systems security and enterprise systems; providing temporary use of online non-downloadable computer software for assessing and correcting computer network vulnerabilities, intrusion detection, managing computer software updates, and managing regulatory compliance, security accreditation and certification
30.
COMPUTER IMPLEMENTED METHOD FOR SIMULATING AN OPERATION OF A REACTOR CORE
The present invention concerns a computer implemented method for simulating an operation of a reactor core (7), the method comprising: determining (100) an initial state of the reactor core (7), the reactor core (7) comprising a plurality of fuel assemblies (10), wherein the core is partitioned in cubes to constitute nodes of a grid; calculating (102, 104), based on the initial state, a nodal target power distribution (p) and/or the target 3D neutron flux distribution (Φ); obtaining (106) an actual power distribution and/or the actual 3D neutron flux distribution of the nuclear reactor core; determining (108) a difference between the target power distribution (p) and the actual power distribution of the nuclear reactor core and/or determining (108) a difference (δΦ) between the target 3D neutron flux distribution (Φ) and the actual 3D neutron flux distribution of the nuclear reactor core; determining (110) modal expansion coefficients (δcℓ) using a Fourier modal decomposition based on the determined difference (δΦ) and applying a Modal Generalized Perturbation Theory, MGPT, to the modal expansion coefficients (δcℓ) for determining a 3D cross-section distribution perturbation (δΣ) causing the determined difference (δΦ); and determining (112) a 3D adaptation distribution (δx) for the determined difference (δΦ) based on the determined 3D cross-section distribution perturbation (δΣ).
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
32.
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).
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
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
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.
METHOD AND SYSTEM FOR MONITORING A NUCLEAR PLANT, WITH DETECTION AND CHARACTERIZATION OF AN IMBALANCE
The monitoring method comprises, for each steam generator of a plurality of steam generators, and for at least one of the parameters of a set of parameters representative of the functioning of the steam generator: - the determination of a deviation between a measured value of the parameter for this steam generator and the mean value of this parameter for all of the steam generators, in order to detect an imbalance of this parameter on the steam generator; and - the characterization of the imbalance according to one or more other parameters of the set of representative parameters, so as to generate a signal of a physical problem or a signal of a measurement drift.
The manufacturing method comprises the obtaining of a core (4), the coating of the core (4) with an anti-diffusion layer (8) so as to obtain a coated core (10), the insertion of the coated core (10) into a cladding (6) with interposition, between the coated core (10) and the cladding (6), of one or more intermediate layers (12), and the pressing of the multilayer assembly (22) thus obtained, each intermediate layer (12) being made from a ductile metal alloy and/or a metal alloy having a conventional yield strength that does not differ by more than 30% from that of the material of the cladding (6), an elongation at break that does not differ by more than 30% from that of the material of the cladding (6) and/or a distributed relative elongation that does not differ by more than 30% from that of the material of the cladding (6).
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
G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
G21C 21/10 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives par extrusion, filage, étirage
36.
BOTTOM NOZZLE AND NUCLEAR FUEL ASSEMBLY COMPRISING SUCH A BOTTOM NOZZLE
The bottom nozzle comprises a tubular body (16) having a lower opening (18) and an upper opening (20), a lower tie plate (24) extending across the upper opening (20) and a debris filter (28) received inside the tubular body (16) below the lower tie plate (24), wherein the bottom nozzle comprises connection members (32), each connection member (32) being configured for securing a lower end of a respective guide tube (12) of the nuclear fuel assembly to the lower tie plate (24) and being operable from below the debris filter (28) for attaching the guide tube (12) to the lower tie plate (24) and detaching the guide tube (12) from the lower tie plate (24).
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
The top nozzle comprises an intermediate plate (26) axially positioned between an upper plate (24) and a lower plate (22) with being axially movable between an upper position and a lower position, one or several main spring member(s) (28) arranged such as to permanently push the intermediate plate (26) towards the upper plate (24), one or several spring member(s) (30) arranged to push to intermediate plate (26) towards the upper plate (24) when the intermediate plate (26) is located between the lower position and an intermediate position associated to this auxiliary spring member (30), and a preload element (32) associated to each auxiliary spring member (30) with being arranged such that the auxiliary spring member (30) abuts against the upper plate (24) via the preload element (32) when the intermediate plate (26) is located between the intermediate position associated to said auxiliary spring member (30) and the upper position.
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
38.
