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 - Alloys based on nickel or cobalt based on nickel with chromium
C22F 1/10 - Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working of nickel or cobalt or alloys based thereon
09 - Scientific and electric apparatus and instruments
37 - Construction and mining; installation and repair services
42 - Scientific, technological and industrial services, research and design
Goods & 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.
3.
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).
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & 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 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & 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 - Scientific and electric apparatus and instruments
37 - Construction and mining; installation and repair services
42 - Scientific, technological and industrial services, research and design
Goods & 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.
7.
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 - Casings; Jackets characterised by their material, e.g. alloys
G21C 21/02 - Manufacture of fuel elements or breeder elements contained in non-active casings
C23C 14/16 - Metallic material, boron or silicon on metallic substrates or on substrates of boron or silicon
C23C 28/00 - Coating for obtaining at least two superposed coatings either by methods not provided for in a single one of main groups , or by combinations of methods provided for in subclasses and
C23C 30/00 - Coating with metallic material characterised only by the composition of the metallic material, i.e. not characterised by the coating process
H01J 37/34 - Gas-filled discharge tubes operating with cathodic sputtering
8.
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).
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 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements
G21C 3/33 - Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles
B01D 29/01 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups ; Filtering elements therefor with flat filtering elements
B01D 35/02 - Filters adapted for location in special places, e.g. pipe-lines, pumps, stop-cocks
11.
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 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements
G21C 3/33 - Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles
B01D 35/02 - Filters adapted for location in special places, e.g. pipe-lines, pumps, stop-cocks
B01D 29/01 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups ; Filtering elements therefor with flat filtering elements
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 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
G21C 13/028 - Seals, e.g. for pressure vessels or containment vessels
G21C 19/20 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
13.
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 - Certifying or maintaining trusted computer platforms, e.g. secure boots or power-downs, version controls, system software checks, secure updates or assessing vulnerabilities
14.
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.
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 or insulators, e.g. for electric cables
G21C 19/02 - Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel - Details of handling arrangements
G21C 19/19 - Reactor parts specifically adapted to facilitate handling, e.g. to facilitate charging or discharging of fuel elements
G21C 19/20 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
20.
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.
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.
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & 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
24.
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 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
26.
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 - Investigating or analysing materials by the use of ultrasonic, sonic or infrasonic waves; Visualisation of the interior of objects by transmitting ultrasonic or sonic waves through the object - Details
B06B 1/06 - Processes or apparatus for generating mechanical vibrations of infrasonic, sonic or ultrasonic frequency making use of electrical energy operating with piezoelectric effect or with electrostriction
27.
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 - Shaped ceramic products characterised by their composition; Ceramic compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on oxides based on zirconium or hafnium oxides or zirconates or hafnates
28.
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).
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 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements
G21C 3/33 - Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles
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 - Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles
32.
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 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material
G21D 3/10 - Regulation of any parameters in the plant by a combination of a variable derived from neutron flux with other controlling variables, e.g. derived from temperature, cooling flow, pressure
09 - Scientific and electric apparatus and instruments
16 - Paper, cardboard and goods made from these materials
20 - Furniture and decorative products
35 - Advertising and business services
42 - Scientific, technological and industrial services, research and design
Goods & 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 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
G21C 13/032 - Joints between tubes and vessel walls, e.g. taking into account thermal stresses
G21C 13/036 - Joints between tubes and vessel walls, e.g. taking into account thermal stresses the tube passing through the vessel wall, i.e. continuing on both sides of the wall
35.
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.
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 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor
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 - Spacer grids being provided with fuel element supporting members
39.
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.
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 - Complex mathematical operations for solving equations
G06F 30/28 - Design optimisation, verification or simulation using fluid dynamics, e.g. using Navier-Stokes equations or computational fluid dynamics [CFD]
43.
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.
The inspection system comprises a supporting device (20) for supporting the fuel pellet(s) (4) such that the pellet axis (A) of each fuel pellet (4) coincides with a reference axis (B), and an optical measuring device (40) arranged for optically measuring the fuel pellet(s) (4), the optical measuring device (40) comprising a light emitter (42) configured for emitting a light beam propagating along an optical axis (C) and a light detector (46) arranged for receiving the light beam (44), wherein each fuel pellet (4) interrupts the light beam (44) and generates a shadow projected on the light detector (46), the optical measuring device (40) comprising a measuring module (48) configured for analyzing the shadow for detecting possible defects on the end faces (10) and/or the lateral face (8) of each fuel pellet (4).
The 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.