METHOD AND ASSEMBLY FOR CONTROLLING A NUCLEAR REACTOR, NUCLEAR REACTOR EQUIPPED WITH SUCH AN ASSEMBLY
This control method comprises the following steps: S20/ acquiring current values of operating parameters of the reactor; S30/ iteratively, implementing the following sub-steps: S31/ generating a sequence of injection of neutron poison and/or water S32/ computing a variation in at least one characteristic quantity of the state of the core (3) of the nuclear reactor during said determined time interval using a power programme, current values of operating parameters and the injection sequence in question, the variation being computed using a predictive model of the core of the reactor; S33/ evaluating a cost function, using the computed variation; sub-steps S31/ to S33/ being repeated until a convergence criterion of the cost function is met; steps S20/ and S30/ being repeated with a period shorter 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
G21D 3/00 - Commande des installations à énergie nucléaire
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 3/16 - Régulation de différents paramètres dans l'installation par ajustement du réacteur en réponse uniquement aux changements se produisant dans la demande du moteur en variant la réactivité
09 - Appareils et instruments scientifiques et électriques
16 - Papier, carton et produits en ces matières
20 - Meubles et produits décoratifs
35 - Publicité; Affaires commerciales
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Encoded, electronic, electromagnetic, photographic, cinematographic, optical data media with holograms, containing information, data and/or recorded elements, in particular in the nature of electronic labels, encoded adhesive labels, encoded barcode labels, labels with machine-readable codes, rapid response bidimensional barcode labels, magnetic labels, encoded badges, magnetic cards, electronic security tags, smart labels, RFID labels, labels with RFID chips [RFID], radio-frequency identification tags [RFID], encoded identification labels; Computing equipment, namely Computer software, in particular for the providing, entry, storage, security and administration of data and information from the aforesaid data media; Software for physical intrusion or network intrusion detection systems; Apparatus for recording, transmitting, processing and reproducing data and information from the aforesaid data media, Holograms; Electronica devices for detecting opening doors; Non-downloadable computer network security software. Paper; Cardboard; Printed matter, Including, in particular Tag labels, Vignettes. Sheets of plastic, namly Labels of plastic. Recording, transcription as well as management and compilation of data recorded on data media with security features; Data mining, Data management, Amongst others in relation to the following goods: Labels, Vignettes, Smart labels, RFID tags, the aforesaid goods being data media. Programming for computers, Design of data processing programs; Development of data processing programs; Computer network security services.
The maintenance method is applied to a nuclear reactor (1) having at least one control assembly (17) for controlling a rod cluster control assembly (13) comprising a casing (21) for receiving a lifting mechanism (23) and a sheath (25) for receiving the control rod (15), a first lip (61) at an upper casing end (35) and a second lip (63) at a lower sheath end (43) forming an omega seal (65). The maintenance method comprises the following steps: - removing the first and second lips (61, 63); - carrying out at least one maintenance operation on the control assembly (17); - creating a welding surface (67) by machining the upper casing end (35); - creating a sealed welded connection (69) by welding the welding surface (67) and a complementary welding surface (73) provided at the lower end of the sheath or of a replacement sheath (71).
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
G21C 13/032 - Raccords entre le tube et la paroi d'une enceinte, p. ex. tenant compte des contraintes thermiques
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
41.
DEVICE FOR RAISING OR LOWERING A NUCLEAR FUEL ASSEMBLY IN A POOL OF A NUCLEAR INSTALLATION
A device (7) for raising or lowering a nuclear fuel assembly (12) in a pool (14) of a nuclear installation, comprising: - a guiding system (20) intended to be fastened to the pool, and - a basket (22) defining a housing (24) for receiving the nuclear fuel assembly and water (40) around the nuclear fuel assembly, the basket being mounted on the guiding system so as to be able to move translationally in a direction (V) that is intended to be substantially vertical, the basket comprising an upper end (32) defining a passage (33) intended to allow the nuclear fuel assembly to be loaded into the housing from above, and a lateral jacket (34) that is intended to encircle the nuclear fuel assembly about the direction (V) and that is seal-tight to water, and - at least one sampling system (62) suitable for delivering at least one water sample (68) sampled from the housing.
G21C 19/08 - Moyens pour le chauffage des éléments combustibles avant leur introduction dans le cœurMoyens pour le chauffage ou le refroidissement des éléments combustibles après leur extraction du cœur
G21C 19/07 - Râteliers de stockagePiscines de stockage
42.
METHOD AND SYSTEM FOR CONTROLLING A NUCLEAR POWER PLANT
The invention relates to a control method which comprises, when no imbalance is detected between a primary power signal (S1) and a secondary power signal (S2), implementing a setpoint monitoring mode, in which the nuclear power plant is controlled in accordance with an operational power setpoint (COP), and in the event of detecting an imbalance, automatically implementing a power limitation mode, which comprises calculating a target equilibrium power (PEC) equal to or less than the primary power (P1) and equal to or less than the secondary power (P2), and controlling the nuclear power plant (2) in accordance with the target equilibrium power (PEC).
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
G21D 3/00 - Commande des installations à énergie nucléaire
43.
ASSEMBLY FOR DETECTING COLLISION RISKS WHEN MOVING A LOAD AND CORRESPONDING MOVING METHOD
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).
The spacer grid element define a cell (17) extending along an extension axis (A) for receiving a nuclear fuel rod (4) and exhibits a polygonal cross-section including at least three supporting sides (20) distributed around the extension axis (A), wherein each supporting side (20) comprises an inwardly protruding corrugation (24) onto which is formed at least one spring (32) for supporting a fuel rod (4) extending through the spacer grid element.
G21C 3/356 - Grilles d'espacement munies d'organes de support des éléments combustibles
45.
CONNECTION ARRANGEMENT FOR MECHANICALLY CONNECTING A FIRST ELEMENT AND A SECOND ELEMENT, SUCH AS A GUIDE TUBE AND A TIE PLATE OF A NUCLEAR FUEL ASSEMBLY
Connection arrangement for mechanically connecting a first element and a second element, such as a guide tube and a tie plate of a nuclear fuel assembly The connection arrangement is for the mechanical connection of a first element (4) having a connection portion (8) to a second element (6) having a housing (10), the connection arrangement comprising a connection ring (12) received inside the housing (10) with being pivotable between an insertion/extraction position allowing insertion/extraction of the connection portion (8) into the housing (10) and a connection position preventing extraction of the connection portion (8) from the housing (10), and a locking ring (20) axially movable along the center axis (A) between a locked position preventing rotation of the connection ring (12) and an unlocked position allowing rotation of the connection ring (12) between the connection position and the insertion/extraction position.
F16B 7/20 - Assemblages de barres ou assemblages de tubes, p. ex. de section non circulaire, y compris les assemblages élastiques utilisant des assemblages à baïonnette
The platform (1) comprises: a floor (17) comprising beams (19) and removable slabs (21) carried by the beams (19); a floating support (13), arranged to float on the water filling a pool of the nuclear facility, a peripheral edge of the floor (17) resting on the floating support (13).
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]
49.
METHOD AND ELECTRONIC DEVICE FOR ASSISTING WITH SURVEILLANCE OF AN ELEMENT OF A NUCLEAR REACTOR, ASSOCIATED COMPUTER PROGRAM AND ASSOCIATED SYSTEM
This method for assisting with surveillance of an element of a nuclear reactor, which method is implemented by an electronic device, comprises the steps of: - (120) training an artificial-intelligence algorithm; - (140) acquiring an image of the element; - (150) estimating, on the basis of the image and via the artificial-intelligence algorithm, whether a fault is present in the element; - (160) displaying the image of the element; and - if at least one fault is estimated to be present, (170) generating an alarm. In the estimating step, an input of 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 input 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
G21D 3/00 - Commande des installations à énergie nucléaire
G06K 9/62 - Méthodes ou dispositions pour la reconnaissance utilisant des moyens électroniques
G06N 7/00 - Agencements informatiques fondés sur des modèles mathématiques spécifiques
09 - Appareils et instruments scientifiques et électriques
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Scientific, surveying, measuring, signalling, checking
(supervision) apparatus and instruments; apparatus and
instruments for conducting, switching, transforming,
accumulating, regulating or controlling electricity;
magnetic data carriers; computer operating systems for use
in nuclear safety; sensors; neutron detectors; electric
actuators; signal conditioning and communication devices for
industrial process control; racks adapted for scientific,
surveying, measuring, signalling, checking (supervision)
apparatus; digital controls; software operating systems for
use in nuclear safety. Industrial analysis and research services; design and
development of computer hardware and software; installation,
maintenance and repair of computer software.
51.
SYSTEM AND METHOD FOR INSPECTING NUCLEAR FUEL PELLETS
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).
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 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci
52.
METHOD AND ASSEMBLY FOR INSPECTING A PLURALITY OF ELEMENTS OF AN INDUSTRIAL PLANT
The invention relates to a method and assembly for inspecting a plurality of elements of an industrial plant. The method comprises the following steps: a/ creating an application (3) having a user interface (5) with one command (7) for each element to be inspected; b/ repeatedly acquiring image data of the elements of the industrial plant using a mobile device (13), and storing these image data in an acquisition memory (15), each item of image data comprising at least one image and a time stamp indicating a time at which the image data was acquired; c/ activating the commands (7) at respective activation times; d/ associating the image data with the elements, the image data associated with a given element being exclusively selected from the image data having a time stamp between the activation time of the command corresponding to said image element and the activation time of the preceding or following command.
G06F 16/58 - Recherche caractérisée par l’utilisation de métadonnées, p. ex. de métadonnées ne provenant pas du contenu ou de métadonnées générées manuellement
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.