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 - Manufacture of fuel elements or breeder elements contained in non-active casings
B23K 11/00 - Resistance welding; Severing by resistance heating
B23K 11/093 - Seam welding not restricted to one of the preceding subgroups for curved planar seams
B23K 11/16 - Resistance welding; Severing by resistance heating taking account of the properties of the material to be welded
B23K 11/18 - Resistance welding; Severing by resistance heating taking account of the properties of the material to be welded of non-ferrous metals
C23C 30/00 - Coating with metallic material characterised only by the composition of the metallic material, i.e. not characterised by the coating process
C23C 28/02 - Coating for obtaining at least two superposed coatings either by methods not provided for in a single one of main groups , or by combinations of methods provided for in subclasses and only coatings of metallic material
F16L 57/06 - Protection of pipes or objects of similar shape against external or internal damage or wear against wear
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 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
G21C 19/26 - Arrangements for removing jammed or damaged fuel elements or control elements; Arrangements for moving broken parts thereof
01 - Chemical and biological materials for industrial, scientific and agricultural use
Goods & 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 - Chemical and biological materials for industrial, scientific and agricultural use
Goods & 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
50.
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).
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 - Chemical and biological materials for industrial, scientific and agricultural use
06 - Common metals and ores; objects made of metal
07 - Machines and machine tools
40 - Treatment of materials; recycling, air and water treatment,
42 - Scientific, technological and industrial services, research and design
Goods & 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 - Chemical and biological materials for industrial, scientific and agricultural use
06 - Common metals and ores; objects made of metal
07 - Machines and machine tools
40 - Treatment of materials; recycling, air and water treatment,
42 - Scientific, technological and industrial services, research and design
Goods & 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.
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).
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 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & 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.
58.
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 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & 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.
60.
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 - Apparatus for bringing fuel elements to the reactor charge area, e.g. from a storage place
G21C 19/32 - Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage place; Apparatus for handling radioactive objects or materials within a storage place or removing them therefrom
B66C 19/00 - Cranes comprising trolleys or crabs running on fixed or movable bridges or gantries
G21C 19/02 - Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel - Details of handling arrangements
09 - Scientific and electric apparatus and instruments
38 - Telecommunications services
Goods & 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.
62.
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.
G21C 19/20 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
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 - Means for moving control elements to desired position
G21C 13/036 - Joints between tubes and vessel walls, e.g. taking into account thermal stresses the tube passing through the vessel wall, i.e. continuing on both sides of the wall
G21C 13/067 - Sealing-plugs for tubes, e.g. standpipes; Locking devices for plugs
68.
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).
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).
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 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements
G21C 3/33 - Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles
G21C 21/00 - Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
B01D 29/01 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups ; Filtering elements therefor with flat filtering elements
B01D 39/10 - Filter screens essentially made of metal
B01D 46/10 - Particle separators, e.g. dust precipitators, using filter plates, sheets or pads having plane surfaces
B28B 1/00 - Producing shaped articles from the material
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 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements
G21C 3/33 - Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles
G21C 21/00 - Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
B01D 29/01 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups ; Filtering elements therefor with flat filtering elements
B01D 39/10 - Filter screens essentially made of metal
B01D 46/10 - Particle separators, e.g. dust precipitators, using filter plates, sheets or pads having plane surfaces
B28B 1/00 - Producing shaped articles from the material
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 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements
G21C 3/322 - Means to influence the coolant flow through or around the bundles
G21C 7/08 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
74.
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.
01 - Chemical and biological materials for industrial, scientific and agricultural use
Goods & 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 - Chemical and biological materials for industrial, scientific and agricultural use
Goods & 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 - Chemical and biological materials for industrial, scientific and agricultural use
Goods & 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 - Chemical and biological materials for industrial, scientific and agricultural use
Goods & 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
79.
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 - Investigating or analysing materials by the use of electric, electrochemical, or magnetic means by investigating magnetic variables for investigating the presence of flaws
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 - Chemical and biological materials for industrial, scientific and agricultural use
06 - Common metals and ores; objects made of metal
Goods & Services
Ceramics for nuclear components; metal oxide for nuclear
components. Unworked and semi-worked metals and their alloys used in the
nuclear energy industries.
84.
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).
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 - Relative disposition of the elements in the bundle lattice
G21C 5/18 - Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone
G21C 3/326 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; Comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
01 - Chemical and biological materials for industrial, scientific and agricultural use
06 - Common metals and ores; objects made of metal
Goods & 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
87.
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 - Investigating or analysing materials by the use of electric, electrochemical, or magnetic means by investigating magnetic variables for investigating the presence of flaws using eddy currents
88.
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 for pipes, cables or protective tubing, e.g. hangers, holders, clamps, cleats, clips, brackets with special provision allowing movement of the pipe allowing movement in transverse direction having supporting springs
F16F 7/116 - Vibration-dampers; Shock-absorbers using inertia effect the inertia member being resiliently mounted on metal springs
F16F 7/14 - Vibration-dampers; Shock-absorbers of cable-support type, i.e. frictionally-engaged loop-forming cables
90.
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).
The method comprises the following steps: - obtaining a fitting (1) comprising a tubular body (3) internally defining a longitudinal passage (5) for fluid flow and having first and second longitudinal ends (7, 9), and permanent fastenings (11, 3) for fastening, in a non-detachable manner, the first and second longitudinal ends (7, 9) to the tubes; - fastening of a first tube (15, 51, 63) to the first longitudinal end (7); - fastening of a second tube (17, 53, 57) to the second longitudinal end (9), the first tube (15, 51, 63) being in fluid communication with the second tube (17, 53, 7) via the longitudinal passage (5) of the tubular body (3) of the fitting (1).