G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
B23K 11/00 - Soudage par résistanceSectionnement par chauffage par résistance
B23K 11/093 - Soudage de joints continus non limité à l'un des sous-groupes précédents pour des joints curvilignes situés dans un plan
B23K 11/16 - Soudage par résistance tenant compte des propriétés du métal à souder
B23K 11/18 - Soudage par résistance tenant compte des propriétés du métal à souder de métaux non ferreux
C23C 30/00 - Revêtement avec des matériaux métalliques, caractérisé uniquement par la composition du matériau métallique, c.-à-d. non caractérisé par le procédé de revêtement
C23C 28/02 - Revêtements uniquement de matériaux métalliques
F16L 57/06 - Protection des tuyaux ou d'objets de forme similaire contre les dommages ou les usures internes ou externes contre l'usure
The extraction device (10) comprises an attachment portion (12) configured to be inserted into a sleeve (4) of the rod (2) through an end without a cap, and a grip portion (14), the attachment portion (12) comprising an elongate body (16) following a longitudinal axis (A) and at least one tooth (18) projecting from the body (16), the or each tooth (18) being configured to allow the attachment portion (12) to be forcibly inserted into the sleeve (4) axially, and to engage with the internal surface (4A) of the sleeve (4) so as to prevent the attachment portion (12) from being extracted from the sleeve (4).
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
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
01 - Produits chimiques destinés à l'industrie, aux sciences ainsi qu'à l'agriculture
Produits et services
(1) Poudres d'oxydes métalliques à usage industriel, sels métalliques en poudre à usage industriel, oxydes de hafnium à usage industriel et à usage scientifique et de recherche médicale.
01 - Produits chimiques destinés à l'industrie, aux sciences ainsi qu'à l'agriculture
Produits et services
metal oxide powders for industrial purposes; metal salts in powder form for industrial purposes; hafnium oxides for industrial purposes and for scientific or medical-research use; hafnium salts for industrial purposes and for scientific or medical-research use
57.
METHOD FOR MANUFACTURING A COATED NUCLEAR REACTOR COMPONENT HAVING A MARKING
The manufacturing method makes it possible to obtain a nuclear reactor component comprising a substrate (4) and a coating (8) covering a surface (4A) of the substrate. The manufacturing method comprises laser marking a pattern (6) on the surface (4A) of the substrate (4), the marking being carried out in such a way so as to form hollow raised portions (10) forming the pattern (6) in the surface (4A) of the substrate (4), and subsequently applying the coating (8) to the surface (4A) of the substrate (4), above the pattern (6).
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
The non-destructive inspection system comprises a base (14), an inspection head (16) carrying one or several inspection probe(s) (48), a chain (18) having a distal end (20) supporting the inspection head (16), the chain (18) being movable relative to the base (14) via a driving unit (28) configured for driving the chain (18) to selectively push the inspection head (16) away from the base (14) and pull the inspection head (16) closer to the base (14).
01 - Produits chimiques destinés à l'industrie, aux sciences ainsi qu'à l'agriculture
06 - Métaux communs et minerais; objets en métal
07 - Machines et machines-outils
40 - Traitement de matériaux; recyclage, purification de l'air et traitement de l'eau
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Soldering chemicals. Rods of metal for welding. Welding apparatus and instruments; Machining (Apparatus for -). Machining of parts for others, Metalworking, Welding, Mechanical processing of metals. Engineering, research and development.
01 - Produits chimiques destinés à l'industrie, aux sciences ainsi qu'à l'agriculture
06 - Métaux communs et minerais; objets en métal
07 - Machines et machines-outils
40 - Traitement de matériaux; recyclage, purification de l'air et traitement de l'eau
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Soldering chemicals. Rods of metal for welding. Welding apparatus and instruments; Machining (Apparatus for -). Machining of parts for others, Metalworking, Welding, Mechanical processing of metals. Engineering, research and development.
09 - Appareils et instruments scientifiques et électriques
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
(1) Scientific, surveying, measuring, signalling, checking (supervision) apparatus and instruments; apparatus and instruments for conducting, switching, transforming, accumulating, regulating or controlling electricity; magnetic data carriers; computer operating systems for use in nuclear safety; sensors; neutron detectors; electric actuators; signal conditioning and communication devices for industrial process control; racks adapted for scientific, surveying, measuring, signalling, checking (supervision) apparatus; digital controls; software operating systems for use in nuclear safety. (1) Industrial analysis and research services; design and development of computer hardware and software; installation, maintenance and repair of computer software.
The method for determining the burnup rate of a nuclear fuel element (2) comprises determining the burnup rate of the nuclear fuel element (2) as a function of a coloration of an outer surface of a cladding (4) of the nuclear fuel element (2).
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
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.
09 - Appareils et instruments scientifiques et électriques
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Scientific, surveying, measuring, signalling, checking (supervision) apparatus and instruments; apparatus and instruments for conducting, switching, transforming, accumulating, regulating or controlling electricity; magnetic data carriers; computer operating systems for use in nuclear safety; sensors; neutron detectors; electric actuators; signal conditioning and communication devices for industrial process control; racks adapted for supporting the conditioning and processing of scientific, surveying, measuring, signalling, checking (supervision) apparatus; digital controls; software operating systems for use in nuclear safety. Industrial analysis and research services; design and development of computer hardware and software; installation, maintenance and repair of computer software.
09 - Appareils et instruments scientifiques et électriques
Produits et services
Scientific apparatus and instruments for surveying, measuring, signaling, and supervising power plants, namely, electronic sensors and printed circuit board (PCB) hardware for power plants; apparatus and instruments for conducting, switching, transforming, accumulating, regulating or controlling electricity in a nuclear power plant; blank magnetic data carriers for use in power plants; recorded computer operating systems for use in nuclear safety; electronic sensors for use in safety installation of power plant, not for medical purposes; scientific apparatus, namely, neutron detectors; electric actuators for use in power plants; signal conditioning and communication devices for industrial process control for use in power plants; racks in the nature of stands adapted for printed circuit board (PCB) hardware for power plants; power controllers, namely, digital controls in the nature of printed circuit board hardware components and recorded computer operating software sold as a unit for use in control systems and instrumentation of power plants; recorded operating system software for use in nuclear safety
09 - Appareils et instruments scientifiques et électriques
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Computer software for use in computer network management;
computer software for computer system security and
enterprise system management; computer software for
monitoring computer networks, computer systems security and
computer enterprise systems; computer software for managing
compliance and certification of computer networks, computer
systems security and enterprise systems; software for
assessing and correcting computer network vulnerabilities,
intrusion detection, managing computer software updates, and
managing regulatory compliance, security accreditation and
certification. Maintenance and updating of computer software; technical
support services, namely, troubleshooting of computer
software problems; consultation services in the fields of
selection, implementation and use of computer hardware and
software systems for others; computer network services,
namely, configuring, maintaining and troubleshooting
computer network software systems and remote and on-site
management of enterprise systems for others; computer system
security services, namely, monitoring of computer systems
for security purposes, namely, assessing and correcting
computer network vulnerabilities, network intrusion
detection, compliance management and security accreditation.
68.
ASSEMBLY AND METHOD FOR TRAINING OPERATORS ON A DIGITALLY-CONTROLLED MACHINING DEVICE, PRODUCTION ASSEMBLY COMPRISING SUCH A TRAINING ASSEMBLY
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).
09 - Appareils et instruments scientifiques et électriques
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Computer software for use in computer network management; computer software for computer system security and enterprise system management; computer software for monitoring computer networks, computer systems security and computer enterprise systems; computer software for managing compliance and certification of computer networks, computer systems security and enterprise systems; software for assessing and correcting computer network vulnerabilities, intrusion detection, managing computer software updates, and managing regulatory compliance, security accreditation and certification. Maintenance and updating of computer software; technical support services, namely, troubleshooting of computer software problems; consultation services in the fields of selection, implementation and use of computer hardware and software systems for others; computer network services, namely, configuring, maintaining and troubleshooting computer network software systems and remote and on-site management of enterprise systems for others; Computer system security services, namely, monitoring of computer systems for security purposes, namely, assessing and correcting computer network vulnerabilities, network intrusion detection, compliance management and security accreditation.
70.
PLATFORM AND PLATFORM SYSTEM FOR A NUCLEAR POWER PLANT
The invention relates to a platform that is configured to span a pool (4) of a nuclear power plant, being movable along two parallel rails (6) disposed on either side of the pool (4). The platform comprises at least one platform module (16) having a module floor (18) defining at least one portion of a platform floor (14) and two sets of guides (20) for interacting with the rails (6) for guiding the platform along said rails (6). Each platform module can be extended so as to vary the spacing between the two sets of guides (20) of the platform module (16), the two sets of guides (20) being brought together in a storage configuration and separated in a use configuration.
G21C 19/18 - Appareils pour porter les éléments combustibles à l'aire de charge du réacteur, p. ex. depuis un emplacement de stockage
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
09 - Appareils et instruments scientifiques et électriques
38 - Services de télécommunications
Produits et services
Computer software for voice and video over Internet or for screen sharing or for digital file transfer dedicated to brodcasting of live or recorded remote audit, inspection or visit of industrial installation or industrial process or product qualification. Providing voice and video over internet services or screen sharing services or digital file transfer services in the field of live or recorded remote audit, inspection or visit of industrial installation or industrial process or product qualification.
72.
A THERMAL SLEEVE FOR A CONTROL ROD DRIVE MECHANISM AND ASSOCIATED NUCLEAR REACTOR HEAD, NUCLEAR REACTOR AND METHOD FOR REPLACING A DAMAGED THERMAL SLEEVE
The invention concerns a thermal sleeve (60) for a control rod drive mechanism of a nuclear reactor pressure vessel (4). The thermal sleeve (60) comprises : - a tube (62) comprising an upper end (68) and a lower end, the tube (62) comprising also an outer surface (70) and an inner surface (72), the outer surface (70) and the inner surface (72) extending from the upper end (68) to the lower end; - a plurality of protrusions (64) disposed at the upper end (68) of the tube (62), each protrusion (64) extending radially outward the tube (62); and - a collar (66) protruding radially outward the outer surface (70) of the tube (62) and extending circumferentially all around the tube (62), away from the upper end (68).