F16L 13/14 - Non-disconnectable pipe joints, e.g. soldered, adhesive, or caulked joints made by plastically deforming the material of the pipe, e.g. by flanging, rolling
F16L 55/16 - Devices for covering leaks in pipes or hoses, e.g. hose-menders
92.
METHOD AND DEVICE FOR MEASURING THE CONCENTRATION OF HYDROGEN PEROXIDE
The measuring method comprises the following steps: - injecting a continuous flow of the liquid into a cell (21) which contains a catalyst (23) which is suitable for catalysing the decomposition of the hydrogen peroxide; - measuring the quantity of oxygen and the quantity of carbon dioxide in a stationary state in the gas flow produced by the cell (21); - establishing the concentration of hydrogen peroxide in the liquid using the quantity of oxygen measured and the quantity of carbon dioxide measured.
G01N 7/18 - Analysing materials by measuring the pressure or volume of a gas or vapour by allowing the material to emit a gas or vapour, e.g. water vapour, and measuring a pressure or volume difference by allowing the material to react
G01N 33/00 - Investigating or analysing materials by specific methods not covered by groups
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 linear guide (11) connecting the dynamic mass (7) to the mounting bracket (5), such that the dynamic mass (7) is freely movable in a given direction with respect to the mounting bracket (5); - 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) along said given direction are damped by the resilient damper (13).
The method comprises inserting the fuel rod (4) through the spacer grids (14) aligned along an assembling axis (A) with passing the fuel rod (4) through a lubrication chamber (30) aligned with the spacer grids (14) such that the lubrication chamber (30) is passed through by the fuel rod (4) before the insertion of the fuel rod (4) through one of the spacer grids (14), and circulating a lubrication fluid containing a gas and a lubricant in gaseous phase and/or mist form in the lubrication chamber (30), the lubrication fluid being injected in the lubrication chamber (30) at a temperature strictly higher than ambient temperature, such that lubricant deposits or condensates in liquid phase with forming a lubricant film on an external surface of the fuel rod (4) that is being inserted through said one of the spacer grids (14).
The present invention relates to welding torches (1) that comprise a head (3) having a body (11) bearing an electrode (13), a source of electric current (27), a metal filler wire and a wire guide (19) guiding the metal filler wire to the electrode (13), the body (11) being obtained by additive manufacturing from an electrically conductive metal and the wire guide (19) comprising an insulating sheath (29) inside which the metal filler wire moves.
B22F 3/105 - Sintering only by using electric current, laser radiation or plasma
B22F 5/10 - Manufacture of workpieces or articles from metallic powder characterised by the special shape of the product of articles with cavities or holes, not otherwise provided for in the preceding subgroups
The conversion process comprises steps of hydrolysis of UF6 to uranium oxyfluoride (UO2F2) in a hydrolysis reactor (4) by reaction between gaseous UF6 and dry steam which are injected into the reactor (4), and of pyrohydrolysis of the UO2F2 to UO2 in a pyrohydrolysis furnace (6) by reaction of the UO2F2 with dry steam and dihydrogen (H2) gas which are injected into the furnace (6). The hourly mass flow rate for feeding the reactor (4) with gaseous UF6 is between 75 and 130 kg/h, the hourly mass flow rate for feeding the reactor (4) with dry hydrolysis steam is between 15 and 30 kg/h, and the temperature in the reactor (4) is between 150 and 250°C.
6222222222) injected into the furnace (6), extracting excess gas in the reactor (4) via a capture device (50) comprising a plurality of filters (52), periodic unclogging of the filters (52) by injection of a neutral gas into the filters (52) from the outside to the inside of the reactor (4) in order to unstick powder stuck on the filters (52), and measuring the relative pressure in the reactor (4), the conversion method further comprising the implementation of an intermittent unclogging of the filters (52) when the relative pressure in the reactor (4) exceeds a predetermined intermittent unclogging threshold.
62622222622, and a control system (16) configured to control the supply device (8) in such a way as to supply at least one of the reagent injection pipes (10) with a neutral gas during a phase of stopping or starting the conversion installation.
The method comprises the following steps: - acquisition of a plurality of quantities characterizing the operation of the nuclear reactor; - calculation of at least one critical thermal flux ratio with the aid of a deep neural network, the inputs of the deep neural network being determined by using the quantities acquired, the deep neural network comprising at least two hidden layers of at least five neurons each; - calculation of the disparities between the at least one critical thermal flux ratio calculated and a plurality of predetermined reference threshold values; - formulation of a command signal for a control system of the reactor, by using the disparities calculated, the command signal being: * automatic shutdown of the reactor or alarm; * do nothing; - emergency shutdown of the nuclear reactor or emission of an alarm signal if relevant.