The inventions concerns a method of determination of a nuclear core loading pattern defining the disposition of fuel assemblies (40) in the nuclear core, the method comprising the following steps: - definition of at least one potential core loading pattern, - calculation of predictive bowing of the fuel assemblies (40) at the end of the operation cycle for each potential core loading pattern, the calculation being carried out by an automatic learning algorithm trained on a training data set comprising a plurality of others loading patterns and, for each of them, the measures of bowing of fuel assemblies (40) at the end of cycle, - evaluation of the at least one core loading pattern based on the predictive bowing calculations and at least one predetermined criteria, and - selection of one of the potential core loading patterns.
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
The invention concerns a thermal sleeve (60) for a control rod drive mechanism of a nuclear reactor pressure vessel (10). The thermal sleeve (60) comprises : - a tube (62) comprising an upper end (68) and a lower end (70); and - a plurality of protrusions (64) fixed at the upper end (68) of the tube (62), each protrusion (64) extending radially outward the tube (62), the protrusions (64) being different from the tube (62), the protrusions (64) being intermeshed to form a continuous collar (80) presenting an outer diameter greater than the outer diameter of the tube (62).
G21C 7/12 - Moyens pour amener les éléments de commande dans la position désirée
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 13/067 - Bouchons scellés pour des tubulures, p. ex. puits de chargementDispositifs de verrouillage pour bouchons
78.
FUEL ASSEMBLY MAINTENANCE DEVICE AND ASSOCIATED MAINTENANCE METHOD AND KIT
Title: The invention relates to a maintenance device (40) for a fuel assembly of a nuclear reactor, the assembly comprising: - a plurality of guide tubes each able to receive a control rod and comprising at least a connection system; and - a top nozzle (16) defining a plurality of through-passages (22) and able to accept the connection system (26) of one of the guide tubes. The maintenance device (40) comprises: - a tool (42) able to lock or unlock one of the guide tubes with respect to the top nozzle (16) by rotating the connection system (26) in the associated passage (22); and - a removable mask (44) able to be positioned facing the top nozzle (16) and comprising a plate (54) defining at least one opening (56) for guiding the tool (42) into coincidence with the passage (22) associated with said connection system (26).
The cleaning device (10), intended for collecting debris (13) in a fluid volume (12) of a nuclear installation, comprises: • - a suction pipe (14) comprising an upstream end and a downstream end; • - an ejector (16) disposed between the upstream end and the downstream end and configured to inject a primary fluid flow into the suction pipe (14) towards the downstream end, in order to suck in a secondary fluid flow from the upstream end; and • - a retention device (18) designed to be disposed at the downstream end and configured to allow fluid to exit the suction pipe (14) whilst retaining the debris (13).
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
G21F 9/00 - Traitement des matériaux contaminés par la radioactivitéDispositions à cet effet pour la décontamination
E04H 4/16 - Parties constitutives, détails ou accessoires non prévus ailleurs spécialement adaptés au nettoyage des piscines ou des pataugeoires
G21C 19/07 - Râteliers de stockagePiscines de stockage
80.
NUCLEAR FUEL ASSEMBLY BOTTOM END PART DEBRIS FILTER AND METHOD OF MANUFACTURING SUCH A DEBRIS FILTER
The 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) having a structure base (52) and a structure apex (54) spaced along a structure axis (A), each filtering structure (50) comprising blades (56) distributed circumferentially around the structure axis (A), each blade having one end connected to the structure base (52) and one end connected to the structure apex (54), each blade (56) delimiting 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
B01D 29/01 - 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
B01D 46/10 - Séparateurs de particules utilisant des plaques, des feuilles ou des tampons filtrants à surface plane, p. ex. appareils de précipitation de poussières
B28B 1/00 - Fabrication d'objets façonnés à partir du matériau
The inspection system for detecting a deposit on a surface (24) comprises: - a light source system (14) to draw a light pattern (20) onto at least a region of the surface (24); - an image capturing system (16) to capture a digital image (36) of the light pattern (20) drawn onto the region of the surface (24); and - a processing system (18) configured to digitally process the image (36) to determine the presence of a deposit on the region of the surface (24) affecting light reflection properties of the surface (24) as a function of the light pattern (20) drawn onto the region of the surface (24).
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
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
G01N 21/88 - Recherche de la présence de criques, de défauts ou de souillures
G01N 21/952 - Inspection de la surface extérieure de corps cylindriques ou de fils
G01N 21/94 - Recherche de souillures, p. ex. de poussières
82.
DEBRIS FILTER FOR A NUCLEAR FUEL ASSEMBLY BOTTOM END PART AND METHOD OF MANUFACTURING SUCH A DEBRIS FILTER
The debris filter is designed for a nuclear fuel assembly bottom end part comprising a lower nozzle (8) and the debris filter (18) 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).
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
B01D 29/01 - 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
B01D 46/10 - Séparateurs de particules utilisant des plaques, des feuilles ou des tampons filtrants à surface plane, p. ex. appareils de précipitation de poussières
B28B 1/00 - Fabrication d'objets façonnés à partir du matériau
The assembly comprises nuclear fuel rods (4) extending along a longitudinal axis (L) and a skeletal support member (6) configured to support the nuclear fuel rods (4), the skeletal support member (6) comprising two end pieces (8, 10), a plurality of guide tubes (12) connecting the end pieces (8, 10) to each other, spacing grids (14) attached to the guide tubes (12), each spacing grid (14) supporting the nuclear fuel rods (4), the nuclear fuel assembly further comprising 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) having at least two attachment points (21) that are offset relative to each other along the longitudinal axis (L).
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 7/08 - 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 des éléments de commande solides, p. ex. barres de commandes
84.
METHOD AND SET FOR REPAIRING A STEAM GENERATOR OF A NUCLEAR REACTOR
The method comprises the following steps: - supplying a set (E) of centrifugal separator elements; - inserting the elements into the steam generator (1) through the manhole (30); - assembling the centrifugal separator elements together inside the steam generator (1), the centrifugal separator elements forming, once assembled, a replacement upper tubular section (39) and replacement blades (41) for a centrifugal separator.
F22B 37/00 - Détails ou parties constitutives des chaudières à vapeur
F22B 37/32 - Dispositifs séparateurs de vapeur employant la force centrifuge
F22B 1/02 - Méthodes de production de vapeur caractérisées par le genre de chauffage par exploitation de l'énergie thermique contenue dans une source chaude
01 - Produits chimiques destinés à l'industrie, aux sciences ainsi qu'à l'agriculture
Produits et services
(1) Oxydes métalliques; sels métalliques à usage industriel et à usage scientifique et pour la recherche médicale, sels métalliques nommément sels de métaux alcalins; oxydes d'hafnium à usage industriel et à usage scientifique et pour la recherche médicale, oxydes d'hafnium nommément oxydes métalliques; sels d'hafnium à usage industriel et à usage scientifique et pour la recherche médicale, produits chimiques à usage industriel et à usage scientifique et pour la recherche médicale nommément sels d'hafnium.
01 - Produits chimiques destinés à l'industrie, aux sciences ainsi qu'à l'agriculture
Produits et services
(1) Oxydes métalliques; sels métalliques à usage industriel et à usage scientifique et pour la recherche médicale, sels métalliques nommément sels de métaux alcalins; oxydes d'hafnium à usage industriel et à usage scientifique et pour la recherche médicale, oxydes d'hafnium nommément oxydes métalliques; sels d'hafnium à usage industriel et à usage scientifique et pour la recherche médicale, produits chimiques à usage industriel et à usage scientifique et pour la recherche médicale nommément sels d'hafnium.
01 - Produits chimiques destinés à l'industrie, aux sciences ainsi qu'à l'agriculture
Produits et services
Metallic oxides; metal salts for industrial purposes and for scientific or medical-research use; hafnium oxides for industrial purposes and for scientific or medical-research use; hafnium salts for industrial purposes and for scientific or medical-research use
01 - Produits chimiques destinés à l'industrie, aux sciences ainsi qu'à l'agriculture
Produits et services
Metallic oxides; metal salts for industrial purposes and for scientific or medical-research use; hafnium oxides for industrial purposes and for scientific or medical-research use; hafnium salts for industrial purposes and for scientific or medical-research use
89.
MAGNETIC FLUX LEAKAGE INSPECTION DEVICE AND ASSOCIATED METHOD
The invention relates to a magnetic flux leakage inspection device (10) for non-destructive inspection of an object comprising at least one ferromagnetic portion, comprising: - a power supply unit (12) capable of generating an alternating supply current, - a magnetisation unit (14) comprising an electromagnet (20) suitable for generating a magnetic field parallel to a surface of the object in the presence of an alternating supply current, - a measuring unit (16) of the magnetic field capable of measuring the magnetic field along a normal axis designed to be perpendicular to the surface of the object, and - a calculation unit (18) capable of detecting a fault in the object from the measured magnetic field and the magnetic field generated by the electromagnet (20), the alternating supply current having a frequency between 0.1 Hz and 100 Hz.
G01N 27/82 - 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
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.
01 - Produits chimiques destinés à l'industrie, aux sciences ainsi qu'à l'agriculture
06 - Métaux communs et minerais; objets en métal
Produits et services
Ceramics for nuclear components; metal oxide for nuclear
components. Unworked and semi-worked metals and their alloys used in the
nuclear energy industries.
94.
DEVICE AND METHOD FOR ANCHORING EQUIPMENT TO A CIVIL ENGINEERING STRUCTURE
The invention relates to a device (100) for anchoring a piece of equipment (EQ) to a civil engineering structure (GC), comprising a plate (5) comprising at least one through-hole (2), a pin (3) intended to rigidly attach the plate (5) to the structure (GC) and a ring (4) of a single piece in order to make a direct connection between the pin (3) and the plate (5) and to be inserted into the through-hole (2), the ring (4) comprising a curved slot (43), that passes through axially and extends at least from the central axis to its radially external edge (42) along a curved guiding trajectory of the pin (3) in a plane that is perpendicular to the central axis, the curved slot (43) being open in the edge (42), as the pin (3) is to be inserted directly into the curved slot (43), the device (100) comprising an unlocking member (8) intended to be positioned on the ring (4).
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 1/41 - Dispositifs d'assemblage spécialement adaptés pour être noyés dans du béton armé ou de la maçonnerie
F16B 43/00 - Rondelles ou dispositifs équivalentsAutres dispositifs de support pour têtes de boulons ou d'écrous
95.
NUCLEAR FUEL ASSEMBLY FOR PRESSURISED WATER REACTOR AND NUCLEAR REACTOR CORE CONTAINING SUCH AN ASSEMBLY
Said nuclear fuel assembly (16) for a pressurised water nuclear reactor comprises nuclear fuel rods (24), guide tubes (31) for receiving absorbent rods from a control cluster and, optionally, an instrumentation tube, the rods (24) being distributed into two areas (41, 42): - a central area (41), all the rods (24) of the central area (41) being rods (24) whose fuel, before irradiation, is exclusively composed of a mixture of uranium and plutonium oxide; and - a peripheral area (42) extending along outer surfaces of the assembly (16), all the rods of the peripheral area (42) being rods (24) containing, before irradiation, uranium oxide but no plutonium oxide.
G21C 3/328 - Disposition relative des éléments dans le réseau
G21C 5/18 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur caractérisée par l'installation de plus d'une zone active
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
01 - Produits chimiques destinés à l'industrie, aux sciences ainsi qu'à l'agriculture
06 - Métaux communs et minerais; objets en métal
Produits et services
Ceramic powders for use in the manufacture of nuclear fuel assembly; metal oxide powders for the manufacture of nuclear fuel assembly Unworked and semi-worked common metals and their alloys for use in the manufacture of nuclear fuel assembly
97.
DEVICE FOR INSPECTING A WELD OF A HOLLOW LONGITUDINAL TUBULAR ELEMENT
The invention concerns a device (10) for inspecting a weld of a hollow longitudinal tubular element, comprising: - a frame (12), - a system (14) for hooking and locking said frame on the tubular element, - a movable member (19) connected to the frame (12) and rotatable with respect to the frame (12) about the tubular element, - a device (20) for rotating the movable member (19) with respect to the chassis (12), - a support (29) including at least one sensor block (24) for sensing Foucault currents connected to the movable member (19), the support (29) being movable in longitudinal translation with respect to the movable member (19), - a device (26) for driving the support (29) in longitudinal translation.
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
98.
METHOD AND SYSTEM FOR USING COMPUTING RESOURCES OF A MULTIPROCESSOR COMPUTING SYSTEM
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.
The tuned mass damper (1) comprises: - a mounting bracket (5) secured to the pipe (3); - a dynamic mass (7) comprising an annular member (9) extending around the pipe (3); - at least one resilient damper (13), connecting the dynamic mass (7) to the mounting bracket (5) such that vibrations transmitted from the pipe (3) to the dynamic mass (7) are damped by the resilient damper (13); - at least one limiting device (11), with a limited organ (55) secured to one of the mounting bracket (5) and the dynamic mass (7), and a limiting organ (57) secured to the other of the mounting bracket (5) and the dynamic mass (7), the limited organ (55) having no contact with the limiting organ (57) when the tuned mass damper (1) is at rest, the limiting organ (57) defining stops for the displacement of the limited organ (55) with respect to the limiting organ (57) along at least three mutually perpendicular directions.
F16L 3/205 - Supports pour tuyaux, pour câbles ou pour conduits de protection, p. ex. potences, pattes de fixation, attaches, brides, colliers avec disposition particulière permettant au tuyau de bouger permettant un mouvement latéral avec des ressorts supportant les tuyaux
F16F 7/116 - Amortisseurs de vibrationsAmortisseurs de chocs utilisant un effet d'inertie l'élément d'inertie étant monté de manière élastique sur des ressorts métalliques
F16F 7/14 - Amortisseurs de vibrationsAmortisseurs de chocs du type support de câble, c.-à-d. des câbles formant des boucles en prise par friction
100.
THERMAL INSULATION ELEMENT, AND ASSEMBLY COMPRISING SUCH AN ELEMENT
The thermal insulation element (7) comprises: - a substantially air-tight longitudinal flexible tube (9) made of metal; - an elastic member (11) that is made of metal and is placed inside the tube (9).
G21C 11/08 - Écrans thermiquesRevêtements thermiques, c.-à-d. pour dissiper la chaleur provenant de radiations gamma qui sans cela chaufferaient un écran biologique externe
